ML20133G707

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Forwards for Review Plant Restart Equipment Issues
ML20133G707
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/12/1996
From: Martin T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Russell W, Taylor J
NRC (Affiliation Not Assigned), NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML20133F923 List:
References
FOIA-96-351 NUDOCS 9701160132
Download: ML20133G707 (7)
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go.* 88cg f *, UNITED STATES 5

y g NUCLEAR REGULATORY COMMISSION '

l Ta Ej REGloN I o, c 475 ALLENDALE ROAD

%....e[ KING of PRUSSIA, PENNSYLVANIA 19406 1415 January 12, 1996 i MEMORANDUM T0: James M. Taylor Executive Director for Operations William T. Russell, Director 4 Office of Nuclear Reactor Regulation i

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SUBJECT:

SALEM RESTART EQUIPMENT ISSUES

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l' The purpose of this memorandum is to communicate the equipment issues we are tracking and intend to independently inspect at the Salem Units 1 and 2 i nuclear power plants. I have appended a copy of these key issues for your review (Attachment 1). '

As you know, the licensee shutdown both Salem units, and I issued a Confirmatory Action Letter (CAL) on June 9, 1995, to address continued performance deficiencies, poor materiel condition, and weak management oversight. A Salem Assessment Panel (SAP) was chartered and has been tasked with monitoring restart activities in accordance with NRC Manual Chapter 0350.

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i In response to a request from the June 1995 Senior Management Meeting, I tasked the regional and resident staff with identifying equipment deficiencies 1 that had a significant effect on Salem performance. During their review, my i

staff considered: (1) the findings of all 1994 and 1995 inspection reports; (2) all 1994 and 1995 escalated and non-escalated violations; (3) all 1994 and 1995 Inspection Followup System open items; (4) all 1994 and 1995 LERs; (5) the two most recent SALPs; and (6) licensee work history, equipment performance, and trend indicators. Through their review of the above sources of data and other sources, they identified the equipment issues listed in Attachment 1. The SAP performed an independent review of these equipment issues and confirmed that the licensee's Restart Action Plan list encompasses the items on the NRC list.

On December 11, PSE&G presented their restart plan to key members of the regional and headquarters staff. During the development of their plan, PSE&G determined that eight systems have caused 45 of the 54 forced outages since s 1988. A listing of these systems is included with this memorandum (Atta.chment 2). In addition, affected NRC personnel met with the public at the Salem Community College in Carneys Point, New Jersey to solicit their input. These 4

interactions, as well as equipment and other performance insights, will be

used by the SAP to develop the final NRC Salem Restart Inspection Plan.

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i 9701160132 970113 PDR FOIA O'NEILL96-351 PDR

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! Distribution w/ Attachments:

W. Kane, DRA j R. Cooper, DRP

. L. Nicholson, DRP S. Barber, DRP

' J. Stolz, NRR >

L. Olshan, NRR i C. Marschall, DRP

W. Dean, OED0 J. Zimmerman, NRR
M. Oprendek, DRP (RA Action Item 95-234) t

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l ATTACWlENT 2 1

SYSTDI & EQUIPRENT RELIABILITY Eight Systems caused 45 of the 54 Forced Outages Since 1988 d

, e Feed & Condensate l e Chemical & Volume Control e Circulating Water

! e Diesel Generator e Main Steam o Reactor Coolant

e Reactor Control & Protection j e Service Water 1

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Distribution w/ Attachments: t' W. Kane, DRA R.' Cooper, DRP  ;

L. Nicholson, DRP ,

! S. Barber, DRP 1 J. Stolz, NRR  ;

l L. Olshan, NRR t

c. Marschall, DRP t W. Dean, OEDO J. Zinnerman, NRR ,

M. Oprendek, DRP (RA Action Item 95-234) .

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ATTACHMENT 1 SALEM RESTART EQUIPMENT ISSUES TECHNICAL ISSUE Resp. Reference Status Org

1. Cont. Spray Dsch Viv (CS-2) DRS URI 92- Open Operability. Calculations indicate 01-04 actual d/p may be greater than design d/p.
2. Reliability of Control Air System. DRP IR 94-19, Open Requires operator action to start 24 & 35 backup compressor.
3. CW Screen Motor Reliability. No DRP IR 95-10 Open automatic motor operation, vulnerable to grass intrusion
4. Digital feedwater installation 'to DRS IR 94-13 Open, correct feedwater control reliability.
5. Moisture in EDG air start system DRP IR 94-19 Open causes reliability problem with check val ves .
6. EDG output breakers fail to close when DRS IR 95-10 Open switch taken to close.
7. EDG has minimal load margin. DRS URI 93- Open 82-04.
8. EDSFI Followup Issues DRS IR 93- Open 082.
9. Cracked exhaust steam piping could DRS No Open indicate weak erosion / control program. Reference
10. Feedwater nozzle bypass flow DRS URI 94- Open introduced error in calorimetric and 024-04 power level .
11. EDG 1A load fluctuations. DRS URI 94- Open 018-02
12. Review adequacy of fuse control DRS IR 95-10 Open program.
13. Review gas turbine batteries degrading DRS IR 95-13 Open with loss of one source of offsite power. Turbine referenced in TS basis to support SW outages.
14. Hagan module replacement project. DRS IR 94-80, Open 95-02.

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ATTACMENT 2 SYSTEM & EQUIPMENT RELIABILITY Eight Systems Caused 45 of the 54 Forced Outages Since 1988 ,

i e Feed & Condensate e Chemical & Volume Control e Circulating Water e Diesel Generator

,e e Main Steam 4 e Reactor Coolant e Reactor Control & Protection e Service Water l

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e Attachment 1 TECHNICAL ISSUE Resp. Reference Status A

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15. Procedure contains non-conservative DRS URI 94- Open 125V battery acceptance criteria. 18-01
16. NRC & QA identified numerous IST DRS URI 94- Open program deficiencies. 21-01, 02

& 03

17. Main condenser steam dumps DRP URI 94- Open  !

malfunction, requires closing MSIVs on 08-01 i trip and prevents use of main condensor.

18. Poor reliability of PDP charging DRP No Open pumps. Reference i
19. Poor process for configuration control DRP URI 95- Open of pipe supports. 06-01
20. POPS ability to mitigate overpressure DRS Vio 94- Open events. 032-05 i
21. Wiring separation & redundancy DRS URI 89- Open concerns with RG 1.97 instruments & 13-07 &

cable separation 90-81-13

22. PORV (IPRI) seat leakage, requiring DRP IR 94-35 Open block valve closure.
23. Undersized PORV accumulators DRS IR 95-13 Open
24. Gate valves identified susceptible to DRS URI 93- Open press lock & thermal binding. 026-01
25. Pressurizer Spray Problems /Use of Aux DRP IR 95-13 Open Spray
26. Radiation monitor problems DRS IR 94-24 Open
27. Rx coolant pump oil collection system DRS IR 94-33 Open deficiencies. & 94-35
28. Understand causes and corrective DRP IR 94-32 Open actions for failures of Rx coolant & 95-02 pump seals.
29. Rx Head Vent Valve Stoke Times DRP VIO 95-02 Open
30. RHR Min-flow Valve (RH29) Failures on DRP VIO 95-10 Open unit 2.
31. RHR Dsch Valve (21RH10) Banging Noise DRP IR 95-10 Open
32. Review program for control & DRS No Open inspecting resilient fire barrier Reference s eal s .

1 Attachment 1 4 TECHNICAL ISSUE Resp. Reference Status Ors

33. Control rods stepping with no DRS IR 94-19 Open temperature error signal.
34. Numerous SI pump deficiencies. DRP IR 95-13 Open
35. Verify adequate protection for SI Pump DRS IR 95-13. Open runnout.
36. SI relief valves performance history DRP IR 94-13, Open of leaking and lifting. 31 & 95-01
37. Review corrective action for service DRS IR 95-07 Open water pipe erosion.
38. Spurious high steam flow signals DRS EA #94- Open causing SI. 112-010103
39. Review corrective actions to r solve DRS IR 94-31 Open numerous switchyard failures.
40. Verify adequate correction for DRS IR 95-17 Open overhead annunciator failures.
41. Verify adequate corrective action to DRS IR 95-17 Open ensure steam generator tube integrity.

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