ML20214W223

Application for Amend to License NPF-57,changing Tech Specs to Include New Min Critical Power Ratio Curve & Reflect Inoperable Status for end-of-cycle Recirculation Pump Trip. Fee Paid

ML20214W223
Person / Time
Site:	Hope Creek
Issue date:	12/05/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML20214W226	List: ML20214W223 ML20214W280
References
NLR-N86188, NUDOCS 8612100131
Download: ML20214W223 (6)

Text

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k m Pubhc Somce

% Electric and Gas

, Company Corbin A. McNeill, Jr. Pubhc Service Electric and Gas Company P.O. Box 236. Hancocks Bridg<3, NJ 08038 609 339-4800 Vice President -

Ngea' December 5, 1986 s NLR-N86188 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 5 7920 Norfolk Avenue Bethesda, Maryland 20814 s

Attention: Ms. Elinor Adensam, Director Project Directorate #3 Division of BWR Licensing

Dear Ms. Adensam:

t REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION - DOCKET NO. 50-354 In accordance with the Atomic Energy Act of 1954, as aucnded and the regulations thereunder, we hereby transmit copies or our request for amendment. and our analyses of the changes to Facility

, Operating License NPF-57 for Hope Creek Generating Station.

The amendment consists 'of a new Minimum Critical Power Ratio (MCPR) Technical Specification curve which would allow for operation with the End-of-Cycle Recirculation Pump Trip (EOC-RPT) inoperable. Additionally, the Technical Specification Action Statement for the EOC-RPT has been modified to reflect the inoperable status.

s Enclosed is a check in the amount of $150.00 required by Y 10CPR170.21.

Pursuant to the requirements of 10CFR50.91, a copy of this g request for amendment has been sent to the State of New Jersey as indicated below. -

This submittal includes 3 signed originals and 40 copies.

Sincerely, 0612100131 861205' PDR ADOCK 05000354 p PDR -

1 Enclosure b

. 81 Rec.*Iwhecu' f a sb

e Director of Nuclear 2 Reactor Regulation C Mr. D. H. Wagner USNRC Licensing Project Manager Mr. R. W. Borchardt USNRC Senior Resident Inspector Mr. David M. Scott, Acting Chief Bureau of Nuclear Engineering Departrient of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Honorable Charles M. Oberly, III Attorney of General of the State of Delaware 820 North French Street _

Wilmington, DE 19801 b, - , -

r STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

Corbin A. McNeill, Jr. , being duly sworn according to law deposes and says:

I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated December 5, 1986, concerning Hope Creek Generating Station, is true to the best of my knowledge, information and belief.

, x Subscribgd and Sworn to before me this I day of afecek , 1986 h '"

_ Kotary Putilic of New Jersey LARAINE Y. BEARD Nolery Public of New Jersey My Commission expires on y Com& Empreshy l,190

P 1 1 9_f.i P t i o D _ o f C h aE g e;_

This proposed change to the HCGS Technical Specifications will incorporate recent analysis to allow continued operation of the unit when the End of Cvele Rectreulation Pump Trip Function

( EOC-RPT) is inoperable. The changes will affect the following Technical Specifications:

T/ S 3.2.3 MINIMUM CRITICAL POWER RATIO T/S 3.3.4.2 END-of-CfCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION Pla s o n f or.__C halg11.

Current Technical Specifications Action Statements for EOC-RPT inoperable will ultimately lead to the derating of the unit to less than 30% of RATED THERMAL POWER. This is because the current HCGS FSAR Chapter 15 analysts assumes that the EOC-RPT function is available. Should testing determine that the EOC-RPT function is inoperable, this Techntcal Spectrication change will allow the unit to continue operatton based on the new analysts assuming the EOC-RPT function is not available.

n S_1.gn Lfj.g a nt Hu a r d s_C o n s i d e r a t i g_n_;_

Safety analysis was performed by the General Electric C o. , and the results reviewed by the Nuclear Fuel organization at PSE&G.

The following HCGS FS AR Chapter 15 transients were reanalyzed:

Generator Load Rejection Without Bypass Feedwater Controller Failure Under normal circumstances, when the Turbine Stop Valves reach the s 5% closed position, or the Turbine Control Valves receive a fast closure signal of a 530 psig, then a Rectreulation Pump Trip

( RPT) is initiated. This ensuing flow coastdown following the RPT will rapidly introduce voiding in the core and limit the reactivity excursion caused by the pressurization transtent. For Hope Creek, these transients are limiting at the End of Cycle.

The reanalysis that was performed assumed that the EOC-RPT function was not available to insert negative reactivity via rapid void formation. The recirculation pumps are assumed to continue to operate at nominal conditions with no flow coastdown.

The delta-CPR for the events was analyzed, and the impact on the Operating Limit Minimum CPR is shown on the mark-up of the Technical Specification Figure 3.2.3-1. The MCPR Limits provided by this analysis and shown in this figure can be considered to be overly conservative for the following reasons:

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1. The current Technical Specification curve for RPT is based on the first cycle EOC conditions (t.e.. the most limiting condi tion)

2. The attached curve constders a lack of EUC-RPT at any time throuahout the evcle and is therefore based on a

" worst-case" scenarto and ts valid for all power levels.

3. The attached curve considers not only the Generator Load Rejection Without Bypass. but also the Feedwater Controller Failure event. This is done in order to address both the ODYN Option A and Option B evaluations of operating limits with the EOC-RPT inoperable.

In the event that the EOC-RPT function was not operable as defined by Technical Specifications, then the above analysis would be bounding for the continued safe operation of the plant, by using the required CPR Operating Limits.

The proposed change does no involve a significant hazards consideration because operation in accordance with this change would not:

1. Involve a significant increase in the probability or consequences of an accident previously analyzed. The limiting overpressurization transients in HCGS FSAR Chapter 15 have been reanalyzed for their impact on the Operating Limit MCPR. The results of this analysis shows that for the ODYN Option A. the Operating Limit MCPR was increased from 1.20 to 1.28 to account for the EOC-RPT function being inoperable. For the ODYN Option B. the analysts showed that the limiting over-pressurization transzents were bounded by the non-pressurization transients such as Loss of Feedwater Heater or Rod Withdrawal Error ( Ref erence HCGS FSAR Ftqure 15. 0 - 3 ) . Sir.ce the analysis differs in the operability of the EOC-RPT function only, and not the initiating circumstances, the probablilty of the event occurring does not increase. With the increased Operating Limit MCPR. the analyzed transients will not violate the Safety Limit MCPR, and therefore the consequences of the event are not increased.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated. The creation of a new, different ki nd of accident from any previously evaluated accident is not considered a possibility. No hardware modifications are being made, and the scope of the current safety analysis is actually being expanded. The proposed Technical Specification change has also already been included in a number of other BWR/4's Tech. Specs. ( e. g. Limerick, Susquehanna) .

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3. Involve a reduction in a margin of safety. The analysis provided here has recalculated the delta-CPR of the two limiting overpressurization transients for HCGS. These new delta-CPR calculations, along with the current HCGS FSAR safety analysis, have provided the Operating Limit MCPR for EOC-RPT operable or inoperable. Operation with respect to these limits will insure that the margin of safety for the Cycle 1 Safety Limit MCPR will be maintained.

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