ML20217F591

Proposed Tech Specs,Adding Note to TS 2.1.1.2 Re MCPR SL Values & Adding Footnote to TS 5.6.5.b to Reference NRC SER That Approved MCPR SL Values for Cycle 7

ML20217F591
Person / Time
Site:	Perry
Issue date:	10/02/1997
From:	CENTERIOR ENERGY
To:
Shared Package
ML20217F590	List: ML20217F591 PY-CEI-NRR-2218, Documents Agreement to NRC Proposed Clarifications That Would Add Note to TS 2.1.1.2 & Add Footnote to TS 5.6.5.b. Revised TS Pages W/Clarifications,Encl
References
NUDOCS 9710080308
Download: ML20217F591 (2)

Text

i b

SLs i

2.0 2.0 SAFETY LlHITS (SLs) 2.1 SLs

)

2.1.1 Reactor Core SLs 2

2.1.1.1 With the reactor steam dome pressure < 785 psig or core j

flow < 10% rated core flow:

l THERMAL POWER shall be s 25% RTP.

I i

2.1.1.2 With the reactor steam dome pressure = 785 psig and core 7

flow = 10% rated core flow:

i

........................ NOTE---

Only applicable for Cycle 7_ operation.

i i

MCPR shall be = 1.09 for two recirculation loop operation j

or = 1.10 for single recirculation loop operation.

2 1

2.1.1,3 Reactor vessel water level shall be greater than the top -

of active irradiated fuel.

1 j

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 5 1325 psig, i

i 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 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

2.2.2.2 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.

(continued) 9710080308 971002 PDR ADOCK 05000440 P

PDR

. PERRY - UNIT 1 2.0-1 Amendment No.

+-.-.... -...,. -,.. -

• E Reporting Rcquirements 5.6 i

5.6 Reporting Requirements 5.6.S Core Operatino limits Report (COLR)

(continued) 4.

LC0 3.3.1.1, RPS Instrumentation (SR 3.3.1.1.14):

b.

The analytical methods used to determine the core operating limits shall be those 3reviously reviewed and approved by the NRC in NEDE-24011-)-A, General Electric Standard Application for Reactor Fuel.

(The approved revision at the time reload analyses are performed shall be identified in the COLR.)*

l c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revis, ions or supplements, f

shall be provided upon issuance for each reload cycle to the

NRC, 5.6.6 Special Reoorts Special Reports shall be submitted in accordance with 10 CFR 50.4 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.

• For Cycle 7, as approved in the NRC Safety Evaluation Report dated PERRY - UNIT 1 5.0-18 Amendment No. 69