ML20065E547

Proposed Tech Specs Re Containment Airlock Interlock Mechanism

ML20065E547
Person / Time
Site:	Perry
Issue date:	09/19/1990
From:	CENTERIOR ENERGY
To:
Shared Package
ML20065E523	List: ML20065E547 PY-CEI-NRR-1217, Application for Amend to License NPF-58,adding Action Statement to Address Inoperable Containment Airlocks Interlock Mechanism in Tech Spec 3.6.1.3
References
NUDOCS 9010020213
Download: ML20065E547 (4)

Text

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4 Attachm2nt 2 PY-CEI/NRR-1217 L Page i of 4 CONTA! WENT SYSTEMS )

PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION

3. 6.1. 3 Each primary containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal f transit entry and exit through the containment, then at least one air i lock door shall be closed, and

b. An overall air lock leakage rate of less than or equal to 2.5 scf per hour at P,, 11.31 psig. i APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and f.

ACTION:  !

a. With one primary containment air lock door in one or both air locks ,

inoperable:

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1. Neintain at least the OPERABLE air lock door closed

• and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the 'next required  !

overall air lock leakage test provided that the OPERABLE air lock  :

door is verified to be locked closed" at least once per 31 days. '

3. Otherwise, be in at least HOT SWTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in CCLD SHUTDOWN wit'.in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..

4 4. Otherwise, in OPERATIONAL CONDITION f, suspend all operation i involving handling of irradiated fuel in the primary containment, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel, 7;.'l . m g j

• - s of Specification 3.0.4 are not applicable.

! I o me.cA % sm c ontainment air lock inoperable in OPERATIONAL CONDITIONS 1.,

2e er 3, except as a result of an inoperable air lock doo maintain at least one air lock door closed; restore the inoperable air lock to 0PER-ABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HDT SHUTDOWN within the , %g next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  % gsm e A. With a primary containment air lock inoperable.(i,n OPERATIONAL CONDITIO f, a j except as a result of an inoperable air lock doch maintain at least one ]

air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or suspend all operations involving handling of irradiated fuel in the primary containment, CORE ALTERATION $, and operations with a potential for draining the reactor vessel.

t fWhen handling irradiated fuel in the primary containment, during CORE ALTERATIONS. and operations with ntial for drainino the reactor vessel, sea, pt t duri M M to r exceed '. ur per y ir an i ab e inn Mor tiv ime

[ P RRY - UNIT 1 ~ 3/4 6-6 9010020213 900919 PDR ADDCK 05000440, P PNUl

Atttchment 2 PY-CEI/NRR-1217 L Page 2 of 4 Insert A

b. With the interlock mechanism in one or both containment air locks inoperable, for the affected air lock (s):

1. Maintain at least one OPERABLE airlock door closed **, and either restore the inoperable interlock mechanism to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock one OPERABLE airlock door closed.

2. Operation may then continue proyjded that one OPERABLE airlock door is verified to be locked closed at least once per 31 days.

Insert B

• Limited use of the OPERABLE air lock door is permitted for a cumulative time not to exceed I hour per year, for repair of the inoperable door, personnel safety, and required operational / maintenance / surveillance activities necessary to ensure safe plant operations.

Insert C

• • Use of the airlock is permitted without having an OPERABLE door locked, provided an individual is stationed at the airlock dedicated to assuring that at least one OPERABLE airlock door remains closed at all times.

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. *; Attcchment 2 '

PY-CEI/NRR-1217 L  ;

Page 3 of 4 1 l

CONTAINMENT SYSTEMS l

BASES l

3/4.6.1 CONTAINMENT (Continued) 3/4. 6.1. 2 CONTAINMENT LEAKAGE (Continued)

The surveillance testing for measuring laakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of exemptions granted for testing the airlocks af ter each opening.

3/4.6.1.3 CONTAINMENT AIR LOCKS  ;

The limitations on closure and leak rate for the containment air locks j are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and <

the containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2. i The specification makes allowances for the fact that there may be long periods l of time when the air locks will be in a closed and secured position during l reactor operation. Only one closed door in each air lock is r uire to ain-tain the integrity of the containment.

• pg The air supply to the containment air lock and seal system is the service J and instrument air system. The system consists of two 100% capacity air '

compressors per unit and can be cross-connected. This system is redundant and extremely reliable and provides system pressure indication in the control room. '

3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance for the main steam line isolation valves in the postulated LOCA situations would be '

a small fraction of the 10 CFR 100 guidelines, provided the main steam line system from the isolation valves up to and including the turbine condenser

, remains intact. Operating experience has indicated that degradedon has I

occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.

The requirement for the leakage control system will reduce the untreated leakage from the MSIV's when isolation of the primary system and containment l -is required.

3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural. integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the contairunent l will withstand the maximum pressure of 15 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.

l PERRY - UNIT I B 3/4 6-2 Amendment No. 19 l

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!~ Att chment 2 PY-CE1/NRR-1217 L Page 4 of 4 ,

Insert D An allovance has been provided for access into or through the containment air locks when one air lock door in one or both air locks is inoperable for a cumulative period not to exceed one hour per year for each air lock. Use of the allowance provides for access through an OPERABLE air lock door for the following types of activities: repair of the inoperable doort personnel safety; and required operational / maintenance / surveillance activities necessary to ensure safe plant operations.

An allowance has also been provided for access into or through the containment airlocks when an interlock mechanism in one or both airlocks is inoperable.

When the interlock mechanism is inoperable, use of the airlock is permitted without having to lock one of the doors provided that an individual is stationed at the airlock, dedicated to assuring that at least one OPERABLE i airlock door remains closed at all times. This allowance is provided l primarily for personnel safety reasons, since locked doors vould at times compromise personnel safety because they may not be able to exit the '

containment during an accident, or other personnel may not be able to enter containment to aid injured workers, depending on which side of the door the lock was placed on.

NJC/ GARY /3750 f

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