Headquarters Daily Report
MARCH 19, 2002
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REPORT NEGATIVE NO INPUT
ATTACHED INPUT RECEIVED RECEIVED
HEADQUARTERS X
REGION I X
REGION II X
REGION III X
REGION IV X
PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS MARCH 19, 2002
MR Number: H-02-0018
NRR DAILY REPORT ITEM
GENERIC COMMUNICATIONS
Subject: Issuance of Bulletin 2002-01
NRC Bulletin 2002-01: Reactor Pressure Vessel Head Degradation and
Reactor Coolant Pressure Boundary Integrity dated March 18, 2002
The U.S. Nuclear Regulatory Commission (NRC) is issuing this bulletin to
require pressurized-water reactor addressees to submit:
(1) information related to the integrity of the reactor coolant pressure
boundary including the reactor pressure vessel head and the extent to
which inspections have been undertaken to satisfy applicable regulatory
requirements, and
(2) the basis for concluding that plants satisfy applicable regulatory
requirements related to the structural integrity of the reactor coolant
pressure boundary and future inspections will ensure continued compliance
with applicable regulatory requirements, and
(3) a written response to the NRC in accordance with the provisions of
Title 10, Section 50.54(f), of the Code of Federal Regulations (10 CFR
50.54(f)) if they are unable to provide the information or they can not
meet the requested completion dates.
ADAMS Accession No.: ML020770497
Technical Contact: Kenneth J. Karwoski, NRR
301-415-2752
E-mail: kjk1@nrc.gov
Lead Project Manager: Steven D. Bloom, NRR
301-415-1313
E-mail: sdb1@nrc.gov
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REGION II MORNING REPORT PAGE 2 MARCH 19, 2002
Licensee/Facility: Notification:
Duke Power Co. MR Number: 2-02-0004
Oconee 1 2 3 Date: 03/19/02
Seneca,South Carolina
Dockets: 50-269,50-270,50-287
PWR/B&W-L-LP,PWR/B&W-L-LP,PWR/B&W-L-LP
Subject: POTENTIAL LOSS OF SAFE SHUTDOWN CAPABILITY - OCONEE (UPDATE)
Reportable Event Number: 38754
Discussion:
This is an update to Event Report Number 38754. On March 7, 2002, Duke
Energy reported that the capacity of the pressurizer heaters which are
supplied power from the standby shutdown facility (SSF) may be
insufficient to compensate for heat losses from the pressurizer during
events where the SSF is used to achieve safe shutdown. As an interim
compensatory measure for those specific events, the licensee has modified
the SSF abnormal procedure to establish water solid conditions in the
pressurizer as a means for controlling reactor coolant system (RCS)
pressure sufficient to maintain RCS subcooling margin. All three units
have continued to remain at full power.
Regional Action:
Under the guidance of NRC Management Directive 8.3, Region II initiated a
Special Inspection at the site on March 19, 2002. The specific issue of
concern to be addressed by the Special Inspection Team is whether the SSF
will perform its design basis function with the compensatory measure in
effect.
Contact: Robert Haag (404)562-4550
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