Text

Amends 128 & 158 to Licenses DPR-71 & DPR-62,respectively, Changing Limiting Condition for Operation & Surveillance Requirements for Tech Spec 3/4.6.1.3
	ML20245K060
Person / Time
Site:	Brunswick
Issue date:	04/25/1989
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20245K064	List: ML20245K060; ML20245K084;
References
	NUDOCS 8905040316
	Download: ML20245K060 (11)
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NUCLEAR REGULATORY COMMISSION a'

l WASHING TON, D. C. 20555

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CAROLINA POWER & LIGHT COMPANY, et al.

DOCKET.NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 128 License No. DPR-71 1.

The. Nuclear Regulatory Comission (the Comission) has found-that:

1 l

A.

The application for amendment filed by Carolina Power & Light Company

-(the licensee), dated October 24, 1984, as supplemented February 27

- 1985,. July 8,1985 and March 17, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954,.as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility w'111 operate in conformity with the~ application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (t) that the activities authorized

'by this amendment can be conducted without endangering the health

.and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requiremerits have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical l

Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as fo11cws:

8905040316 890425 PDR ADOCK 0500 4

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. (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as re31 sed through Amendment No.128, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:

Elinor G. Adensam, Director Project Directorate Il-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 25,1989 l

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ATTACHMENT TO LICENSE AMENDMENT NO.128 1

FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Pages Insert Pages 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 B 3/4 6-1 B 3/4 6-1 i

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l CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS q

LIMITING CONDITION FOR OPERATION l

3.6.1.3 The primary containment air lock shall be OPERABLE with:

l 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.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

l With one primary containment air lock door inoperable:

a.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 SEUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 closedi restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See Special Test Exception 3.10.1.

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

128

j CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:

By verifying the seal leakage rate to be less than or equal to 5 scf a.

per hour when the gap between the door seals is pressurized to 10 psig*:

1.

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

Prior to establishing PRIMARY CONTAINMENT INTEGRITY when the air j

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,n.Its limit:

i 1.

At least once per six months #, and

2..

Prior to establishing PRIMARY CONTAINMENT INTEGRITY when maintenance (except for seat 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 CONTAI"HENT INTEGRITY 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.

I The provisions of Specification 4.0.2 are not applicable.

BRUNSWICK - UNIT 1 3/4 6-5 Amendment No. 128

l 3 /4'. 6 CONTAINMENT SY11gMS i

BASES l

2 3/4.6.1 PRIMARY CONTAINMENT q

3/4.6.1.1 PRIMARY CONTAINMENT INTECRITY Primary CONTAINMENT INTECRITY ensures that the release of radioactive materials free the containment atmosphere will be restricted to i

those leakage paths and associated leak rates assumed in the accident l

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 LEAKACE The limitations on primary containment leakage rates easure that the total containment leakage volume vill 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 e

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 isolatico 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 performed in accordance with ANSI N45.4-1972,

" Leakage Race 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 56.8-1981e " 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 races 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 race given in Specifications 3.6.1.1 and 3.6.1.2.

The specification 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 the lock for maintenance and surveillance testing.

BRUNSWICK - UNIT 1 8 3/4 6-1 Amendment No. D. IM. 128

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L (2)~TechnicalSpecifications

The Technical Specifications contained in. Appendices A and B, as revi. sed through Amendment No.158, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility

.in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR-REGULATORY COMMISSION Original Signed By:

Elinor G. Adensam, Director Project Directorate II_1-Division of Reactor Projects I/II Office.of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

. Specifications

- Date of Issuance:

April 25,1989

SEE PREVIOUS CONCURRENCE OFC :LA:PD21 :DRPR*PM:PD21:DRPR*

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j NAME : PAnderson :ETourigny:bd: SHLewis

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j DATE :03/21/89-

03/20/89

03/30/89

04/1V89 y

0FFICIAL RECORD COPY

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ATTACHMENT TO LICENSE AMENDMENT NO.158 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Pages Insert Pages 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 8 3/4 6-1 B 3/4 6-1 I

l 1

4 1

l' j-CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITINC CONDITION FOR OPERATION 3.6.1.3 The primary containment air lock shall be OPERABLE withs i

Both doors closed except when the air lock is being used for normal a.

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:

With one primary containment air lock door inoperable:

a.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the primary containment air lock door interlock inoperable:

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4 The provisions of Specification 3.0.4 src net applicable.

c.

With the primary containment air lock inoperabl, except as a result of an inoperable air lock door or interlock, maintain at least one air lock door closedi restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See Special Test Exception 3.10.1.

BRUNSWICK - UNIT 2 3/4 6-4 Amendment No. 158

1 lC 2.

~

i CONTAINMENT SYSTEMS i

I SURVEILLANCE REQUIREMENTS i

4.6.1.3 Each primary contairunent air lock shall be demonstrated OPERABLE:

By verifying the seal leakage rate to ne less chan or equal to 5 sef I

a.

per hour when the gap-between the door seals is pressurized to 10 psig*:

j l

1.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each closing, except when the air lock j

'is being used for multiple entries, then at lease once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and

?

h 2.

Prior to establishing PRIMARY CONTAINMENT INTEGRITY when the air lock has been used and no maintenance has been performed on the air lock, and y

3.

When the air lock seal has been replaced.

b.

By conducting an overall air icek leakage that at P, 49 psis, and by.

j verifying that the overall air lock leakage is with,in its linic j

i 1

1.

At least once per six months #, and 2.

Prior to establishing PRIMARY' CONTAINMENT INTECRITY when j

maintenance (except for seal replacement) has been performed on.

I the air lock that could affect the air lock naaling 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 dryvell entry when PRIMARY CONTAINMENT INTEGRITY is required, and i

3.

Following the performance of maintenance affecting the air lock interlock.

I l

Exemption of Appendix J of 10 CFR $0.

The provisions of Specification 4.0.2 are not applicable BRUNSW!CK - UNIT 2 3/4 6-5 Amendment No. 158

1 3/4.6 'CONTAIW(ENT SYSTEMS BASES 3

3/4.6.1 PRIMARY CONTAINMENT l

3/4.6.1.1 PRIMARY CONTAINMENT INTECRITY i-Primary CONTAINMENT INTECRITY 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 accident 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 e

of the periodic tests to account for possible degradation of the containment leakage barriers he: ween 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 IIIcA.3 requires that all Type 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 M45.4-1972,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 INTECRITY.

end 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 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 the lock for maintenance and surveillance testing.

BRUNSWICK - UNIT 2 8 3/4 6-1 Amendment No. 77, 76, 158

ML20245K060

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