ML20211A230

Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR

ML20211A230
Person / Time
Site:	Hatch
Issue date:	09/19/1997
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20211A228	List: HL-5481, Forwards Revised TS Page Containing Footnote & mark-up of Affected Page Re SLMCPR ML20211A230
References
NUDOCS 9709240173
Download: ML20211A230 (3)

Text

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t ENCLOSURE Edwin 1. Hatch Nuclear Plant - Unit 1 Request to Revise Technical Specifications:

Safety Limit Minimum Critical Power Ratios (SLMCPR) i Revised Technical Specifications page 2.0-1 and the corresponding marked-up page, I

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2.0 2.01 SAFETY LIMITS _(SLs) 2.l 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:

THERMALL POWER shall-be ss 25% RTP.

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

1 MCPR shall be a 1.10 for two recirculation loop operation or a: 1.12 for-single recirculation loop operation.*

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

2.1.2 Reactor Coolant System 1RCS) Pressure SL i

Reactor steam dome pressure shall. be 5; 1325 psig, o

The specified limits are for Cycle 18 only.

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

2.2.1 Within I hour, notify the NRC _0perations Center, in accordance with-10 CFR 50.72, 1

i 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,.the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.

(continued)

HATCH UNIT _1 2.0-1 MCPR

a 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 dome pressure < 785 psig or core

-flow < 10% rated core flow:

THERMAL POWER shal; be s 25% RTP, 2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow a 10% rated co flow:

f. IO MCPR JLall be m 4,47 for two recirculation loop operation or a for s ng e recirculation loop operation.

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

2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig.

N ne specif.ect hmits aree fog Cyc le I 6 on ly *

'2.2 SL Violations 2

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, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.

(continued)

HATCH UNIT 1 2.0-1

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