ML20101K813

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Proposed Tech Specs Section 2.0 Re Safety Limits
ML20101K813
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/25/1996
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20101K803 List:
References
NUDOCS 9604030078
Download: ML20101K813 (4)


Text

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 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 dome pressure a 785 psig and core flow a 10% rated core flow:

MCPR 1 be a r two recirculation loop operation or a Tor single recirculation loop operation.

2.1.

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

2.1.2 Reactor Coolant System Pressure SL 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)

PBAPS UNIT 2 2.0-1 Amendment No. EM-9604030078 960325 PDR ADOCK 05000277 P

PDR

l SLs 2.0 2.0 SAFETY LIMITS (SLs) l 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:

THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam dome pressure a: 785 psig and core ow 2: 10% rated core flow:

MCPR shall be a:-Iv0Ffor two recirculation loop operation or at 208"f6r single recirculation loop operation.

l.Il 2.1.1.

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

2.1.2 Reactor Coolant System Pressure SL Reactor steam done 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 P, esident--

Peach Bottom Atomic Power Station.

!contirq3Q PBAPS UNIT 3 2.0-1 Amendment No. 314--

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ATTACHMENT 3 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Docket Nos. 50-277 50-278 Ucense Nos. DPR-44 DPR-56 UCENSE CHANGE REQUEST No. 9641 i

Letter from R. M. Butrovich (GE Nuclear Energy) to H. J. Diamond (PECO Energy), "GE13 Single Loop Operation SLMCPR,"

dated June 12,1996 i

i

9 GE Nuclear Energy

' ~ 5Itarfuel Atrences llichard M. Butrovich fuelPic;ect Ma?'ager General Elec:nc Ccmcany P.O. S:s 180. MIC; A33 Wilmington.NC 284010780 910 615 6266 h sr0 675-5684 cc: R. A. Hanvelt June 12,1995 S. P. Congdon RMB:95-125 J. F. KIapproth J. M. Cannedy i

Mr. H. J. Diamond, Director Fuel & Services Division PECO ENERGY COMPANY 965 Chesterbrook Boulevard Wayne, PA 19087-5691

SUBJECT:

GE13 Single Loop Operation SLMCPR

REFERENCE:

1. Letter, J. F. Klapproth to NRC-DCD, " Completion of GE13 Licensing Qualifcation", December 30,1993.
2. Letter, J. F. KIapproth to R. C. Jones Jr., " Safety Limit MCPR for GE13 Fuel",

September 27,1994.

Dear Hugh:

In Reference (1) GE notified the NRC that the GE13 design fully complies with the GESTAR-II Amendment 22 acceptance criteria for new fuel designs. Reference (2) requested NRC approval of the generic GE13 SLMCPR (1.09) to facilitate utility implementation of GE13 Fuel. Prior NRC approval would allow future utility technical speci6 cation amendment requests to be treated as an administrative change.

Single Loop Operation (SLO)is considered as a special case for the Safety Limit MCPR. The uncertainty associated with the core flow measurement is greater for this case. It has also been demonstrated that SLO results in increased noise in neutron flux measurements. The SLMCPR for SLO is determined in the same manner as the reference SLMCPR value, accounting for tne increased uncertainty in core flow and TIP/LPRM measurements.

The Single Loop Operation Safety Limit MCPR (1.ll) may be applied to Limerick Units 1 and 2 and Peach Bottom Units 2 and 3 with GE13 fuel. Transition cycles incorporating GE13 fuel are expected to be bounded by this analysis. The GE13 SLO Safety Limit MCPR analysis has been performed in compliance with Amendment 22 of GESTARII andis documented in DRF A00-05616-1.

Very trul > yours, t

i L Butrovich