ML15244A709
| ML15244A709 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Catawba  |
| Issue date: | 01/14/1992 |
| From: | Rosenthal J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Novak T NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| Shared Package | |
| ML15244A710 | List: |
| References | |
| TASK-AE, TASK-T92-01, TASK-T92-1 AEOD-T92-01, AEOD-T92-1, NUDOCS 9201210088 | |
| Download: ML15244A709 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION C,
!q/3 WASHINGTON, D. C. 20555 JAN 14 1992 MEMORANDUM FOR:
Thomas M. Novak, Director Division of Safety Programs Office for Analysis and Evaluation of Operational Data FROM:
Jack E. Rosenthal, Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data
SUBJECT:
TECHNICAL REVIEW REPORT-ENHANCED SETPOINT TESTING PROCEDURES FOR PRESSURIZER SAFETY VALVES AT OCONEE AND CATAWBA The Duke Power Company reported that as-found setpoint tests of pressurizer safety valves (PSVs) from Oconee and Catawba had revealed three valves whose setpoint exceeded the nominal +/- 1 percent psig allowed by technical specification (TS).
Duke's investigation into the cause for setpoint deviation produced several possible causes.
After evaluation, they took actions to resolve them; particularly, they recognized that the remedies for leakage could affect the valve setpoint and required retest of the valve subsequent to polishing the disc and seat.
Both the Westinghouse Owner's Group actions to accommodate the effects of a water-filled loop seal discussed in AEOD T91-05 and Duke's actions to remedy leakage detailed in this report have improved the understanding of the role that setpoint testing plays in determining an accurate setpoint for spring-actuated safety valves. They are a demonstration of individual efforts now underway by the nuclear industry to resolve the safety valve setpoint problems.
Both show that carefully controlled testing procedures produce better testing results.
This technical review report is the product of an investigation which began with a trip to Charlotte, N.C. to discuss the problem with Duke, NRR, and Region II and a followup trip 160121 9201210088 920114 PDR ADOCK 05000269 PDR PDR _
Thomas M. Novak
-2 to Wyle Laboratories to witness a valve test. Duke demonstrates that stricter controls on procedures used in refurbishment and retesting can give better results.
Of ltiafsilgned by Jack E. Rosenthal Jack E. Rosenthal, Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated cc:
S. Hart, Duke Power Company J. Carbonneau, Wyle Laboratories Distribution:
PDR VBenaroya AChaffee, NRR Central File LSpessard PLewis, INPO ROAB R/F GZech DQueener, NOAC MWegner SRubin VChexal, EPRI EBrown PBaranowsky GHammer, NRR JRosenthal KBlack FCherney, RES EJordan RSavio, ACRS EGirard, RH DRoss MTaylor, EDO FJape, RII TNovak KRaglin, TTC
- See previous concurrence ROAB:DSP:AEOD ROAB:DSP:AEOD 9'FOAB:DSP:AEOD MWegner:rgz EBrown JRosenthal 11/13/91*
11/14/91*
1W 2
Thomas M. Novak
-2 to Wyle Laboratories to witness a valve test. Duke demonstrates that stricter c ntrols on procedures used in refurbishment and retesting can give better results.
Jack E. Rosenthal, Chief Reactor Operations/Analysis Branch Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated Distribution:
PDR EJord SRubin AChaffee, NRR Central File DRos PBaranowsky PLewis, INPO ROAB R/F TN yak KBlack DQueener, NOAC MWegner V enaroya RSavio, ACRS VChexal, EPRI EBrown pessard MTaylor, EDO JRosenthal GZech KRaglin, TTC R AB:DSP:AEOD ROAB:DSP:AEOD C:ROAB:DSP:AEOD egne rrQmk EBrown JRosenthal 11/j3/9 I11/1l91 11/ /91