ML20155D943

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Proposed Tech Specs 2.1.1.2,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by GE
ML20155D943
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 10/27/1998
From:
CENTERIOR ENERGY
To:
Shared Package
ML20138L488 List:
References
NUDOCS 9811040089
Download: ML20155D943 (3)
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Attachm:nt 3 PY-CEl/NRR-2325L l

Page 1 of 3 I .

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PROPOSED CHANGES TO 1

TECHNICAL SPECIFICATIONS l

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{ 9811040089 981027 i PDR ADOCK 05000440.

i P PDR

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" ' Attachment 3

, PY-CEl/NRR-2325L

. - -- - PEgG2of3 SLs 2.0 1 l . .

2.0 SAFETY LIMITS (SLs) 1 2.1 SLs l 1

2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core j flow < 10% rateu core flow: 1 THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam dome pressure a .'85 psig and core flow = 10% rated core flow:

r. . . . . . . . _ _ _ _ _ . . . . . . . . . .-tete. - - - - - - - - - - - - - - - - - - - - - - - - - - 7 l Sly applicable for Cycle 7 cperation t

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1 MCPR 1 be a 1.09 for two recirculation loop operation l or 2 -He for single recirculation loop operation. i 1.11] l 2.1.1.3 Reactor vessel water level shall be greater than the top j of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL l Reactor steam dome pressure shall be 5 1325 psig.

2.2 SL Violations With any SL violation, the following action' sshall be completed:

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 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:

l 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 corporate executive responsible for overall plant nuclear safety.

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PERRY - UNIT 1 2.0-1 Amendment No. 91 l

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" Attachment 3

. l PY-CEl/NRR-2325L Pege 3 of 3 Reporting Requirements 5.6

'5.6 Reporting Requirements 5.6.5 Core Operatina Limits Reoort (COLR) (continued) 4 LCO 3.3.1.1. RPS Instrumentation (SR 3.3.1.1.14):

, b. The analytical methods used to determine the core operating l

limits shall be those previously reviewed and approved by the NRC in NEDE-24011-P-A General Electric Standard l Application for Reactor Fuel. (The ap roved re' vision at the time relo analyses are performed sha 1 be identified in the COLR. l l c. The core operating limits shall be determined such that all I applicable limits (e.g. , fuel. thermal mechanical limits. I core thermal hydraulic limits. Emergency Core Cooling i Systems (ECCS) limits, nuclear limits such as SDM. transient l l analysis limits. and accident analysis limits) of the safety l analysis are met.

d. The COLR. including any midcycle revisions or supplements. 1 shall be provided upon issuance for each reload cycle to the '

NRC.

1 5.6.6 Soecial Reoorts l l

Special Reports shall be submitted in accordance with 10 CFR 50.4 l within the time period specified for each report.

The following Special Reports shall be submitted:

a. Violations of the requirements of the fire protection program described in the USAR which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported via the Licensee

! Event Report system.

l I + for Cyck 7. ;; apprc'/cd ir, the PRC S0fcty O/;katicr. Rcport dotcd ' l Mc'veder '7 . 1997 l

PERRY - UNIT 1 5.0-18 Amendment No. 91 l

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