ML20155D943
| ML20155D943 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/27/1998 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20138L488 | List: |
| References | |
| NUDOCS 9811040089 | |
| Download: ML20155D943 (3) | |
Text
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Attachm:nt 3 PY-CEl/NRR-2325L Page 1 of 3 l
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PROPOSED CHANGES TO 1
1 TECHNICAL SPECIFICATIONS l
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9811040089 981027 i
PDR ADOCK 05000440.
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m PY-CEl/NRR-2325L PEgG2of3 SLs 2.0 1
l 2.0 SAFETY LIMITS (SLs) 1 2.1 SLs 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:
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:
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Sly applicable for Cycle 7 cperation t
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MCPR 1 be a 1.09 for two recirculation loop operation or 2 -He for single recirculation loop operation.
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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 Reactor steam dome pressure shall be 5 1325 psig.
2.2 SL Violations With any SL violation, the following action' shall be completed:
s 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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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.
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The core operating limits shall be determined such that all l
applicable limits (e.g., fuel. thermal mechanical limits.
core thermal hydraulic limits. Emergency Core Cooling i
Systems (ECCS) limits, nuclear limits such as SDM. transient l
analysis limits. and accident analysis limits) of the safety analysis are met.
d.
The COLR. including any midcycle revisions or supplements.
shall be provided upon issuance for each reload cycle to the NRC.
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 PERRY - UNIT 1 5.0-18 Amendment No. 91 l
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