GO2-83-590, Forwards Revised Vols 1-3 to Environ Equipment Qualification Rept for Safety-Related Equipment. Rev Provides Response to Concerns Raised in Suppl 3 to SER (NUREG-0892)
| ML17277A638 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/30/1983 |
| From: | Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17277A639 | List: |
| References | |
| RTR-NUREG-0892, RTR-NUREG-892 GO2-83-590, IEB-79-01B, IEB-79-1B, NUDOCS 8307070006 | |
| Download: ML17277A638 (7) | |
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ACCESSION NBR:8307070006 DOC.DATE: 8)/06/30 NOTARIZED; NO DOCKET FACIL,50 397 NPPSS Nuclear ProJects Unit 2E 8ashinaton Public Powe 05000397 AUTH NAME AUTHOR AFFILIATION BOUCHEY.G.D.
Nashinaton Pghlic Power Suooly System RECIP.NAME RECIPIENT AFFILIATION SCHNENCER r A Licensina Branch 2
g o~CW esse 4zt 'LS
SUBJECT:
Forwards revised "Enwiron Eouioaent Qualification Reot for safety-Rel ated Eauioments Ti Vol s 1 3.Rev ar ovides resoonse to concel ns rai sed in.Suool 3 to SER (NUREG<<0892)
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Washington Public Power Supply System P.O. Box 968 3000George Washington Way Richland, Washington 99352 (509) 372-5000 Docket No. 50-397 Director of Nuclear Reactor Regulation~'ttention:
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PROJECT NO.
2 JUSTIFICATION FOR INTERIM OPERATION June 30, 1983 G02-83-590 This letter transmits the Supply System's revised Environmental Eqtlip-ment gualification Report for Safety-Related Equipment.
This revision provides an update to the equipment list and responds to concerns raised in Supplement 3 to the Safety Evaluation Report (NUREG-0892).
The list included in this report contains electrical equipment important to safety as required by 10 CFR 50.49(d).
A major element of the revision is full development of our Justification for Interim Operation (JIO) of safety-related electrical equipment as required by 10 CFR 50.49.
The NRC Supplement No.
3 to the Safety Evaluation Report (SSER) raised a
number of concerns.
Some of those are responded to within the document being transmitted by this letter.
It is appropri ate to address some of the conce'ms in this letter itself.
The SSER requested discussion on how changes to equipment items resulting from IE Bulletins, Circulars, and Information Notices have
- been, or will be, evaluated for their impact on qualification.
The Supply System has a
controlled, documented process for review and disposition of such NRC documents.
Plant changes flowing from such responsive actions are con-trolled by the design change control process.
The SSER called on us to reevaluate the adequacy of the plant walkdown performed before the staff's audit.
The Supply System has caused system reviews to be conducted to add or delete items from the ClE list.
These reviews improve the quality of the program and allow us to make the con-clusionary judgments necessary regarding environmental qualification of this facility.
Additionally, in the efforts to complete the lists, incor-porate plant changes and complete data entries, mistakes in the list were observed and corrected.
t 830707000b 830b30 PDR ADOCK 05000397 A
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Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Page Two June 30, 1983 Ci02-83-590 The SSER requests our revi ew of the Equi pment Qual ificat ion Program to establish that all data reported is applicable.
We have reviewed the program.
As,discussed
- above, system reviews were conducted to improve and verify the equipment lists.
Computer programs were developed and used to assure that other programs had communicated properly in the generation of lists, and checking and reviewing were emphasized acti'viti'es in conduct of activities leading to this docu-ment.
We can state that significant effort has been exerted to cor-rect the data and we judge that there are no significant omissions or errors.
On June 27, 1983 our Architect-Engineer identified four main steam system pressure switches which were recently added to the plant design in response to NRC requirements and belong within the scope of our quali-fication program but were not discussed in these documents.
This situa-tion is highlighted here because of our responsibility to be open with you and also to make a point.
We expect that minor changes will continue to be made in the list and qualification program.
All such changes are addressed by our qualification efforts.
At the time of fuel load, we expect to be able to judge the plant properly qualified.
Last moment changes are expected.
We know they must be addressed and require quali-fication documentation.
We believe such changes are a reality and must be taken into account in our operation and your evaluation of this qualification process.
The SSER directs us to submit the results of our review for all safety-related mechanical (SRM) equipment located in a harsh environment.
Our SRM program addresses all active safety-related mechanical equipment in a harsh environment.
The results of our review are included in this Environment Qualification Report.
As the NRC is aware, the Supply System has an independent Verification Program underway.
The"Equipment Qualification Program was reviewed and errors were found in the calculated profiles associated with high energy line breaks (HELB).
We have calculations underway correcting the errors.
Where this document shows equipment status as qualified, it is qualified to LOCA and "old" HELB environments.
Preliminary calculations show that most of the HELB profiles will not change significantly.
There-fore, it is our judgment that most equipment will remain qualified to the
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Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Page Three June 30, 1983 G02-83-590 revised HELB profiles when they are available and have been evaluated.
We will provide verification of this judgment with the supporting document revisions as soon as we can, and certainly by July 30,
- 1983, to minimize the pressure on your review.
We are available to discuss these documents with the staff.
Very truly yours, G.
D. Bouchey, 340
- Manager, Nuclear Safety and Regulatory Programs GDB:KRW:st Attachment cc:
Mr. R. Auluck, NRC Mr.
W. S. Chin, BPA Mr. A. Toth, NRC, Site