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Significance:
Jun 30, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
FAILURE TO PROPERLY IMPLEMENT MATERIAL CONTROL PROCEDURES
The inspectors identified a performance deficiency involving a NCV of Technical Specifications 5.4.1, related to the unauthorized and improper storage of loose material in the designated material exclusion area around the Unit 1 and Unit 2 transformers. The inspectors identified this issue on a number of occasions. After each occurrence, the licensee took immediate corrective actions by either removing loose material out of the transformer yard or properly securing the material being stored in the transformer yards.
The inspectors concluded that the finding was more than minor because loose/unsecured material in the transformer yards increased the likelihood of those events occurring that could upset plant stability. Specifically, during high wind speed conditions the loose material could have affected the main power transformers and could have caused a unit trip or it could have affected the station auxiliary transformers that could increase the likelihood of a loss of mitigating systems. In each case however, the inspectors concluded that there was not enough debris in either area to affect both transformers simultaneously. The finding was determined to be of very low safety significance because it did not contribute to both the likelihood of a reactor trip and the likelihood that mitigating equipment or functions would not be available. The primary cause of this NCV was related to the cross-cutting aspect in the area of Human Performance in the Work Practices component (Item H.4.(b)). Multiple groups, including contractors and operators failed to properly implement the procedures for control of material in the transformer exclusion zones. The preliminary cause appeared to be inadequate supervisory and management oversight of work activities.
Inspection Report# : 2008003 (pdf)
Significance: Jun 30, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
INADEQUATE PROCEDURE
The inspectors identified a performance deficiency involving a NCV of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix B, Criterion V, “Instructions, Procedures, and Drawings,” related to a plant barrier impairment (PBI) procedure. The procedure for PBI did not contain steps to ensure that relied-upon compensatory measures were maintained. Specifically, while the B Train room of essential service water had a flood barrier removed and covered under a PBI, the compensatory measure of sump alarms were found not functioning. The licensee has entered the issue into their corrective action program, repaired the sump alarms, and plans to revise the PBI procedure. The inspectors concluded that the finding was greater than minor because the licensee failed to effectively manage prescribed compensatory measures related to a cornerstone objective. The finding was determined to be of very low safety significance based on a SDP Phase 1 screening in accordance with IMC 0609, Table 4a, because the finding did not increase the likelihood of an external or internal flood. The primary cause of this NCV was related to the cross-cutting component of Human Performance for Resources (Item H.2.(c)) because the licensee’s PBI procedure was not adequate in that it did not ensure safety margins were maintained by providing instructions to periodically verify that the compensatory measures were still available.
Inspection Report# : 2008003 (pdf)
Significance: Jun 30, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
FAILURE TO CONTROL LABELING ON BOTH UNITS CONTROL PANELS AND SIMULATOR
The inspectors identified a performance deficiency involving a NCV of Technical Specifications 5.4.1, for the licensee’s failure to provide procedural controls for the unique identification of Regulatory Guide 1.97 post accident instrumentation to aid the control room operator. Specifically, the licensee failed to adequately control the labeling on both units’ control panels and the simulator, resulting in several improperly marked post-accident indicators. The licensee has entered the issue into their corrective action program and labeled the appropriate post-accident instruments. The finding was greater than minor because, if left uncorrected, it could become a more significant safety concern. Inaccurately labeled control room indicators of post-accident instrumentation could lead to confusion and hamper operator response if conflicting indications resulted due to accident conditions. The finding was determined to be of very low safety significance based on a SDP Phase 1 screening in accordance with IMC 0609.04, “Initial Screening and Characterization of Findings.” The inspectors did not identify a cross-cutting aspect to this finding.
Inspection Report# : 2008003 (pdf)
Significance: Mar 28, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
This is a security Related Finding - see inspection report for details.
This finding, affecting the Mitigating Systems Cornerstone, is related to mitigative measures developed to cope with losses of large areas of the plant; in respons to Section B.5.b of the February 25, 2002, Interim Compensatory Measures (ICM) Order (EA-02-026) and related NRC guidance. This finding has been designated as "Official Use Only - Security-Related Information": therefore, the details of this findng are being withheld from public disclosure. This finding has a cross-cutting aspect in the area of Human Performance - conservative assumptions and safe actions. See inspection report for more details.
Inspection Report# : 2008006 (pdf)
Significance: Dec 31, 2007
Identified By: NRC
Item Type: NCV NonCited Violation
FAILURE TO PERFORM AN EVALUATION ON A BOLTED CONNECTION
The inspectors identified a Non-Cited Violation of 10 CFR 50.55a(a)(3)(i) for failure to apply an approved alternative to the American Society of Mechanical Engineers Code to evaluate susceptibility of bolting corrosion and the potential for failure after identifying leakage at residual heat exchanger flow control valve assembly, valve 2RH606, bolted connection. The primary cause of this failure was related to the cross cutting component of Human Performance, Work Practices (Item H.4.(b) of IMC 0305) because licensee personnel failed to follow procedures. As part of its corrective actions, the licensee performed a review of 160 bolted-connection boric acid leaks and identified 47 similar examples (including 2RH606). The licensee planned to assign a work group evaluation to determine the appropriate additional corrective actions. The finding was more than minor because it met the criteria in IMC 0612, Appendix E, “Examples of Minor Issues,” Example 4a. Specifically, the licensee routinely failed to perform/document engineering evaluations to evaluate bolted connections with boric acid leaks. The issue was of very low safety significance based on Phase 1 screening in accordance with IMC 609, Appendix A, “Significance Determination of Reactor Inspection Findings for At-Power Situations.” Specifically, no failures of American Society of Mechanical Engineers Code bolted connections had actually occurred due to a failure to perform this evaluation.
Inspection Report# : 2007006 (pdf)
Significance: Aug 24, 2007
Identified By: NRC
Item Type: NCV NonCited Violation
Inadequate test control for safety-related heat exchangers
The inspectors identified a finding having very low significance and an associated NCV of 10 CFR Part 50, Appendix B, Criterion XI, “Test Control,” related to the failure to establish a formal heat exchanger testing program capable of identifying an unacceptable condition of the safety related cubicle coolers. Specifically, prior to 2003, the licensee’s program lacked formalized acceptance criteria. The current program did not provide guidance on how to translate design information into acceptance criteria or guidance on quantifying the results of the examinations.
Inspection Report# : 2007009 (pdf)
Significance: Aug 24, 2007
Identified By: NRC
Item Type: NCV NonCited Violation
Inadequate safety-related heat exchanger examination procedure
The inspectors identified a finding of very low safety significance involving a Non-Cited Violation of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," with regard to the licensee’s heat exchanger examination procedure. Specifically, the procedure was inappropriate to ensure that the safety-related heat exchangers were satisfactorily inspected and evaluated. Upon discovery, the licensee initiated an evaluation to determine the operability of the affected heat exchangers.
Inspection Report# : 2007009 (pdf)
Significance: Aug 24, 2007
Identified By: NRC
Item Type: NCV NonCited Violation
Failure to take corrective action
The inspectors identified a Non-Cited Violation of 10 CFR Part 50, Appendix B, Criterion XVI, “Corrective Action,” having very low safety significance. Specifically, the inspectors determined that the licensee failed to identify that operability of the AFW pump room coolers would not be supported above 100°F and subsequently correct the condition when the allowable heat sink temperature was raised. The licensee performed a preliminary calculation and determined the coolers remained operable.
Inspection Report# : 2007009 (pdf)
Significance: May 15, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
INADEQUATE ACCEPTANCE CRITERIA ESTABLISHED IN TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT
A finding of very low safety significance and associated Non-Cited Violation of 10 CFR 50, Appendix B, Criterion V, Instructions Procedures and Drawings was identified by the inspectors for the licensee’s failure to establish adequate acceptance criteria when performing a surveillance required by the plant’s Technical Specifications. Specifically, acceptance criteria ensuring airflow flow from areas of low potential contamination to areas of high potential contamination when performing Technical Specification Surveillance Requirement 3.7.12.4 associated with the nonaccessible area exhaust filter plenum ventilation system in the auxiliary building was not established. The licensee has entered the issue into its corrective action program and intend establish qualitative criteria verifying air flow into spaces containing potential contaminated fluids during post accident conditions. This finding was more than minor because it affected the radiological barrier functionality of the control room and auxiliary building attribute under the barrier integrity cornerstone. The finding was of very low safety significance because all the answers were no to the SDP screening associated with the Barrier’s Cornerstone.
Inspection Report# : 2008002 (pdf)
Significance: Mar 28, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
This is a security Related Finding - see inspection report for details.
This finding, affecting the Barrier Integrity Cornerstone, is related to mitigative measures developed to cope with losses of large areas of the plant; in respons to Section B.5.b of the February 25, 2002, Interim Compensatory Measures (ICM) Order (EA-02-026) and related NRC guidance. This finding has been designated as "Official Use Only - Security-Related Information": therefore, the details of this findng are being withheld from public disclosure. This finding has a cross-cutting aspect in the area of Human Performance - documentation, procedures, and component labeling. See inspection report for more details.
Inspection Report# : 2008006 (pdf)
Significance: Sep 30, 2007
Identified By: NRC
Item Type: NCV NonCited Violation
Failure to Meet TRM Requirements for Spent Fuel Building Crane Interlocks and Physical Stops (1R20)
A finding of very low safety significance and associated Non-Cited Violation of Technical Specification 5.4.1 was identified by the inspectors for failure to have and follow procedures, which met the surveillance requirements of Technical Requirements Manual (TRM), Section 3.9.d.1. Specifically to verify that both the spent fuel pool crane electrical interlocks and physical stops were operable, with the purpose to prevent crane travel with loads greater than 2000 pounds over fuel assemblies. This was required to be completed within seven days prior to crane use. The inspectors identified that loads greater than 2000 pounds were regularly moved with the crane with the electrical interlocks bypassed and the physical stops removed.
The finding was greater than minor because, if left uncorrected, it could have become more significant as additional heavy loads were moved with no interlocks in place. The finding affected the attribute of maintaining functionality of spent fuel cladding in the Barrier Integrity cornerstone. Using the SDP Phase 1 Screening Worksheet of IMC 0609, the inspectors determined that the finding screened as Green because it only affected the fuel barrier. The licensee entered the issue into its corrective action program, temporarily suspended crane operation, and modified its procedures and practices to meet the TRM. The finding had a cross-cutting aspect in the area of Human Performance in the work practices component. Personnel failed to follow the TRM because implementing procedures did not require both the electrical interlocks and physical stops to be in place within seven days prior to crane use (H.4(b)).
Inspection Report# : 2007005 (pdf)
Significance: Jun 30, 2008
Identified By: NRC
Item Type: NCV NonCited Violation
FAILURE TO SAMPLE A TEMPORARY TANK AT THE REQUIRED PERIODICITY
A finding of very low safety significance and associated NCV of the Technical Requirements Manual, Appendix L, and Technical Specifications 5.4.1(a) were identified by the inspectors. On May 1, 2008, the inspectors identified that the licensee had failed to sample the temporary wastewater storage tanks installed to hold shower and wash water from the Unit 2 Containment Access Facility at the required frequency of seven days. Procedure RP-BR-654, “Unit 1(2) Containment Access Facility Liquid and Air Sampling and Disposal Requirements, Revision 0,” as written, did not direct the required sampling frequency. The licensee took immediate corrective action by sampling the temporary storage tank, revising the scheduling tool to ensure that the tanks are sampled at least every seven days when radioactive material is being added to the tank, and planning to revise the sampling procedure. The finding involved an occurrence in the licensee's radioactive material control program that is contrary to the licensee’s procedures. The finding was more than minor because it impacted the program and process attribute of the Public Radiation Safety Cornerstone and affected the cornerstone objective to ensure adequate protection of public health and safety from exposure to radioactive material release into the public domain, in that the failure to measure the levels of radioactivity in the temporary storage tanks had the potential to impact the licensee’s effluent program. The inspectors applied the IMC 0609, Appendix D, “Public Radiation Safety Significance Determination Process” to this finding. The finding is in the licensee’s radiological effluent monitoring program. The finding did not involve a failure to implement the effluent release program nor did public dose exceed Appendix I, Criterion, or 10 CFR 20.1302(e) and the finding was determined to be of very low safety significance. The primary cause of this NCV was related to the cross-cutting component of Human Performance for Work Practices (Item H.4.(c)) because the licensee did not ensure that supervisory and management oversight of the procedure was adequate to assure nuclear safety.
Inspection Report# : 2008003 (pdf)
Although the NRC is actively overseeing the Security cornerstone, the Commission has decided that certain findings pertaining to security cornerstone will not be publicly available to ensure that potentially useful information is not provided to a possible adversary. Therefore, the cover letters to security inspection reports may be viewed.
Last modified : August 29, 2008