ML20134D017

Corrected Page 3/4 6-2,re Containment Leakage Limiting Condition for Operation,To Amend 98 to License DPR-53

ML20134D017
Person / Time
Site:	Calvert Cliffs
Issue date:	07/31/1985
From:	NRC
To:
Shared Package
ML20134D006	List: ML20134D003 ML20134D009 ML20134D017 ML20134D021 ML20134D026
References
NUDOCS 8508190022
Download: ML20134D017 (2)

Text

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of:

l.

1La (346,000 SCCM), 0.20 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 50 psig, or i

a 2.

1Lt (61,600 SCCM), 0.058 percent by weight of the containment i

air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P, 25 psig.

t b.

A combined leakage rate of 1 0.60 L (207,600 SCCM), for all penetra-tions and valves subject to Type B $nd C tests when pressurized to P.

3 APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

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With either (a) the measured overall integrated containment leakage rate or (b) with the Mea (259,500sured combined leakage fate for all penetrations and exceeding 0.75 L SCCM) or 0.75 L (46,200 SCCM), as applicable, sub.iect to Types B and C tests exceeding 0.60 L, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the follow-ing test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50* using the methods and provisions l

of ANSI N45.4 - 1972:

Three Type A tests (overall Integrated Containment Leakage Rate) a.

shall be conducted at 40 + 10 month intervals during shutdown at either Pa (50 psig) or at7t (25 psig) during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.*

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• The third test of the first 10-year service pericd shall be conducted during spring 1985 Unit 1 refueling outage.

CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendmen.t.No. 75, 98 ggBi g g g % 317 PDR p

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3/4.6 CONTAINMENT SYSTEMS i

3/4. 6.1 PRIMARY CONTAINMENT j

CONTAINMENT INTEGRITY LIMITING CONDITION FOR OEPRATION i

I

3. 6.1.1 Primary CONTAINt1ENT INTEGRITY shall be maintained.

1 APPLICABILITY: MODES 1, 2, 3 and 4.

j.

i ACTION:

j Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS i

4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

At least once per 31 days by verifying that all penetrations

• a.

not capable of being closed by OPERABLE containment automatic isolation valves and. required to be closed during accident conditions are closed by valves, blind flanges, or deactivated i

automatic valves secured in their positions, except as provided i

in Table 3.6-1 of Specification 3.6.4.1.

I j

b.

By verifying that each containment air lock is OPERABLE per j

Specification 3.6.1.3.

i By verifying that' 5e $quipment hatch is closed and sealed, c.

j prior to entering liode 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per Appendix J to i

10 CFR Part 50.

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• Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.

These penetrations shall be verified closed during i

each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

CALVERT CLIFFS - UNIT.1 3/4 6-1 Amendment No. 8 3

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