ML20245B943

Proposed Tech Spec Limiting Conditions for Operation & Surveillance Requirements for Primary Containment Air Locks

ML20245B943
Person / Time
Site:	Brunswick
Issue date:	04/17/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20245B823	List: ML20245B822 ML20245B943
References
NUDOCS 8904260395
Download: ML20245B943 (6)

Text

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. CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 The primary containment air lock shall be OPERABLE with:

.a.

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

An overall air lock leakage rate of less than or equal to 0.05 L, at P, 49 psig.

3 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

a.

With one primary containment air lock door inoperable:

1.

Maintain 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 SHUTDOWN 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 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 />.

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the primary containment air lock door interlock inoperable:

1.

Lock the inner air lock door closed.

L 2.

Operation may then continue provided that the inner air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT SHUTDOWN 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 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 />.

b..

)(3 4.

The provisions of Specification 3.0.4 are not applicable.

baz "b'

e c.

With the primary containment air lock inoperable, except as a result of an

-@d@

inoperable air lock door or interlock, maintain at least one air lock door Eho 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 or be in at least HOT SHUTDOWN 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 COLD

$8 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

oc 4<

rde gyg

• See Special Test Exception 3.10.1.

m n.n.

BRUNSWICK - UNIT 1 3/4 6-4 Amendment No.

b CONTAINMENT SYSTEMS I

SURVEILLANCE REQUIREMENTS I

4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:

a.

By verifying the seal leakage rate to be less than or equal to 5 sef

~

per hour when the gap between the door seals is pressurized to

]

10 psig*:

1 1

1.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 i

hours, and 2.

Prior to establishing PRIMARY CONTAINMENT INTECRITY when the air lock has been used and no maintenance has been performed-on the air lock, and 3.

When the air lock seal has been replaced.

b.

By conducting an overall air lock leakage test at P, 49 psig, and by verifying that the overall air lock leakage is with,in its limit:

1.

At least once per six months #, and 2.

Prior to establishing PRIMARY CONTAINMENT INTECRITY when maintenance (except for seal replacement) has been performed on the air lock that would affect the air lock sealing capability.*

c.

By verification of air lock interlock OPERABILITY:

1.

Prior to establishing PRIMARY CONTAINMENT INTECRITY when the air lock has been used, and 2.

Prior to and following a drywell entry when PRIMARY CONTAINMENT INTEGRITY is required, and 3.

Following the performance of maintenance affecting the air lock

[

interlock.

Exemption to Appendix J of 10 CFR 50.

The provisions of Specification 4.0.2 are not applicable.

BRUNSWICK - UNIT 1 3/4 6-5 Amendment No.

D l-k I

3/4.6 CONTAINMENT SYSTEMS l

1 BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAINMENT INTECRITY Primary CONTAINMENT INTEGRITY ensures that the release of

)

radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage : ate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 49 psig, P. As an added conservatism, the measured overall integrated leakage rate is,further limited to less than or equal to 0.75 L, or 0.75 L, as applicable, during performance of the periodic tests to account for possible degradation of the containment j

leakage barriers between leakage tects.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore, the special requirement for testing these valves.

Exemptions from the requirements of 10 CFR Part 50 have been granted for main steam isolation valve leak testing, testing of airlocks after each opening, and leakage calculation methods.

Appendix J, paragraph III.A.3 requires that all Type A'(Containment Integrated Leak Rate) tests be gerformed in accordance with ANSI N45.4-1972,

" Leakage Rate Testing of Containment Structures for Nuclear Reactors."

ANSI N45.4-1972 requires that leakage calculations be performed using the j

Point-to-Point or Total Time method. ANSI N45.4-1972 has been revised to a j

new standard, ANSI /ANS 56.8-1981, " Containment System Leakage Testing," which incorporates the Mass-Point method for leakage calculations. Type A tests will be performed in conformance with ANSI N45.4-1972 but will use the

)

1 Mass-Point method for calculation of leakage rates as described in ANSI /ANS 56.8-1981.

3/4.6.1.3 PR[ MARY CONTAINMENT AIR LOCKS 1

Tha

.mitations on closure and leak rate for the containment air locks are > qs.trid to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY g ren in Specifications 3.6.1.1 and 3.6.1.2.

The specification and leak ran j

makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation.

Only one closed door in each air lock is required to maintain the integrity of the containment.

In the event of an inoperable door interlock, locking shut the inner door will ensure containment integrity while permitting access to i

the lock for maintenance and surveillance testing.

i BRUNSWICK - UNIT 1 B 3/4 6-1 Amendment No.

,4 7 CONTAINMENT SYSTEMS l

PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION

'3.6.1.3 The primary containment air lock shall be OPERABLE with:

a.

Both dcors closed except when tht air lock is' being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of less than or equal to 0.05 L, at P,, 49 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

a.

With one primary containment air lock door inoperable:

1.

Maintain 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 SHUTDOWN 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 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 />.

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the primary _ containment air lock door interlock inoperable:

1.

Lock the inner air lock door closed.

2.

Operation may then continue provided that the inner air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT SHUTDOWN 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 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 />.

4.

The provisions of Specification 3.0.4 are not applicable.

With the primary containment air lock inoperable, except as a result of an c.

inoperable air lock door or interlock, maintain at least one air lock door i

closedt 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 be in at least HOT SHUTDOWN 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 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 />.

• See Special Test Exception 3.10.1.

BRUNSWICK - UNIT 2 3/4 6-4 Amendment No.

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 EachprimarycontainmentairlockshallbedemonstratedOPERABLE:

.a.,

By verifying the seal leakage rate to be less than or equal to 5'sef-per hour when the gap between the door seals is pressurized to j

10 psig*:

1.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at lease once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and 2.

Prior to establishing PRIMARY CONTAINMENT INTECRITY when the air lock has been used and no maintenance has been performed on the air lock, and 3.

When the air lock seal has been replaced.

b.

By conducting an overall air lock leakage that at P, 49 psig, and by verifying that the overall air lock' leakage is with,in its limit:

I 1.

At least once per six months, and 2.

Prior to establishing PRIMARY CONTAINMENT INTEGRITY when maintenance :.lexcept for seal replacement) has been performed on the air lock that could affect the air lock sealing capability.*

By verification of air lock interlock OPERABILITY:

c.

1.

Prior to establishing PRIMARY CONTAINMENT INTECRITY when the air lock had been used, and 2.

Prior to and following a drywell entry when PRIHARY CONTAINMENT INTECRITY is required, and 3.

Following the performance of maintenance affecting the air lock I

interlock.

i Exempticn of Appendix J of 10 CFR 50.

I The provisions of Specification 4.0.2 are not applicable BRUNSWICK - UNIT 2 3/4 6-5 Amendment No.

_______-_-_-__-_-.____________--_____________-_-____--____-______-____-__-___1

.d 3/4.6 CONTAINMENT SYSTEMS

' BASES I

3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMA Y CONTAINMENT INTECRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the occident analyses at the peak accident pressure of 49 psig, P,further limited As an added conservatism, the measured overall integrated leakage rate is to less than or equal to 0.75 L, or 0.75 L, as applicable, during performance t

of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore, the special requirement for testing these valves.

Exemptions from the requirements of 10 CFR Part 50 have been granted for main steam isolation valve leak testing, testing of airlocks after each opening, and leakage calculation methods.

Appendix J, paragraph III.A.3 requires that all Typa A (Containment Integrated Leak Rate) tests be performed in accordance with ANSI N45.4-1972,

" Leakage Rate Testing of Containment Structures for Nuclear Reactors."

ANSI N45.4-1972 requires that leakage calculations be performed using the Point-to-Point or Total Time method. ANSI N45.4-1972 has been revised to a new standard, ANSI /ANS 56.8-1981, " Containment System Leakage Testing," which incorporates the Mass-Point method for leakage calculations. Type A tests will be performed in conformance with ANSI N45.4-1972 but will use the Mass-Point method for calculation of leakage rates as described in ANSI /ANS 56.8-1981.

3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.

The specification makes allowances for the fact that there may be long perions of time when the air locks will be in a closed and secured position during reactor operation.

Only one closed door in each air lock is required to maintain the integrity of the containment. In the event of an inoperable door interlock, locking shut the inner door will ensure containment integrity while permitting access to the lock for maintenance and surveillance testing.

BRUNSWICK - UNIT 2 B 3/4 6-1 Amendment No.

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