ML20117E695

Application for Amend to License DPR-16,consisting of TS Change Request,Proposing New pressure-temp Limits Up to 22, 27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corresponding EFPY of Operation

ML20117E695
Person / Time
Site:	Oyster Creek
Issue date:	08/23/1996
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20117E700	List: ML20117E695 ML20117E706 ML20117E733
References
RTR-REGGD-01.099, RTR-REGGD-1.099 6730-96-2151, NUDOCS 9609030041
Download: ML20117E695 (9)

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{ GPU Nuclear,Inc.

( U.S. Route #9 South NUCLEAR '**'*"'c'*****

Forked River, NJ 087310388 Tel 609 9714000 August 23, 1996 6730-96-2151 U. S. Nuclear Regulatory Commission Att: Document Control Desk Washington, D.C. 20555 Gentlemen

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219

. Technical Specification Change Request (TSCR) No. 245 -

In accordance with 10 CFR 50.4(b)(1), enclosed is a Technical Specification Change Request (TSCR) No.

245. Also enclosed is a Certificate of Service for this request certifying service to the chief executive of the township in which the facility is located, as well as the designated official of the State of New Jersey Bureau of Nuclear Engineering.

In accordance with the requirement of the Oyster Creek Technical Specifications GPU Nuclar submitted pressure-temperature (P-T) limits for operation up to seventeen (17) effective full power years (EFPY) on January 11,1991 (TSCR No.194). Subsequently, on April 11,1991 the Commission issued Amendment No.

151 in response to our application. It is projected that OCNGS will reach 17 EFPY ofoperation in April, 1997 The current P-T limits were developed in accordance with 10 CFR 50, Appendix G to assure that brittle fracture of the reactor _ vessel is prevented. Part of the analysis involved in developing the P-T curve is to account for irradiation embrittlement effects in the core region or beltline. The results of the surveillance capsule test and the method described in Regulatory Guide 1.99, Revision 2 were used to account for irradiation embrittlement.

This TSCR proposes new pressure-temperature limits up to 22,27 and 32 EFPY based upon the predicted nil-ductility adjusted reference temperature (ARTmr) for corresponding EFPY ofoperation. These new sets cf curves will be used beyond 17 EFPY in the future as the corresponding EFPY ofoperation is completed. The new sets of the P-T limits were also developed based on the surveillance capsule test results, and in accordance with requirements of10 CFR 50, Apperxlix G and Regulatory Guide 1,99, Revision 2.

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Page 2 Detailed discussions on methodology c.nd results of the analyses for generating the P-T limits are provided in  !

the attached report, GENE-B13-01769, " Pressure-Temperature Curves per Regulatory Guide 1.99, Revision 2 for the Oyster Creek Nuclear Generating Station" Pursuant to 10 CFR 50.9)(a)(1), enclosed is an analysis applying the stanosds of 10 CFR 50.92 to make a '

determination ofno significant hazards consideration.

Very truly yours, 7dA%

Michael B. Roche Vice President and Director Oyster Creek

. YN/ pip c: Administrator, Region I NRC Resident Inspector (OC)

Oyster Creek NRC Project Manager i

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GPU NUCLEAR CORPORATION  !

OYSTER CREEK NUCLEAR GENERATING STATION Provisional Operating License No. DPR-16 .

Technical Specification Change Request No. 245 Docket No. 50-219 I

Applicant submits, by this Technical Specification Change Request No. 245, to the Oyster Creek Nuclear i Generating Station Technical Specifications, a change to pages 3.3-1,3.3-5,3.3-8a,3.3-9,4.3-1, and 4.3-2.

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~~ M'ichael B. Roche Vice President and Director  !

Oyster Creek l Sworn and Subscribed to before me this23 day of 89,1996.  ;

M /b A Notary Public ofNJ l

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T g GPU Nucleer, Inc.

U.S. Route #9 South NUCLEAR ' " U 8

• 88 forked River, NJ 087310388 Tel 609-9714000 i

August 23, 1996 6730-96-2151 The Honorable John C. Parker MayorofLacey Township 818 West Lacey Road Forked River, NJ 08731

DearMayor Parker:

Enclosed herewith is one copy of Technical Specification Change Request N Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on Aueust 23 .1996.

Sincerely, b

Michael B. Roche Vice President and Director Oyster Creek

. YN/ pip Attachment -

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GPU Nuclear,Inc.

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U.S. Route #9 South NUCLEAR '**'******

Forked River. NJ 08731-0388 Tel 609-971-4000

August 23, 1996 6730-96-2151 Mr. Kent Tosch, Director Bureau ofNuclear Engmeenng 4

Department ofEnvironmental Protection CN 411

-l Trenton,NJ 08625

Subject:

Oyster Creek Nuclear Generating Station Provisional Operating License No. DPR-16 Technical Specification Change Request No. 245 Pursuant to 10 CFR 50.91(b)(1), please find enclosed a copy of the subject document w United States Nuclear Regulatory Commission on August 23, 1996.

Sincerely, b

Michael B. Roche Vice President and Director Oyster Creek YN/ pip .

Attachment

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

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In the Matter of )

) Docket No. 50-219 GPU Nuclear Corporation )

CERTIFICATE OF SERVICE I

This is to certify that a copy of Technical Specification Change Request No. 245, for Oyster Creek Nuclear l Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission on August 23,  !

1996 has this day of 8/2Vl996, been served on the Mayor of Lacey Township, Ocean County, New Jersey by j deposit in the United States mail, addressed as follows:

l The Honorable John Parker Mayor ofLacey Township 818 West Lacey Road Forked River, NJ 08731 i

By Michael B. Roche  !

Vice President and Director i Oyster Creek l

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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 245 l

i Applicam hereby requests the Commission to change Appendix A to the above captioned license as below, and pursuant to 10 CFR 50.91, an analysis concerning the determination of no significant hazards consideration is presented below:

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1.0 SECTIONS TO BE CHANGED )

l Section 3.3. A (i), (ii), (iii) and (iv) and Bases References Curves (a), (b) and (c) in Figure 3.3.1 (

Section 4.3.A and Bases i l

2.0 EXTENT OF CHANGli l l

i) Section 3.3.A (i), (ii), (iii) and (iv), and curves (a), (b) and (c) in Figure 3.3.1 are revised to provide i new pressure-temperature (P-T) operating curves for operations up to 22,27 and 32 effective full -  ;

power years (EFPY) and, J

ii) The current Oyster Creek Technical Specifications provide P-T operating curves for operation up to 17 EFPY in Figure 3.3.1. Technical Specification Change Request No. 245_ proposes to provide P-T operating curves for operations up to 22,27 and 32 EFPY (Figures 3.3.1,3.3.2 and 3.3.3 respectively). To reflect this arrangement, editorial changes are made in Section 3.3. A and its Bases and Section 4.3.A and its Bases.

3.0 CHANGES REOUESTED The changes are shown on the attached Technical Specification pages 3.3-1,3.3-5, 3.3-8a, 3.3-9a, 3.3-9b,3.3-9c,4.3-1, and 4.3-2.

4.0 DISCUSSION The purpose of the Technical Specification Change Request is to revise the Technical Specification to l incorporate new pressure-temperature (P-T) limits. Following discussion supports these proposed  !

Technical Specification changes:

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Section 3.3.A(iv) of Oyster Creek Technical Specifications requires appropriate new pressure temperature limits be approved when the reactor system has reached 17 effective full power years (EFPY) ofreactor operation.  ;

l Neutron irradiation results in the embrittlement of pressure vessel steels. The primary materials of concern are those surrounding the active core. To monitor the effects ofirradiation on these materials, test specimens fabricated from the materials used to fabricate the reactor vessel are installed on the  !

reactor vessel wall at the core mid-plane. Dosimetry wires are included which provide an estimate of the fluence to which the specimens were exposed. The specimens and wires are periodically removed, tested, analyzed and the results evaluated to determine the extent ofembiittlement as a function offluence.

The property of concern is the reference nil-ductility temperature (RTun) which increases as a function of fluence and material chemistry. Once the RTun, fluence and material chemistry are known,  ;

predictions of RTmn in the future can be made. P-T curves are developed based upon the adjusted i RTmn at the end of the operating period.

After Cycle 9, GPUN removed Reactor Vessel Materials Surveillance Program (RVMSP) Capsule No.

2. Its contents were tested and analyzed; the results were evaluated and predictions of RTun for various  ;

periods ofoperation were prepared.

I The new P-T limits were developed through 22,27 and 32 EFPY based upon the Reg. Guide 1.99, Rev.

2, methodology for predicting adjusted RTmn. j We have determined that this change request with respect to P-T limits involves no significant hazards  !

considerations in that operation of the Oyster Creek Plant in accordance with the proposed amendment, will not:

1. Involve a significant increase in the probability of an accident because the new limits account for the .

increase in RTun, including statistical uncertainty, due to neutron irradiation of the reactor vessel as j well as establishing initial RTun on the basis ofcurrent Code requirements, also including statistical uncertainty, in accordance with Reg. Guide 1.99, Rev.2. The new P-T curves will assure that brittle l fracture of the reactor vessel is prevented. i

2. Create the probability of a new or different kind of accident from any accident previously evaluated.

These new limits are the result of the calculation methodology in Reg. Guide 1.99, Rev. 2, as required  !

by Generic Letter 88-11. Primary system configuration and function remain unchanged.

3. Involve a significant reduction in margin of safety because the bases for the margin of safety remain the same as current limits, i.e., ASME, Sect. XI, App. G for available fracture toughness and applied stress intensity, Reg. Guide 1.99, Rev. 2 for calculating applied stress intensity, Reg. Guide 1.99, Rev.

2 for calculating adjusted RTun and 10 CFR 50, App. G, for criticality conditions.

1 5.0 IMPLEMENTATION 1

It is requested that the amendment authorizing this change become effective prior to restart ofOyster  !

Creek for the Cycle 16 operation.

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