ML20134F612

Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative

ML20134F612
Person / Time
Site:	Peach Bottom
Issue date:	10/30/1996
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20134F611	List: ML20134F609 ML20134F612
References
NUDOCS 9611070060
Download: ML20134F612 (4)

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ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNIT 3 Docket No. 50-278 License No. DPR-56 TECHNICAL SPECIFICATIONS CHANGES Attached Page Unit 3 TS Page 2.0-1

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l 9611070060 961030 PDR ADOCK 05000278 p

PDR

SLs i

2.0

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,,2.0,. SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

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THERMAL POWER shall be s 25% RTP.

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2.1.1.2 With the reactor steasa dome pressure m 785 psig and core i

flow = 10% rated core flow:

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) Ao MCPR shall be E..;;7 for two recirculation loop operation

/.UO opfor single recirculation loop operation.

i 2.1.1.3 Reactor vessel water level shall be greater than the tnp of active irradiated fuel.

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2.1.2 Reactor Coolant System Pressure SL j

i Reactor steam done pressure shall be s 1325 psig.

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2.2 SL Violations With any SL violation, the following actions shall be completed:

i 2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance j

with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.2.1 Restore compliance with all SLs; and j-2.2.2.2 Insert all insertable control rods.

j 2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Plant Manager and the Vice President-l Peach Bottom Atomic Power Station.

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PBAPS UNIT 3 2.0-1 Amendment No. 214 J.

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i ATTACHMENT 3 4

PEACH BOTTOM ATOMIC POWER STATION i

UNIT 3

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l Docket No. 50-278 Ucense No. DPR-56 UCENSE CHANGE APPUCATION ECR 9642600 i

Letter from R. M. Butrovich (GENE) to H. J. Diamond (PECO Energy), " Peach Bottom Unit 3 Safety Umit MCPR Revision," dated July 7.1996

p GE Nuclear Energy RochardM Buttonch

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2-July 7,1996

~1' cc: J. M. Carmody RMB:96-146 C. M. Ionescu G. C. Storey Mr. H. J. Diamond, Director Fuel & Senices Division PECO NUCLEAR 965 Chesterbrook Boulevard Wayne, PA 19087-5691

SUBJECT:

Peach Bottom Unit 3 Safety Limit MCPR Revision

REFERENCE:

1. Letter, R. M. Butrovich to H. J. Diamond, " Generic gel 1 Safety Limn MCPR Calculation", April 2,1996 l

2. Letter, R. M. Butrovich to H. J. Diamond, " Peach Bottom Unit 3 Safety Limit MCPR", May, 31,1996.

3. Letter, R. M. Butrovich to H. J. Diamond, " Peach Bottom 3 Cycle 11 SRLR Revision 1", June 14,1996.

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Dear Hugh:

l Reference 1 advised PECO Nuclear of discoveries related to the methodology used by GE to calculate SLMCPR that indicated the generic SLMCPR may not always yield the most conservative result. GE performed a plant unique evaluation for Peach Bottom Unit 3 and reported the results to PECO Nuclear in reference 2. 'Ilie SLMCPR for Peach Bottom Unit 3 Cycle 11 went from 1.07 (gel 1 Generic) to 1.08 (Cycle specific). The single loop operation SLMCPR is 1.09. Reference 3 provided a revised Supplemental Reload Licensing Report for Peach Bottom Unit 3 Cycle 11. PECO Nuclear should submit a technical specification revision indicating the revised cycle specific SLMCPR.

Ifyou have any questions, please give me a call.

Very truly yours, f

/ialuu-M. Butrovich

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