ML20211M257

Sanitized Supplement to 970331 & 970716 Applications for Amend to License NPF-57,revising Ts.Addl Info & Revised TS Bases Pages Associated W/Amend 101

ML20211M257
Person / Time
Site:	Hope Creek
Issue date:	08/26/1997
From:	Eric Simpson Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20046D868	List: ML20211M230 ML20211M240 ML20211M245 ML20211M253 ML20211M257 ML20211M264
References
LCR-H97-05, LCR-H97-5, LR-N97528, NUDOCS 9710140110
Download: ML20211M257 (7)

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E4ctrc and Gas Crvey E. C. Sempeon Put*c Servce bectne and Gas Company P.O Box 236, Hancocks Bndge, NJ 08038 60 4 334 1700 wo u.e e m. cm E II E LR-N97528 LCR H97-05 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REQUEST FOR CHANGE'TO TECHNICAL SPECIFICATIONS (SUPPLEMENT)

SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR)

HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DDCNET No. 50-354 i

Gentlemen:

! On March 31, 1997, Public Service Electric & Gas (PSE&G) Company transmitted, via letter LR-N97187, a proposed' change to the Hope Creek Technical Specifications (TS). The proposed changes revised TS 2.1.2, " THERMAL POWER, High Pressure and High Flow",

ACTION a.1.c for LCO 3.4.1.1, " Recirculation Loops" and the Bases for TS 2.1, "Safaty Limits". The changes contained in that request implemented an appropriately conservative Safety Limit Minimum Critical Power Ratio (SLMCPR) for Hope Creek's Cycle 7 (current cycle) core and fuel designs. Justification for those proposed changes was developed from General Electric SLMCPR analyses performed to address SLMCPR issues identified in a 10CFR21 notification made by General Electric on May 24, 1996.

On July 16, 1997, PSE&G supplemented the March 31, 1997, submittal to provide revised SLMCPR values for the upcoming operating cycle (Cycle 8). As a result of NRC questions received concerning the differences between the Cycle 7 and Cycle 8 SLMCPR values, PSE&G is providing additional information contained in Attachment 1 of this letter. PSE&G has determined that the information contained in this letter does not alter the conclusions reached in the 10CFR50.92 No Significant Hazards analysis previously submitted with LCR H97-05 in the July 16, 1997 letter. In accordance with 10CFR50.91(b) (1), a copy of this submittal has been sent to the State of New Jersey.

Attachment 2 of this letter provides revised Technical Specification Bases pages associated with Hope Creek Technical Specification Amendment No. 101, issued on July 24, 1997 The Bases pages revised by Amendment No. 101 impacted the same section as Technical Specification Amendment No. 100, also issued on July 24, 1997 Therefore, the Bases pages for Amendment No.

THE INFoRMATIoN CONTAINED IN ATTACHMENT 1 or THIS LETTER IS PROPRIETARY

- NoT FoR PUBLIC DISCLo3URE -

9710140110 971003~

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ADOCK 05000354 pg m-___m

Aus se ny Document Control Desk LR-N97528 101 are-being revised to reflect the changes already approved through the issuance.cf Amendment No. 100.

Should you have any questions regarding this request, we will be pleased to discuss them with you.

Sincerely, i

Affidavit Attachments (2)

C Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - HC U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. S. Morris (X24)

USNRC Senior Resident Inspector - HC Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway-CN 415 Trenton, NJ 08625 a

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Document Control Desk - AUG881REL LR-N97528-

-JPP ,

- BC- Senior Vice Prosident_- Nuclear Engineering (N19)

General Manager - Hope Creek _ Operations (H07)

Director - QA/NSR (X01)

Director - Licensing / Regulation and' Fuels (N21)

Manager - Business _ Planning & Co-Owner Affairs (N18)

Manacer - Hope Creek Operations.(H01)

Manager - System Engineering - Hope Creek (H18 ) -

Manager - Nuclear Review Board (N38)

Manager.- Hope Creek Licensing (N21)

Supervisor - Hope Creek Fuels (N20) ,

J. J. Keenan, Esq. _ (N21)

Records Management (N21)

Microfilm Copy Files Nos. 1.2.1 (Hope Creek), 2.3 (LCR H97-05) e i , ,- y , ,, 1rv'-

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REF: LR-N97528 LCR H97-05 STATE OF hTW JERSEY )

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COUNTY OF SALEM )

E. C. Simpson, being duly sworn according to law deposes and says:

I am Senior Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Hope Creek Generating Station, Unit 1, are true to the best of my knowledge, information and belief.

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• Subscribed and Sworn to before me this 2(o day of b d , 1997 0

fML G.

NotaryPudeofN[ Jersey WM.

EUZABETH J. KIDD NOTARY PU8UC OF fGf JERSEY W Cane Epos Apet 25. 2000 My Commission expires on

.- Dccument CSntrol DOOk LR-N97528 Atccchment 1 LCR H97-05 i

HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 '

DOCKET NO. 50-354 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SIJ4CPR) CHANGES 4

• ADDITIONAL INFORMATION CONCERNING HOPE CREEK CYCLE 7 AND CYCLE 8

SLMCPR LIMITS

The Hope Creek Cycle 7 and Cycle 8 cores are both 100% comprised of the GE9B thermal-mechanical fuel design. Both cycles have similar core enrichments of 3.25% and 3.231 and similar reload I

batch fractions of 30.43 and 30.9% respectively.

Since the absolute value of the SLMCPR is significantly driven by the uncertainty in core and bundle power peaking distributions, core average parameters do not provide adequate insight to gauge the impact on SLMCPR. A closer look at the factors which influence the localized bundle pin peaking and core radial i peaking factors will reveal the driving forces behind the SLMCPR 1 differences.

The following bundle types are currently loaded into Hope Creek Cycle 7:

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Number Bundle Description Cycle First s

Loaded 4 52 GE9B-P8CWB325-11GZ2-80M-150-T 4 184 GE9B-P8CWB325-31GZ2-80M-150-T 5 1 64 GE9B-P8CWB325-11GZ1-80M-150-T 5 144 GE9B-P8CWB324-9GZ1-80M-150-T 6 88 GE98-P8CWB325-11GZ1-80M-150-T 6 144 GE9B-P8CWB324-9GZ1-80M-150-T 7 88 GE9B-P8CWB325-11GZ1-80M-150-T 7 The following bundle types are currently loaded into Hope Creek Cycle 8:

Number Bundle Description Cycle First Loaded 56 GE9B-P8CWB325-11GZ2-80M-150-T 5 8 GE9B-P8CWB325-11GZ1-80M-150-T 5 144 GE9B-P8CWB324-9GZ1-80M-150-T 6-88 GE98-P8CWB325-11GZ1-80M-150-T 6 144 GE98-P8CWB324-9GZ1-80M-150-T 7 88 GE9B-P8CWB325-11GZ1-80M-150-T 7 176 GE9B-P8CWB327-8GZ1-80U-150-T 8 60 GE9B-P8CWB298-8GZ-80U-150-T 8 THIS ATTACHMENT CONTAINS PROPRIETARY INFORMATION

- NOT FOR PUBLIC DISCLOSURE -

Page 1 of 3

• Document Control Desk LR-N97528 Attachment 1 LCR H97-05 Although these fuel bundles are all of the GE9B thermal- g mechanical design, they differ in their nuclear characteristics.

Pin-by-pin enrichment loading, gadolinia burnable poison loading, as well as axial zoni,ng of the enrichments and burnable poisons give rise to diffecing pin peaking distribution behaviors. The fact that only approximately one third of the core is loaded with fresh fuel each cycle (a bundle is expected to be resident in the core for at least three cycles) means that different regions of fuel will achieve their different peaking characteristics at ditforent times during their individual lifetimes. A once burnt region of fuel can be reaching its peak reactiv!ty at the same time that a similarly designed twice burned region of fuel will be reaching its minimum.

These differing nuclear characteristics provide a spectrum of peaking distributions, which are not necessarily repeatable from

, once cycle to anothe: Inspection of the tables above will show that Cycle 8 is only now discharging fuel originally loaded in Cycle 4. The influence of these Cycle 4 bundles had on the Cycle 7 peaking distributions will no longer be experienced in Cycle 8.

Closer inspection of some of the differences between the GE generic GE9 SLMCPR evaluation and the Hope Creek specific evaluations for Cycles 7 and 8 ccnfirms these effects:

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Paramete" Generic GE9 Hope Creek Hope Creek C cle 7 C cle 8 Limitin Ex30sure SLMCPR 1.07 1.08 1.10

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ot tye es ano ave ue ouno e pin peaking d' ributions which give rise to less limiting The radial peaking istricutions of t hree evaluations are ite different, though. The4 Egg $)

nd maximum radial peaking factors (RPFs) reveal that 7 has a MCPR distribution similar to that of the Generic GE9, but Cycle 8 shows a much more pronounced effect on the SLMCPR due to its initial MCPR distribution. A THIS ATTACHMENT CONTAINS PROPRIETARY INFORMATION

- NOT FOR PUBLIC DISCLOSURE -

Page 2 of 3

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, Dscument Control D30k LR-N97528 Attechment 1 LCR H97-05 larger percentage of the bundles in the Cycle 8 core are near the limiting MCPR (i.e., a much flatter MCDR distribution). The importance of the flatter MCPR distribution in Cycle 8 is the increase in critical power ratio (CPR) uncertainty, and its subsequent increase in SLMCPR.

t THIS ATTACHMENT CONTAINS PROPRIETARY INFORMATION

- NOT R)R PUBLIC DISCLOSURE'-

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