ML16342A033
| ML16342A033 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/29/1993 |
| From: | Peterson S Office of Nuclear Reactor Regulation |
| To: | Rueger G PACIFIC GAS & ELECTRIC CO. |
| Shared Package | |
| ML16342A034 | List: |
| References | |
| TAC-M82775, NUDOCS 9304020023 | |
| Download: ML16342A033 (12) | |
Text
~PR RKQ0~
Vp.0 o
'o $
++ p*+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554I001 March 29, i993 Docket No. 50-323 Hr. Gregory H. Rueger Nuclear Power Generation, B14A Pacific Gas and Electric Company 77 Beale Street, Room 1451 P.O.
Box 770000 San Francisco, California 94177
Dear Hr. Rueger:
SUBJECT:
SAFETY EVALUATION OF PACIFIC GAS AND ELECTRIC COMPANY'S (PG&E'S)
COMPLETION OF PREOPERATIONAL ENDURANCE TESTING OF THE SIXTH EMERGENCY DIESEL GENERATOR (EDG)
AT DIABLO CANYON POWER PLANT UNIT 2 (TAC NO. H82775)
By letter dated February 12, 1993, Pacific Gas and Electric Company (PG8E) documented the successful completion of the preoperational endurance testing of the 2-3 emergency diesel generator (EDG) and stated PG&E's basis for resolution of the open items and issues described in NRC Inspection Report (IR) 50-323/92-201.
The open items and issues
- were, in part, identified during the NRC's earliest inspection of PG&E (IR 50-323/91-202) and the inspection of PG8E's supplier of the power generator (NEI Peebles-Electric
- Products, Inc.
(P-EP), of Cleveland, Ohio (IR 99900772/91-01),
and NEI Peebles Limited, Peebles Electrical Machines (PEH), of Edinburgh, Scotland (IR 99901065/91-01)).
As stated in IR 50-323/92-01, closure of the issues identified during the inspections of PG8E, P-EP, and PEH was pending PG8E's successful completion of its compensatory actions taken as a result of the inspection findings.
Specifically, the actions included post-modification tests and inspections that would determine the adequacy of the 2-3 EDG's design, materials, and manufacturing processes.
These tests and inspections are expected to resolve the team's remaining concerns by evaluating the EDG during operating and transient conditions necessary to detect
- problems, and by subjecting certain components of the EDG to operating cycles which would likely result in premature cyclic fatigue failure if defects were present.
In the February 12, 1993 letter, PG&E stated that the open items identified in the summary section of IR 50-323/92-201, and associated with final evaluations and documentation for the Spare and Replacement Parts Evaluations (RPEs) for the diesel engine (M-6602) and the power generator (E-7505) are complete and have been incorporated into the RPEs.
PG8E also stated in its letter that the applicable Action Requests were complete, and the specific technical issues identified during these inspections were resolved by the successful completion of its compensatory actions taken as a result of the inspection findings and the post-modification tests.
According to PG&E, the post-modification tests 9304026023 930329 PDR ADOCK,05000323 (P
i '";aPDR p 'i'/Vlij)i'~JRU'iJ
0 r'
r,',i
~,g,"0 tl l l..
Hr. Gregory H. Rueger March 29, 1993 demonstrated the adequacy of the 2-3 EDG's design, materials, and manufacturing processes.
Therefore, PG&E has successfully demonstrated reasonable assurance that the 2-3 EDG is capable of performing its intended safety function.
The staff has also evaluated the malfunctions that occurred during performance of the endurance testing and has determined that these malfunctions did not affect qualification of the EDG..
Based on the staff's evaluation of the endurance testing and subsequent inspection results, which included visual and fiberscope inspections as well as disassembly and inspection of four power assemblies of the 2-3 EDG at DCPP Unit 2, we conclude that the endurance testing and associated post-test inspections have been completed in,a satisfactory manner.
Our safety evaluation is enclosed.
If you have any questions regarding this issue, please contact me.
Sincerely,
Enclosure:
Safety Evaluation cc w/enclosure:
See next page DISTR I BUTION pnginal s>gned bY Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
, Docket Files DFoster GHill (2)
OC/LFDCB LNorholm NRC
& Local PDRs SPeterson WJones
- KPerkins, RV JNorberg PDV r/f Tguay CGrimes Region V (8)
JRoe MVirgilio OGC DHagan ACRS (10)
OPA SHathews JStrosnider See revious concurrence OFC NAME DATE LA PDV DFoste 9 /pnA3 PH/PDV SPeter'n:mc
- SC RVIB SHatthews 03/18/93
- BC RVIB
- DD/DRIL
- BC EHEB LNorholm RZimmerman JNorber 03/18/93 03/23/93 03/24/93 D
PDV Tguay 3/~8/
OFFICIAL RECORD COPY DOCUMENT NAME:DC82775.LTR
I
Hr. Gregory H. Rueger materials, and manufacturing processes.
Therefore, PGKE has successfully demonstrated reasonable assurance that the 2-3 EDG is capable of perform' its intended safety function.
1 The staff has also evaluated the malfunctions that occurred during rformance of the endurance testing and has determined that these malfunctio did not affect qualification of the EDG.
Based on the staff's evaluatio of the endurance testing and subsequent inspection results, which inc ded visual and fiberscope inspections as well as disassembly and inspection f four power assemblies of the 2-3 EDG at DCPP Unit 2, we conclude that $ e endurance testing and associated post-test inspections have been co g eted in a
satisfactory manner.
Our safety evaluation is enclosed.
If you have any questions regarding this issue, pleas contact me.
Sincerely,
Enclosure:
Safety Evaluation cc w/enclosure:
See next page DISTRIBUTION She R. Peterson, Project Manager Pr ject Directorate V
vision of Reactor Projects III/IV/V ffice of Nuclear Reactor Regulation Docket Files DFoster GHill (2)
OC/LFDCB LNorholm NRC 5 Loc PDRs SPeterso WJones KPerk',
RV JNor erg PDV r/f TQuay CGrimes Region V (8)
JRoe HVirgi1 io OGC DHagan ACRS (10)
OPA SHathews JStrosnider See revious concurren e
OFC NAME DATE LA/PDV DFoster 3 /@/~~
PH/P SP erson:mc
- SC/RVIB
- BC RVIB
- DD DRIL
- BC EHEB D
PDV SHatthews LNorholm RZimmerman JNorber TOuay 03/18/93 03/18/93 03/23/93 03/24/93
/ /
OFF ICIA RECORD COPY DOCUMENT NAME:DC82775.LTR
Hr. Gregory H. Rueger materials, and manufacturing processes.
Therefore, PGRE has success lly demonstrated reasonable assurance that the 2-3 EDG is capable of p forming its intended safety function.
The staff has also evaluated the malfunctions which occurred ring performance of the endurance testing and has determined tha these malfunctions did not affect qualification of the EDG.
Ba d on the staff's evaluation of the endurance testing and subsequent inspe ion results, which included visual and fiberscope inspections, as well as isassembly and inspection of four power assemblies of the 2-3 EDG a
DCPP Unit 2, we conclude that the endurance testing and associated post-test inspections have been completed in a satisfactory manner.
Our safety e
laution is enclosed.
If you have any questions regarding this issue please contact me.
Sin erely,
Enclosure:
Safety Evaluation cc w/enclosure:
See next page DISTRIBUTION Docket Files DFoster GHill (2)
OC/LFDCB LNorholm NRC 5 Local PDRs SP~ terson Oones
- Perkins, RV JNorberg Sheri R. Peterson, Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation PDV r/f JRoe MVirgilio Tguay OGC DHagan CGrimes ACRS (10)
OPA Region V (8)
SHathews JStrosnider OFC LA/PDV H
~
E D
PDV NAME DFoster SPeterson:mc thews DATE
/ /
Q /l E/ tQ 5/lS/R%
r m
srv RZimmerman 3 /~/o3 J
e g p+r~w Tguay OFF I AL RECORD COPY DOCUMENT NAME:DC82775.LTR
4i 'i
~P III p
1 II j
Nr. Gregory H. Rueger demonstrated the adequacy of the 2-3 EDG's design, materials, and manufacturing processes.
Therefore, PGLE has successfully demonstrated reasonable assurance that the 2-3 EDG is capable of performing its intended safety function.
The staff has also evaluated the malfunctions that occurred during performance of the endurance testing and has determined that these malfunctions did not affect qualification of the EDG.
Based on the staff's evaluation of the endurance testing and subsequent inspection results, which included visual and fiberscope inspections as well as disassembly and inspection of four power assemblies of the 2-3 EDG at DCPP Unit 2, we conclude that the endurance testing and associated post-test inspections have been completed in a satisfactory manner.
Our safety evaluation is enclosed.
If you have any questions regarding this issue, please contact me.
Sincerely, R..P~~
Sheri R. Peterson, Project Hanager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/enclosure:
See next page
Hr. Gregory H. Rueger Pacific Gas and Electric Company Diablo Canyon CC:
NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 93424 Dr. Richard Ferguson, Energy Chair Sierra Club California 6715 Rocky Canyon
- Creston, California 93432 Hs.
Nancy Culver San Luis Obispo Hothers for Peace P. 0.
Box 164 Pismo Beach, California 93448 Hs. Jacquelyn C. Wheeler 3303 Barranca Court San Luis Obispo, California 93401 Managing Editor The County Telegram Tribune 1321 Johnson Avenue P. 0.
Box 112 San Luis Obispo, California 93406 Chairman San Luis Obispo County Board of Supervisors Room 370 County Government Center San Luis Obispo, California 93408 Hr. Truman Burns Hr. Robert Kinosian California Public Utilities Commission
. 505 Van Ness, Rm.
4102 San Francisco, California 94102 Mr. Steve Shu Radiologic Health Branch State Department of Health Services Post Office Box 942732 Sacramento, California 94234 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Peter H. Kaufman Deputy Attorney General State of California 110 West A Street, Suite 700 San Diego, California 92101 Michael H. Strumwasser, Esq.
Special Assistant Attorney General State of California Department of Justice 3580 Wilshire Boulevard, Room 800 Los Angeles, California 90010 Christopher J.
- Warner, Esq.
Pacific Gas 8 Electric Company Post Office Box 7442 San Francisco, California 94120 Hr. John Townsend Vice President and Plant Manager Diablo Canyon Power Plant P.
O.
Box 56 Avila Beach, California 93424 Diablo Canyon Independent Safety Committee ATTN:
Robert R. Wellington, Esq.
Legal Counsel 857 Cass Street, Suite D
Monterey, California 93940
I I