ML20081J241
| ML20081J241 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/11/1991 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20081J245 | List: |
| References | |
| C320-91-2165, GL-88-01, GL-88-1, NUDOCS 9106210191 | |
| Download: ML20081J241 (7) | |
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GPU Nuclear Corporation 3
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":Ln:r 8" Forked River, New Jersey 08731-0388 609 971 4000 Wnter's Direct Dia' Number.
June 11,1991 C320-91-2165 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Gentlemen Subject Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 200 Pursuant to 10 CFR 50.90, GPU Nuclear Corporation (GPUN), operator of the Oyster Creek Nuclear Generating Station (OCNGS), Provisional Operating License No. DPR-16, requests a change to Appendix A of that license.
The attached Technical Specification Change Request proposes to add Specification 4.3.I which would require an inst,rvice inspection program for piping to be performed as identified in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff. The proposed wording is as given in draft NUREG-1433, Volume 1, Standard Technical Specifications General Electric Plants, BWR/4, January 1991.
Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainleos Steel Piping," requested BWR licensees to incorporate in their Technical Specifications a requirement to perform an augmented inservice inspection program for stainless steel piping. The piping inspection program for Oyster Creek, with a few exceptions, has been consistent with Generic Letter 88-01 requirements. The exceptions, with justification, have been approved by the NRC staff. Also attached is the latest revision (Revision 3) of CPUN Topical Repcrt 050, which documents the inspection plan.
We consider this request to be of moderate priority sir.ce IGSCC inspections at Oyster Creek are currently performed in accordance with an NRC-approved program.
If approved, we would be prepared to implement the changes upon losuance of the license amendment.
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,U. [S. Nuclecr R gulctory Commis: tion Page Two This change request has been reviewed in accordance with Section 6.5 of the OCNGS Technical Specifications, and using the standards in 10 CFR 50.92 we have concluded that these proposed changes do not constitute a significant hazards consideration.
Pursuant to 10 CFR 50.91 (b) (1), a copy of this change request has been sont to the State of New Jersey Department of Environmental Protection.
Ve p c ily yours,
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J a ton Vc 3 I esident and Director, Oi er Creek JJB/PC/amk Attachment cc: Administrator, Region I NRC Resident Inspector Mr. Alex Dromerick, NRC Project Manager
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1 ATTACHMENT 1 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 200 i
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION l
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Docket No. 50-219 GPU Nuclear Corporation
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CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No.
200 for Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission on June 11 1991, has this day of June 11 1991, been served on the Major of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Debra Madensky Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 087I (7
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By J. [J.
3 on Vibe r ident and Director Oyst reek
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I CPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION Provisional Operating License No. DPR-16 Technical Specification Change Request No. 200 Docket No. 50-219 Applicant submits, by this Technical Specification Change Request No. 200 to the Oyster Creek Nuclear Generating Station Technical Specifications, a
proposed change to page 4.3-2.
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a[ ton Vfc-esident and Director Orse Creek Sworn and Subscribed to before me this /l day of
~, 1991.
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Notary PubDe of hh My commisalon Emires #d 5' / 9 r
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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING ?,1 CENSE NO. DPR-16 DOCKET No. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 200 Applicant hereby roquests the Commission to chango Appendix A to the above captioned license as below, and pursuant to 10 CFR 50.92, an analysis concerning the determination of no significant hazards considerations is also presented:
1.
Section to be Chan2Cd Section 4.3 2.
Extent of Chano2 Add Technical Specification 4.3.I.
3.
Changes Reagented The requested change is shown on attached Technical Specifications page 4.3-2.
N 4.
Purpose Technical Specification Change Request (TSCR) No. 200 is being submitted to the NRC for approval to satisfy a commitment made in GPUN letter to NRC (5000-90-1938) dated June 7, 1990.
The commitment was reiterated in Topical Report No. 050, Revision 2 which was submitted to the NRC by GPUN letter (5000-90-1982) dated October 18, 1990.
The commitment stemn from a requirement in NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping."
The generic letter requested BWR licensees to incorporate in their Technical Specifications a requirement to perform an inservice inspection program for stainless steel piping which conforms to the generic letter.
The piping inspection program at Oyster Creek, with a few exceptions, has been consistent with Generic Letter 88-01 requirements. The exceptions, with justification, have been approved by the NRC.
There may continue to be exceptions in the future.
Therefore, a new Technical Specification 4.3.I is being proposed as follows:
4.3.I An inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the NRC staff positions on schedule, methods, personnel, and sample expansion included in the generic letter or in accordance with alternate measures approved by the NRC staff.
The proposed wording is as given in draft NUREG-1433, Volume 1, Standard Technical Specifications General Electric Plants, BWR/4, January 1991.
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n Determination We have determined that.the proposed Technical Specification change involves no
.significant hazards considerations as discussed below.
1.
The change will not involve a significant increase in the probability or consequence of any accident previously evaluated.
The proposed specification is a piping inspection program requirement.
The objective of this program is to provide further assurance that IGSCC does not adversely affect austenitic stainless steel pipe integrity. With piping integrity maintained the probability of pipe failure and potential consequent equipment malfunction are not increased.
The inspection program does not alter the evaluation of high energy line breaks.or plant response to loss of coolant accidents and so accident consequences are not increased.
2.
The proposed change does not create the possibility of a new or different accident from any accident previously evaluated.
Since the inspection activity, which is a non-destructure examination, does not involve' physical changes to the plant, revise operating i
procedures or comprise a test, accidents or malfunctions of a different type are not created.
3.
A significant reduction in margin of safety is not involved.
The augmented pipe inspection program proposed as Specification 4.3.I provides additional pipe inspection requirements beyond those currently specified in the Technical Specifications.
.It does not delete or revise those current requirements. Therefore, no reduction in margin of safety is involved.
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