ML20248H794
| ML20248H794 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/03/1989 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-04, GL-89-4, NUDOCS 8910120084 | |
| Download: ML20248H794 (3) | |
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GPU Nuclear Corporation Nuclear
=tr 88 Forked River, New Jersey 08731-0388 l
609 971-4000 Writer's Direct Dial Nurnber:
October 3,1989 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sir
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Generic Letter 89-04; Inservice Test Programs This letter is being *:ritten to 1) respond to Generic Letter 89-04, 2) inform the USNRC of the GP'J Nuclear. Inservice Test (IST) Evaluation and Upgrade Program, and 3) request an extension of the October 3, 1989 due date for completion of the Generic Letter programmatic review.
Generic letter 89-04 directed GPU Nuclsar to review our most recently submitted IST program against NRC positions contained in Attachment I to GL 89-04, and to submit the results of this review by October 3, 1989. By letter dated May 20, 1988, GPU Nuclear had requested an ASME allowed extension of the existing IST program to October 14, 1991. The extension request was approved by the USNRC by letter dated March 6, 1989. The present IST program was written consistent with ASME XI, 1974 edition and Summer 1975 addenda.
Responding to GL 89-04 requires a reassignment of resources.
Initial efforts indicated that some changes to the IST program required by the GL 89-04 response may not be sufficient to fully comply with the edition of the code which would become effective in 1991. Additionally, some of the changes required by the 1991 submittal would not be captured by the GL 89-04 response.
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.To-maximize the effectiveness of the two-submittals, an integrated approach is appropriate. The scope of this effort and projected completion dates are detailed below:-
- 1. Review the existing IST program to ensure that components required"to be
-tested per-presently committed ASME code (1974 edition, summer 1975 addenda) are being tested as specified'in the Generic Letter.
The preliminary review has been completed. A detailed review is underway and is scheduled to be completed by April 3, 1990. To date 38 valves have been identified for addition to the program.
- 2. Review the testing procedures to identify any valve testing requirements not. presently included in the IST program or in the GL 89-04 program.
The review has been completed and requisite procedure revisions have been identified.
- 3. Revise the procedures identified in (2) above.
The procedure revision process will be initiated shortly and is projected to be completed by June 3, 1990. Where modifications are required to implement the procedure revisions, see Item 6, below.
- 4. Issue new procedures for the valves identified in (1) above which are not presently tested by an existing procedure.
These procedures are projected to be issued by June 3, 1990.
- 5. Resolve open issues relating to testing required by either GL 89-04 or the ASME code and propose alternatives to testing.
The open issues relating to the ASME code requirements will be addressed by October 14, 1991.
- 6. Determine what hardware changes or modifications to valves would be required to meet both the presently committed ASME code, and the ASME code effective as of October 14, 1990.
Although hardware changes or modifications may be suggested by the review of GL 89-04, GPU Nuclear will determine the scope and extent of this requirement to meet the ASME code edition effective as of October 14, 1990. This will preclude the possibility of multiple modifications to a given component due to the changes in code requirements. Hardware changes and modifications will be identified and addressed by the IST ten year update, due for submittal on October 14, 1991.
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U.S.' Nuclear Regulatory Commission Page 3-l 7.
GL 89-04'does.not address the section of ASME code relating to pump' testing at the Oyster.. Creek Station.-- 'GPU Nuclear will review the IST pump' testing program against the' newer ASME code requirements as part-of the-1991 ten year update.
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- If any'further information is required, please contact Mr. John Rogers at 609-971-4893.
Very truly yours,
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E.E. Fitzpat ick
.Vice President & Director Oyster Creek-EEF/JR/jc (7-9)
.cc: Mr. William T. Russell,. Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road
' King of Prussia, PA 19406
-Mr. Alexander W. Dromerick-U.S. Nuclear' Regulatory Commission Washington,-DC 20555 NRC' Resident Inspector Oyster Creek Nuclear Generating Station l
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