ML20155D015

Application for Amend to License DPR-16,consisting of Rev 1 to Tech Spec Change Request 166,changing Tech Specs to Support Cycle 12 Reload

ML20155D015
Person / Time
Site:	Oyster Creek
Issue date:	09/22/1988
From:	Wilson R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20155D014	List: ML20155D010 ML20155D015 ML20155D019 ML20155D031
References
NUDOCS 8810110011
Download: ML20155D015 (7)

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GPU NUCLEAR CORPORATION i

OYSTER CREEK NUCLEJ 9 GENERATING STATION j l

I PROVISIONAL OPERATING LICENSE NO. OPR-16  ;

Technical Specification Change Request flo.166, Rev.1 ,

Docket No. 50-219 i

Applicant submits, by this Technical Specification Change Request No. 166, i

Rev. I to the 0yster Creek fluelear Generating Station Technical .

Specifications, a change to pages 3.10-1, 3.10-2, 3.10-3, 3.10-4, 3.10-5,  !

I. 3.10-6, 3.10-10 and 3.10 5 i

t By: *R. F)NW Wilson j Vice President Technical Functions i

i I Sworn and subscribed to before me this AA M dayofx,h8n/et.t 1983.

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l UNITED STATES OF AliERICA NUCLEAR REGULATORY C0 fili!SSION IN THE I4ATTER OF )

DOCKET N0. 50-219 GPU NUCLEAR CORPORATI0fl CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No.

166. Rev. 1 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Commission on September 22, 1988, has this day of September 22 , 1988, been served on the flayer of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable Christopher Connors fiayor of Lacey Township 818 West Lacey Road ror d Ri er, NJ 08731 By: . fE' kY 9 R. F. Vilson Vice President Technical Functions i

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Pars lppany, New Jersey 07054 201 316-7000 TELEX 136-482 Wter's Direct Dial Number:

September 22, 1988 The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731

Dear Mayor Connors:

Enclosed herewith is one copy of the Technical Specification Change Request No. 166, Rev. I for the Oyster Creek Nuclear Generating Station Operating Licensing.

This document was filed with the United States Nuclear Regulatory Cornission on September 22 , 1988.

Ve y tr ly yours,

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. F. Wilson Vice President Technical Fun:tions RFW/JDL/pa Enclosura l

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-, v GPU Nuclear Corporation One Upper Pond Road

!,73 ; QQ ggf Parsippany, New Jersey 07054 201-316-7000 TELEX 136 482 September 22, 1988 Wnter's Direct Dial Number:

fis. Jenny floon, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628

Subject:

Oyster Creek fluclear Generating Station Provisional Operating License No. DPR-16 Technical Specification Change Request flo.166, Rev. 1 Pursuant to 10CFR50.91(b)(1), please find enclosed a copy of the subject docunent which was filed with tne United States Nuclear Regulatory Commission on September 22 , 1983.

Ve y tr ly yours, R.."F. \J fli) on w Vice President Technical Functions RFil/JDL/pa Enclosure 7327f GPU Nuc'er Corpora $co 's a subsd ary c4 Geval Putic Ut i t es Corporat on

OYSTER CREEK NUCLEAR GENERATING STATION >

PROVIS10flAL OPERATING L ICENSE NO. OPR-16 DOCKET NO. o0-219 TECHNICAL SPECIFICATION CHANGE REQU-ei NO.166, Rev.1 Applicant hereby requests the Comniission to change Appendix A to the above caot1oned license as indicated below. Pt.rquant to 10CFR50.91, an analysis concerning the determination of no significant hazards considerations is also presented:

1. Section to be Changed 3.10

2. Extent of Change liodify Section 3.10 to accommodate the Cycle 12 Reload. Specifically, liCPR and 11APLHG'l limits will be changed.

3. Changes Requested As indecated in the attached revised Technical Cpecification pages 3.10,1, 3.10-2, 3.10-3, 3.10.4, 3.10-5, 3.10-6, 3.10-10 and 3.10-11

4. Discussinn The Cycle 11 core for Oyster Creek consisted of 560 fuel assemblies, the composition of which included Exxon Type VB assemblies and General Electric P8x8R assemblies. The Cycle 12 core will consist of Exxon Type VB assemblies and General Electric P8x8R and GE8x8E8 assemblies. The GE8X3EB fuel design will be introduced for the first time into the Oyster Creek core for Cycle 12.

By letter Jated November 25, 1985 GPU Nuclear conyt.yed to the NRC its intent of performing the Cycle 12 Reload analysis in-house. Consistent with that intent, the following GPU Nuclear Topical Reports (to be used in the Cycle 12 Reload analysis) were submitted for NRC approval; TR-020 "liethods for the Analysis of Soiling Water Reactors Lattica Physics", I TR-021 "fiethods for the Analysis of Boiling 'later Resctors Staady State l Physics", TR-033 ".'iethods for the Generation of Core V,inetics Data for RETRAN-02", TR-040 "Steady-State and Quasi-Steady-St&te liethods used in the Analysis of Accident and Transients" and TR-045 "3WR-2 Transient Analysis flodel using the RETRAN Code". GPU Nuclear Topical Report 049 '

"Reload Information and Safety Analysis Report for Oyster Creek Cycle 12 Reload" submitted with TSCR #166, is a surimary of the results of the Cycle 12 reload core design and safety analysis. Revision 1 to GPU Nuclear ,

Topical Report 049 submitted with TSCR #166, Revision 1, incorporates '

consideration of uncertainties for input variables to code correlation as discussed in GPU Nuclear's response to the NRC's request for additional

• information concerning GPU Nuclear Topical Report 045.

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Licensing topical report NEDE-30996-P "SAFER 110 DEL EVALUATION OF l

t LOSS-0F-COOLANT ACCIDENTS FOR JET PUMP AND NON-J'.T PuliP PLANTS" was submitted for NRC review by the General Electric Company on June 25, 1986. The NRC staff issued its safety evaluation addressing the acceptability of referencing licensing topical report NEDE-30996-P, Volume II, on liay 11, 1987. NEDE-31462P "0YSTER CREEK NUCLEAR GENERATING STATION SAFER /COREC00L/GESTR-LOCA LOSS-OF-COOLANT ACCIDENT ANALYSIS", submitted with TSCR #166, represents the Oyster Creek plant specific application of the approved NEDE-30996-P, Volume !! methodology. As discussed in NEDE-31462P, the Oyster Creek plant specific SAFER /COREC00L/GESTR-LOCA analysis meets the explicit requirements of the staff's safety evaluation of 11ay l',1987 and the criteria of 10CFRSO.46.

With respect to the proposed f1CPR limit, the Turbine Trip Without Bypass transient was the most limiting for Cycle 12 with a maximum Delta-CPR of 0.37. The proposed 11CPR value of 1.51 was conservatively chosen based on a safety limit of 1.07, a maximum Delta-CPR of 0.37 and a statistical multiplier of 1.049. This represents an increase from the Cycle 11 f1CPR valve which was 1.45.

With respect to the proposed 11APLHGR limits, the analysis demonstrated that the DBA is the PCT limiting break size and resulted in higher liAPLHGR values of approximately 0.7 KW/ft at low exposure. Operating the Cycle 12 bundles w' thin the propnsed liAPLHGR limits insures that the PCT will not exceed the performance criteria of 10 CFR 50.46 during a LOCA situation.

The proposed Technical Specifications have been based on the results of the analysis discussed above and thereby provide reasonable assurance that the health and safety of the public will not be endangered by operating in the proposed manner.

5. Determination GPU Nuclear has determined that operation of the Oyster Creek Nuclear Generating Station in accordance with the proposed technical specifications does not involve a significant hazard. The changes do not:

1. Involve a significant increase in the probability or the consequence

, of an accident previously evaluated. The probability of an accident is not dependent upon the core loading and there are no other changes to the plant configuration, availability of safety systems, the manner in which the safety systems are initiated or the way the plant is

operated that will increase the probability of an accident. Cycle 12 introduces a ned fuel design, GE8X8EB, which has been reviewed and 3

approved by the NRC; letter from H. Berkow (NRC) to J. S. Charnley (GE) dated December 3,1985, "Acceptance for Approval of Fuel Designs Described in Licensing Topical Report NEDE-24011-P-A-6, Anendment 10 for Extended Burnup Operation." The fuel design has been incorporated 1 into the reload applications of other BWR plants. The neutronic and l mechanical design is not significantly different from designs

currently in use at Oyster Creek and the fuel will not be operated in i a manner that would cause the consequences of an accident to be increased.

2. Create the possibility of a new or different kind of accident from any ,

previously evaluated. The Cycle 12 core loading does not involve any I other change to the plant configuration, nor does it change the I availability of safety systems or the manner in which they respond to initiating avents. Also, the design does not change the manner in which the core will be operated from previous cycles. As such, tha

possibility cf a new or different kind of accident from any previously evaluated is not created.

3. Involve a significant reduction in a margin of safety. The proposed Technical Specifications are based on analysis results which were performed in accordance with methods and procedures developed by GPUN and GE. The GPUN methods have been submitted to the NRC for their review and approval. NRC approval requires GPUN to demonstrate the adequacy of the methods for the analyses to be performed, that the methods account for the uncertainties to the analyses, and that GPUN can adequately employ the methods for their application. All of the methods used by GPUN have been submitted to the NRC and have been approved except for TR-045 which is under review and addresses system transients using the RETRAN-02 computer code. NRC 6pproval of TR-045 is expected since the methods employed have been used by other utilities in similar applications, the methods account for uncertainties and the methods provide results which are consistent with previous reload analyses. Currently, the RETRAN-02 cede itself is being reviewed by the NRC for use in reload analyses.

l The GE LOCA analytes, NEDE-37462P, "0yster Creek Nuclear Generating '

Station SAFER /COREC00L/GESTR-LOCA LOSS-0F-COOLANT ACCIDENT ANALYSIS,"

submitted with this reload application is based on a methodology previously approved by the NRC via a flay 11, 1987 safety evaluation ,

addressing NEDE-30996-P, Volume II. This methodology has been used by other utilities in reload applications, and, as in the case of TR-045, NRC approval of the Oyster Creek application is expected.

Therefore, the results of the analyses presented in TR-049 and NEDE-31462P and the technical specification changes based on these results will ensure that there is no sigt.ificant reduction in the margin of safety.

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