ML20204E497

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Proposed Tech Specs,Correcting Typos Found in Table 3.3.6.1-1
ML20204E497
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 03/15/1999
From:
CENTERIOR ENERGY
To:
Shared Package
ML20204E491 List:
References
NUDOCS 9903250047
Download: ML20204E497 (1)


Text

m Primary Containment and Drywell Isolation Instrumentation PY-CEI/NRR-2373L 3.3.6.1 Page1of1

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Table 3.3.6.1 1 (page 6 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR PEFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIF SYSTEM ACTION C.1 REQUIREMENTS VALUE 5.

RHR System Isolation a.

RHR EqJIpment Area 2

,3 1 per area F

SR 3.3.6.1.1 s 159.9'F Anblent SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.7 b.

Reactor Vessel Water 1,2

,3 '

2 F

SR 3.3.6.1.1

= 177.1 l

8 Level Low, Level 3 SR 3.3.6.1.2 inches SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 2

,3

,4, 2

J SR 3.3.6.1.1

= 177.1 l

5 SR 3.3.6.1.2 incher SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 c.

Reactc Vessel Steam 1,2,3 2

F SR 3.3.6.1.1 s 15D psig Domo' sure - High SR 3J.6.1.2 33,fo.l.3 SR r3.c1.1 SR 3.6.

.4

~3 3 g, g 9 2' d g,,s V

8 3.

d.

Drywel. Pressure-High 1,2,3 SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3

'A9'; '

SR 3.3.6.1.4 SR 3.3.6.1.5

e. Manual Initiation 1,2,3 2

G SR 3.3.6.1.5 NA (e) With reactor vesset steam dome pressure iess than the RNR cut in permissive pressure.

(f) Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.

(a) With reactor vesset steam dome pressure greater than or equal to the RHR cut in permissive pressure.

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9903250047 990315 PDR ADOCK 03000440 P

PDR l

PERRY - UNIT 1 3.3-59 Amendment No. 85 1

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