ML20215H774

Application for Amend to License NPF-57,revising Figure for Min Critical Power Ratio to Reflect Analysis Performed as Result of Testing During Recent Power Ascension Test Program.Safety Evaluation Encl.Fee Paid

ML20215H774
Person / Time
Site:	Hope Creek
Issue date:	04/30/1987
From:	Corbin McNeil Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20215H776	List: ML20215H774 ML20215H779
References
NLR-N87075, NUDOCS 8705070040
Download: ML20215H774 (6)

Text

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Public Service Electric and Gas -

Company l Corbin A. McNeiH, Jr. Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609 339-4800 l sea vee eradent .

Nuclear APR 3 01967 NLR-N87075 l

f United States Nuclear Regulatory Commission-Document Control Desk Washington, DC 20555 REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 l In'accordance with the requirements of 10 CPR 50.90, Public

! Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance'with the requirements of 10 CPR 170.21, a check in the amount of $150.00 is enclosed. In accordance with the requirements of 10 CPR 50.91(b)(1), a copy of this request for amendment has been sent to the State of New Jersey as indicated below.

This amendment request revises the figure for the Minimum Critical Power Ratio (MCPR) (see Attachment 2). This change-reflects a new analysis performed as a result of' testing during the recent Power Ascension Test Program (see Attachment 1).

This submittal includes one (1) signed original, including affidavit, and thirty-even (37) copies pursuant to 10 CFR 50.4(b)(2)(ii).

l Should you have any questions on the subject transmittal, please do not hesitate to contact us.

Sincerely, l

'- $ s 8705070040 870430 PDR ADOCK 05000354 P PDR h

Enclosure (check) ,I 40 0

Affidavit ,gb. T k(

Attachments (2) \

Document Control Desk 2 APR 3 0 MW . ,

I C Mr. G. W. Rivenbark NRC Licensing Project Manager t Mr. )R. W. Borchardt i NRC Senior Resident Inspector Director, Bureau of Radiation Protection l Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Regional Administrator, Region I U. S. Nuclear Regulatory Commission

631 Park Avenue

-King of Prussia, PA 19406 4

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Ref: LCR 87-05 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

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

I am Senior Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated APR 3 01987 , concerning Facility Operating License NPF-57 for Hope Creek Generating Station, is true to the best of my knowledge, information and belief.

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w d and Sworn to b 9 fore me Subscribp/

thisAFj, day of _Agg,*/ , 1987 e

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' Notary Public of New Jersey DEMM D. HADOW A PuhtselNewJussy My Commission expires on Mr B # ssiluut M 1900

ATTACHMENT 1 .,

HOPE CREBE GENERATIN3 STATION LCR 87-05 ,

END-CF-CYCLE RECIRC. PUNP TRIP REANALYSIS SAFETY-EVALUATION Page 1 of 3 t

Descrintion of Chanae:

The purpose of this LCR is to request a change to the Hope Creek

j. Technical Specifications. -

This change will reflect new analysis perf ormed as a result of testing performed during the recent Power Ascenion Test Program. The proposed change will affect the

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following Technical Specification:

f T/S Figure 3.2.3-1 MINIMUM CRITICAL POWER RATIO ( MCPR)

VERSUS T AT RATED PLOW i Reason for Chance:

l l During the Power Ascension Test Program, the flow coastdown of i

the reactor recirculation pumps was found to be non-conservative with respect to those values assumed in the Final Safety Analysis Report ( FS AR) . Recirculation Pump Trips are used to introduce j voiding into the core to minimize the subsequent power escursion 1

following a postulated pressurization transient, such as a j Generator Load Rejection without Bypass, or a Feedwater Controller l Failure '( High) . The required pump coastdown curve and the as-tested coastdown curves from two startup tests are shown in i i Figure A of the attached letter from General Electic Co.

l Because of the effect on transient power levels, this analysis is ,

4 instrumental in developing the Operating Limit Minimum Critical 1 Power Ratio ( OLMCPR), and its associated Tech. Spec. ( T/ S 3 / 4. 2. 3) .

l This Tech. Spec. was therefore also non-conservative. Continued operation of the unit after the test program was made possible with the inclusion of Amendment 1 to the Facility Operating License, dated January 5, 1987, and by declaring the ROC-RPT I system. inoperable, with the appropriate actions taken as de-scribed in Technical Specifications 3/4.2.3 and 3/4.3.4.2.

1 New analysis has been performed which assumes a recirculation l flow coastdown which bounds the as-tested values. This new j analysis is now conservative with respect to the actual operation 1 of the plant. Because the analysis assumes a more cor3eervative

! coastdown, the newly determined OLMCPR's with the ROC-RPT system

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operable may now be revised in the Tech. Specs., and operation may continue without declaring the EOC-RPT system inoperable.

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31anificant Masards Consideration:

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

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The following HCGS FSAR Chapter 15 transients were reanalysed:

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Generator Load Rejection Without Bypass Feedwater Controller Failure ( Maximum Demand) i l

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. HCPR CREEE GENERATIN3 STATION LCR 87-05 END-OF-CYCLE RECIRC. PUNP TRIP REANALYSIS SAFETY EVALUATION

Page 2 of 3

The precisa values of the OLMCPRs as determined by this analysis are reported in the attached letter from General Electric Co.

The FSAR assumes that when the Turbine Stop Valves reach the s 55 closed position, or the Turbine Control Valves receive a fast closure signal of a 530 peig, then a Recirculation Pump Trip

( RPT) is initiated. The ensuing flow coastdown following the RPT l will rapidly introduce voiding in the core and limit the reactivity excursion caused by the pressurisation transient. For Hope Creek, these transients are limiting at. the End of Cycle, j i  :

j The reanalysis that was performed assumes that the ROC-RPT function was slower than that measured in the plant. This ,

assumes a lesser capability to insert negative reactivity via l rapid void formation. The delta-CPR for the events was analysed, ,

1 and the impact on the OLMCPR is shown on the mark-up of the  !

l Technical Specification Figure 3.2.3-1. The MCPR Limits provided l

{ by this analysis and shown in this figure can be considered to be j overly conservative for the following reasons: l 1

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1. The Technical Specification curves for RPT are based on

! the first cycle EOC conditions ( i. e. , the most limiting j condition)

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greater transient power excursion due to fewer voids l

, being formed in the core.

I i 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 3 of operating limits with the EOC-RPT inoperable.

j The proposed change does not involve a significant hazards

consideration because operation in accordance with this change j would not

l 1. Involve a significant increase in the probability or

) consequences of an accident previously analysed. The i

limiting overpressurisation transients in HCGS FSAR j Chanter 15 have been reanalysed for their impact on the Operating Limit MCPR. The results of this analysis 4

show that for the ODYN Option A, the Operating Limit

! MCPR was increased f' rom 1. 20 t o 1. 2 3 to account for the slower EOC-RPT coastdown. Far the ODYN Option B, the analysis showed that the limiting overpressurization 3 transients were bounded by the non- pressurization

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transients such as Loss of Feedwater Heater or Rod Withdrawal Error ( Reference HCGS FSAR Figure 15. 0-3) .

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- HOPE CREEK GENERATING STATION LCR 87-05 END-OF-CYCLE RECIRC. PUMP TRIP REANALYSIS SAFETY EVALUATION Page 3 of 3 4

Since the analysis differs in the speed of the EOC-RPT coastdown only, and not the initiating circumstances, the probablilty of the event occurring does not increase.

With the increased Operating Limit MCPR. the analysed transients will not violate the Safety Limit MCPR. and therefore the consequences of the event are not in-creased.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated. The creation of a new. different kind of accident from any previously evaluated accident is not considered a possibility. No hardware modifications are being made.

! The safety analysis that was performed only assumes a I

different coastdown than the FSAR analysis, and is more conservative than the actual coastdown measured at the plant.

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

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