ML17290A648
| ML17290A648 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/30/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| Shared Package | |
| ML17290A651 | List: |
| References | |
| TAC-M84553, NUDOCS 9310060071 | |
| Download: ML17290A648 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 30, 1993 Docket No. 50-397 Hr. J.
V, Parrish (Mail Drop 1023)
Assistant Managing Director, Operations Washington Public Power Supply System P. 0. Box-968
- Richland, Washington 99352-0968
Dear Hr. Parrish:
SUBJECT:
SAFETY EVALUATION FOR THE PUMP AND VALVE IST PROGRAM WASHINGTON PUBLIC POWER SUPPLY SYSTEM, WNP-2 (TAC NO. H84553)
Revisions 3 and 3B of the Washington Public Power Supply System, Nuclear Plant Number 2 (WNP-2), inservice testing (IST) program were submitted in letters dated June 17, 1985 and October 12, 1987, respectively.
The NRC responded with a Safety Evaluation (SE) which was transmitted by a letter dated May 7, 1991.
The SE included a Technical Evaluation Report (TER) prepared by EG&G, Idaho; Appendix B of the TER contained eighteen items which you were requested to address.
Your responses to these eighteen items were submitted in a letter dated December 3, 1991, which also included Revision 4 of your IST program.
In addition to the responses, Relief Requests RP-7, RV-26, and RV-27 were also included in this submittal.
Relief Request RV-27 has already been granted by the staff in a SE dated Hay 19, 1992.
A supplemental response to items 2, 3, 12, and 13 was submitted by your letter dated July',
1992.
Relief Request RV-22 was also submitted with this letter.
Further, Relief Requests RP-7 and RV-26 were denied in an SE dated September 23, 1992.
In a subsequent submittal dated December 22,
- 1992, you withdrew Relief Request RP-7 and submitted Relief Requests RP-8, RP-9, and RP-10.
Relief Request RV-13,'ranted in the Hay 7,
- 1991, SE, was revised and included in your December 22, 1992, submittal.
Finally, you resubmitted Relief Request RP-9 in a letter dated Hay 27, 1993.
The staff's evaluations of Relief Requests RP-8, RP-9, RP-10, RV-13, and RV-22 are included in the enclosed Safety Evaluation.
Your responses to the items listed in Appendix B of the TER are evaluated in Table 1 of this SE.
The enclosed SE was prepared by the NRC to provide the results of the staff review.
The Code of Federal Regulations, 10 CFR 50.55a(f), requires certain Class 1, 2, and 3 pumps and valves in water-cooled nuclear power facilities to meet the inservice testing requirements stated in the ASHE Boiler and Pressure Vessel Code (Code),
Section XI:
specifically Subsection
- IWP, Inservice Testing of Pumps in Nuclear Power Plants,"
and Subsection IWV, "Inservice Testing of Valves in Nuclear Power Plants."
Guidance on acceptable alternatives to Code requirements has been provided for certain aspects of inservice testing by NRC in Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs."
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'Mr. J.
V. Parrish September 30, 1993 Regulations 10 CFR 50.55a
$g (a)(3)(i), (a)(3)(ii), and (f)(6)(i) authorize the Commission to approve alternatives to and grant relief from ASME Code requirements upon making the necessary findings.
The status of these relief requests is as follows:
RP-8 RP-9 RP-10 RV-13 RV-22 Granted Granted Alternative authorized Interim relief granted Granted The NRC staff has determined to grant relief pursuant to 10 CFR 50.55ag(f)(6)(i) and authorize the requested alternatives pursuant to 10 CFR 50.55a(a)(3).
The relief granted is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the r equirements were imposed on the facility.
The staff's findings with respect to these relief requests as part of your IST Program are contained in this SE.
Since ely,
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Theodore R.
Quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation NRC 8 Local PDRs TQuay ACRS (10)(P315)
DISTR IBUTION:
I Docket File EAdensam OGC (15B18)
- See revious concurrence PDV Reading File JClifford
- KPerkins, RV JRoe DFoster OFFICE PDV/LA EBarnhil NAME DATE 93 OFFICIAL RECORD COPY PDV P
JCl'ord 093 OGC 93
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Hr. J.
V. Parrish WPPSS Nuclear Project No.
2 Washington Public Power Supply System (WNP-2)
CC:
Hr. J.
H. Swailes WNP-2 Plant Manager Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968 G.
E.
C. Doupe, Esq.
(Mail Drop 396)
Washington Public Power Supply System 3000 George Washington Way P. 0.
Box 968
- Richland, Washington 99352-0968 Mr.
War ren Bishop, Chairman Energy Facility Site Evaluation Council P. 0.
Box 43172 Olympia, Washington 98504-3172 Hr. Alan G. Hosier (Hail Drop PE20)
WNP-2 Licensing Manager Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968 Hr.
G.
C. Sorensen (Hail Drop PE20)
Regulatory Programs Manager Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968 Regional Administrator, Region V
U.S.
Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Chairman Benton County Board of Commissioners P. 0.
Box 190
- Prosser, Washington 99350-0190 Mr. R. C. Barr U. S. Nuclear Regulatory Commission P. 0.
Box 69
- Richland, Washington 99352-0968 M. H. Philips, Jr.,
Esq.
Winston 5 Strawn 1400 L Street, N.W.
Washington, D.C.
20005-3502
Hr. J.
V. Parrish Regulations 10 CFR 50.55a
$g (a)(3)(i), (a)(3)(ii), and (f)(6)(i) authorize the Commission to approve alternatives to and grant relief from ASHE Code requirements upon making the necessary findings.
The status of these relief requests is as follows:
RP-8 RP-9 RP-10 RV-13 RV-22 Granted Granted Alternative authorized Interim relief granted Granted The NRC staff has determined to grant relief pursuant to 10 CFR 50.55ag(f)(6)(i) and authorize the requested alternatives pursuant to 10 CFR 50.55a(a)(3).
The relief granted is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
The staff's findings with respect to these relief requests as part of your IST Program are contained in this SE.
Sincerely,
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation