ML20117H676

Proposed Tech Specs 2.0 Re Safety Limits

ML20117H676
Person / Time
Site:	Peach Bottom
Issue date:	08/23/1996
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20117H673	List: ML20117H671 ML20117H676
References
NUDOCS 9609090368
Download: ML20117H676 (4)

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ATTACHMENT 1  ;

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PEACH BOTTOM ATOMIC POWER STATION UNIT 2 l

Docket No. 50-277 i i

License No. DPR-44 t

TECHNICAL SPECIFICATIONS CHANGES l t

Attached Page i Unit 2 TS Page 2.0-1 l

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9609090368 960823 PDR ADOCK 05000277 p PDR

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, SLs 2.0 2.0 SAFETY LIMITS (SLs) i I

2.1 SLs 2.1.1 Reactor Core sts 2.1.1.1 With the reactor steam done pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam done pressure a: 785 psig and core flow a:10% rated core flow:

R shall be 2: for two recirculation loop operation

or a

5y3t for si recirculation loop operation.

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

2.1.2 Reatter Coolant System Pressure St Reactor steam dome pressure shall be s 1325 psig.

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

2.2.1 Within I hour, notify the NRC Operations Center, in accordance 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 2.2.2.2 Insert all insertable control rods.

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--

Peach Bottom Atomic Power Station.

(continued) 1 PBAPS UNIT 2 2.0-1 Amendment No. 210 i

ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 Docket No. 50-277 License No. DPR-44 REVISION TO LICENSE CHANGE REQUEST NO. 96-01 Letter from R. M. Butrovich (GENE) to H. J. Diamond (PECO Energy), " Peach Botton Unit 2 Cycle 12 Safety Limit MCPR," dated August 8, 1996 j

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GE Nuclear Energy l Lhard M Butrovoch

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, : ,a August 8,1996 -

s sid ~ cc: J. M. Carmody l RMB:96-160 T. R. Loomis l G.C. Storey )

D. B. Wahermire C. W. Smith Mr. H. J. Diamond, Director Fuel & Senices Division PECO NUCLEAR 965 Chesterbrook Boulevard Wayne, PA 19087-5691 l

SUBJECT:

Peach Bottom Unit 2 Cycle 12 Safety Limit MCPR

REFERENCE:

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

Dear Hugh:

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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 has performed a plant unique evaluation for Peach Bottom Unit 2 Cycle 12. The SLMCPR is 1.11 (Generic GE13 is 1.09). He single loop operation SLMCPR is 1.13. He calculation was based upon USNRC approved methods (" General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-11, and U.S. Supplement, NEDE-24011-P-A-11-US, November 17,1995) and interim implementing procedures. Resision i1 of the aforementioned document, "GESTAR II", requires that the SLMCPR be reconfirmed each cycle. His reconfirmation was performed using the interim implementing procedures which the NRC staff discussed with GENE during their meetings on April 17,1996 and May 6,1996 through May 10,1996. Rese interim procedures include cycle-specific parameters which include: 1) the actual core loading,2) conservative variations ofprojected control blade pattems,3) the actual bundle parameters (e.g., local peaking), and 4) the full cycle exposure range.

if you have any questions, please give me a call.

Very t yours, 1

M. Butrosich Fuel Project Manager