Text

Amends 158 & 129 to Licenses NPF-14 & NPF-22,revising TSs to Establish & Ref Primary Containment Leak Rate Testing Program in Order to Implement Requirements of 10CFR50,App J, Option B
	ML17158B717
Person / Time
Site:	Susquehanna
Issue date:	07/02/1996
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Pennsylvania Power & Light Co, Allegheny Electric Cooperative
Shared Package
ML17158B718	List: ML17158B717; ML17158B719;
References
	NPF-14-A-158, NPF-22-A-129 NUDOCS 9607120207
	Download: ML17158B717 (48)
	v • d • e

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+0*44 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 205f$4001 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.

DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

~ 58 License No. NPF-14 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for'the amendment filed by the Pennsylvania Power Light Company, dated February 12,

1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I'.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance:

(i) 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 Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.

9607l20207 960702 PDR ADOCK OS000387 PDR1

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

1 58 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PP8L shall operate the facility in accordance with. the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance. July 2, 1996

~ John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO FACILITY OPERATING LICE S E NO.

NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

~REMOV 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-8 3/4 6-11 8 3/4 6-1 8 3/4 6-2 INSERT 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-8 3/4 6-11 B 3/4 6-1 8 3/4 6-2

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LIMITINGCONDITION FOR OPERATION 3.6.1

~ 1 PRIMARY CONTAINMENTINTEGRITY shall be maintained.

OPERATIONAL CONDITIONS 1, 2" and 3.

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Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENTINTEGRITY shall be demonstrated:

a.

After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by teak rate testing in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

b. At least once per 31 days by verifying that all primary containment penetrations""

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 automatic valves secured in

position, except as provided in Table 3.6.3-1 of Specification 3.6.3.

c.

By verifying each primary containment air lock OPERABLE per Specification 3.6.1.3.

d.

By verifying the suppression chamber OPERABLE per Specification 3.6.2.1.

See Special Test Exception 3.10.1 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 each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once per 92 days.

SUSQUEHANNA -'UNIT 1 n

3/4 6-1 Amendment No.

158

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LIMITINGCONDITION FOR OPERATION

'.6.1.2" Primary containment leakage rates shall be limited to:

a.

An overall integrated leakage rate (Type A test) in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

b.

A combined leakage rate in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves', main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests.

¹c. 'Less than or equal to 100 scf per hour for any one main steam isolation valve and a combined maximum pathway leakage rate of 5 300 scf per hour for all four main steam lines through the isolation valves when tested at P22.5 psig.

d.

"Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tested in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

e.

A combined leakage rate of less than or equal to 3.3 gpm for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 P~.

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When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1

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With:

a.

The measured overall integrated primary containment leakage rate (Type A test) not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, or b.

The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves", main steam line drain valves" and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, or

¹c. The measured leakage rate exceeding 100 scf per hour for any one main steam isolation valve or a total maximum pathway leakage rate of ) 300 scf per hour for all four main steam lines through the isolation valves, or d.

The measured leak rate exceeding 1.2 scf per hour for any one main steam line drain valve, or e.

The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 3.3 gpm, Exemption to Appendix "J" of 10 CFR 50.

¹ Deletion of the MSIV Leakage Control System was approved in Amendment No. 151 and implemented during the U1 9RIO.

SUSQUEHANNA - UNIT 1 3/4 6-2 Amendment No.

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~ f LIMITINGCONDITION FOR OPERATION (Continued)

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~Ilgwu. (Continued) restore:

a.

The overall integrated leakage rate (Type A test) to be in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, and b.

The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves", main steam line drain valves" and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests to be in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program; and

¹c. The leakage rate to less than or equal to 11.5 scf per hour for any main I

steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage rate to 5 300 scf per hour for all four main steam lines through the isolation valves, and d.

The leakage rate to less than or equal to 1.2 scf per hour for any one main steam line drain valve, and

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e, The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or, equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated in accordance with Specification 6.8.5, Primary Containment Leakage Rate

Testing, Program, for the following:

a.

Type A Test b.

Type B and C Tests (including air locks and purge supply and exhaust isolation valves) c.

Air Locks d.

Main Steam Line Isolation Valves e.

Hydrostatically Tested Containment Isolation Valves f.

Purge Supply and Exhaust Isolation Valves

¹ Deletion of the MSIV Leakage Control System was approved in Amendment No. 151 and implemented during the U1 9 RIO.

SUSQUEHANNA - UNIT 1 3/463 Amendment No. fgJ, f$f, 158

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SURVEILLANCEREQUIREMENTS (Continued)

THE SURVEILLANCEREQUIREMENTS PREVIOUSLY ON THIS PAGE HAVE BEEN DELETED SUSQUEHANNA - UNIT 1 3/4 6-4 Amendment No.

95, 158

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LIMITINGCONDITION FOR OPERATION 3.6.1.3Each 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 in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

OPERATIONAL CONDITIONS 1, 2" and 3.

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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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months o'

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 ,

b. With the primary containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; 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.

SUSQUEHANNA - UNIT 1 3/4 65 Amendment No.

78, 158

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SURVEILLANCE REQUIREMENTS 4.6.1,3 Each primary containment air lock shall be demonstrated OPERABLE:

a.

By verifying seal leakage rate is in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

, b.

By conducting an overall air lock leakage test in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.""

"" Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested upon initial entry after the primary containment has been de-inerted.

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

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LIMITINGCONDITION FOR OPERATION 3.6.1.5 The structural integrity of'the primary containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.

OPERATIONAL CONDITIONS 1, 2 and 3.

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'With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces or the primary containment, including the liner plate, shall be visually inspected in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

4.6.1.5.2 Qg~ Any abnormal degradation of the primary containment structure detected during the required inspection shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days.

This report shall include a description of the condition of the concrete, the inspection procedure, the tolerances on, cracking, and the corrective actions taken.

SUSQUEHANNA - UNIT 1 3/4 6 8 Amendment No.

g5, 158

L'IlUIITINGCONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation for up to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months each 365 days with the supply and exhaust, isolation valves in one supply line and one exhaust line open for inerting, deinerting or pressure control."

OPERATIONAL CONDITIONS I, 2 and 3.

a.

With a drywell and/or suppression chamber purge supply and/or exhaust isolation valve open, except as permitted above, close the valve(s) within four hours 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 .

b. With a containment purge supply and/or exhaust isolation valve(s) with resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.8.2, restore the inoperable valve(s) 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 .

SURVEILI ANCE REQUIREMENTS 4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust butterfly isolation valves shall be verified not to have been open for more than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months in the previous 365 days. "

f 4.6.1.8.2 Each 18 inch and 24 inch drywell and suppression chamber purge supply and exhaust with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, at least once per 6 months.

Valves open for pressure control are not subject to the 90 hour0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 day limit provided the 2-inch bypass line is being utilized.

SUSQUEHANNA - UNIT 1 3/4 6-11 Amendment No.

gg, 158

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BASES 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.

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 design basis LOCA maximum peak containment pressure of 45.0

psig, P,.

As an added conservatism, the measured overall integrated leakage rate (Type A test) is further limited to less than or equal to 0.75 L, during performance of the periodic tests to account for possible'egradation of the containment leakage barriers between leakage tests.

Operating experience with main steam line isolation valves and main steam line drain valves

'as indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

The frequency for performing the Type A tests is consistent with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

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

¹ Deletion of the MSIV Leakage Control System was approved in Amendment No. 151 and implemented during the U1 9 RIO.

SUSQUEHANNA - UNIT 1 B 3/4 6-1 Amendnent No.

/gal, SSg, 158

BASES 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 containment will withstand the

. maximum pressure of 45.0 psig in the event of a LOCA. A visual inspection in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, is sufficient to demonstrate this capability.

The limitations on drywell and suppression in chamber internal pressure ensure that the containment peak pressure of 45.0 psig does not exceed the design pressure of 53 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 5 psid. The limit of 2.0 psig for initial positive containment pressure will limit the total pressure to 45.0 psig which is less than the design pressure and is consistent with the safety analysis.

The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340 F during LOCA conditions and is consistent with the safety analysis.

The drywell and.suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control. Until these valves have been demonstrated capable of closing during a LOCA or steam line break accident, they shall be blocked so as not to open more than 50'. Until these valves have been demonstrated capable of closing within the'times assumed!n the safety analysis, they shall not be open more than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months in any consecutive 365 days.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.

The 0.60 La leakage limit shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

SUSQUEHANNA - UNIT 1 B 3' 2

Amendment.No.

g9, 158

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ADMINISTRATIVECONTROLS (Continued) 6.8.5 A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by.10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program", dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P is 45.0 psig.

The maximum allowable primary containment leakage rate, Lat Pshall be 1% of the primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

a.

Primary Containment leakage rate acceptance criterion is 5 1.0 L,.

During each unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 L, for Type B and Type C tests and s'0.75 L, for Type A tests; b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is ~ 0.05 L, when tested at t P 2)

For each door, leakage rate is ~ 5 scfh when pressurized to 2 10 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provision of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

SUSQUEHANNA - UNIT 1 6-16a amendment No.

158

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/yn UNITED STATES N c'LEAR REGULATORY COMMIS WASHINGTON> D.C. %555-0001 PENNSYLVANIA POWER 5 LIGHT COMPANY LLEGHENY ELECTRIC COOPERATI NC.

DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No. NPF-22 The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power h

Light Company, dated February 12,

1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is. reasonable assurance:

(i) 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 Commission's regulations set,forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been. satisfied.

2.

3.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 129 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PPLL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 2, 1996

~John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

0 ATT CHMENT TO LICENSE AMEND ENT NO-12 FACILITY OPERATING LICE SE NO. NPF-22 OCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-8 3/4 6-11 B 3/4 6-1 B 3/4 6-2 INSERT 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-8 3/4 6-11 B 3/4 6-1 B 3/4 6-2

LIMITINGCONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENTINTEGRITY shall be maintained.

OPERATIONAL CONDITIONS 1, 2" and 3.

hGXJQH Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENTINTEGRITY shall be demonstrated:

a.

After each closing of each penetration subject to Type 8 testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program".

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b. At least once'er 31 days by verifying that all primary containment penetrations""

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 automatic valves secured in position, except as provided in Table 3.6.3-1 of Specification 3.6.3.

c.

By verifying each primary containment air lock OPERABLE per Specification 3.6.1.3.

d.

By verifying the suppression chamber OPERABLE per Specification 3.6.2.1, See'Special Test Exception 3.10.1 Except

valves, blind flanges, and deactivated automatic valves which are located inside the containment, and are locked, sealed or otherwise secured in the close'd position.

These penetrations shall be yerified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once per 92 days.

SUSQUEHANNA - UNIT 2 3/4 6-1 Amendment No. 129

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.LIMITINGCONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a.

An overall integrated leakage rate (Type A test) in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

b.

A combined leakage rate in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves',

main steam line drain valves" and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests.

I c.

Less than or equal to 100 scf per hour for any one main steam isolation valve and a combined maximum pathway leakage rate of 5 300 scf per hour for all four main steam lines through the isolation valves when tested at P22.5 psig.

d.

Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tested in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

e.

A combined leakage rate of less than or equal to 3.3 gpm for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 P,.

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When PRIMARY CONTAINMENTINTEGRITYis required per Specification 3.6.1.1.

With:

a.

The measured overall integrated primary containment leakage rate IType A test) not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, or b.

The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, or c.

The measured leakage rate exceeding 100 scf per hour for any one main steam isolation valve or a total maximum pathway leakage rate of > 300 scf per hour for all four main steam lines through the isolation valves, or d.

The measured leak rate exceeding 1.2 scf per hour for any one main steam line drain valve, or e.

The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 3.3

gpm, Exemption to Appendix "J" of 10 CFR 50.

SUSQUEHANNA - UNIT 2 3/4 6-2 Amendment No. TD, 129

a

LIMITINGCONDITION FOR OPERATION (Continued) aQIlM (Continued) restore:

a.

The overall integrated leakage rate (Type A test) to be in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, and b.

The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves", main steam line drain valves" and valves which are hydrostaticaily leak tested per Table 3.6.3-1, subject to Type B and C tests to be in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, and c.

The leakage rate to less than or equal to 11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage rate to 5300 scf per hour for all four main steam lines through the isolation valves, and d.

The leakage rate to less than or equal to 1.2 scf per hour for any one main steam line drain valve, and e.

The combined leakage rate for all containment isolation valves in hydrostaticaily tested lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200'F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, for the following:

a.

Type A Test b.

Type B and C Tests (including air locks and purge supply and exhaust isolation valve) c.

Air Locks d.

Main Steam Line Isolation Valves e.

Kydrostatically Tested Containment Isolation Valves f.

Purge Supply and Exhaust Isolation Valves SUSQUEHANNA - UNIT 2 3/4 6-3 Amendment No. 89, Elf, 129

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CONTAINMENTSYSTEMS SURVEILLANCEREQUIREMENTS (Continued)

THE SURVEILLANCEREQUIREMENTS PREVIOUSLY ON THIS PAGE HAVE BEEN DELETED SUSQUEHANNA - UNIT 2 3/4 6-4 Amendment No. 129

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iv LIMITINGCONDITION 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 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 in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

OPERATIONAL CONDITIONS 1, 2" and 3.

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 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 .

b. With the primary containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; 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'pecial Test Exception 3.10.1.

SUSQUEHANNA - UNIT 2 3/4 6-5 Amendment No. 49, 129

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SURVEILLANCEREQUIREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:

a.

By verifying seal leakage rate is in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

b.

By conducting an overall air lock leakage test in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.""

"" Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested upon initial entry after the primary containment has been deinerted.

SUSQUEHANNA - UNIT 2 3/4 6-6 Anendment Ko. 129

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.PJ3lbMBY CDHTAl55IK LIMITINGCONDITION FOR OPERATION 3.6.1.5 The structural integrity of the primary containment shall be maintained at a

" level consistent with the acceptance criteria in Specification 4.6.1.5 l

l With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment, including the liner plate, shall be visually inspected in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program 4.6.1.5.2 Edgar~

Any abnormal degradation of the primary containment structure detected during the required inspection shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days.

This report shall include a description of the condition of the concrete, the inspection procedure, the tolerances on

cracking, and the corrective actions taken.

SUSQUEHANNA - UNIT 2 3/4 6-8 Amendment No. 129

LIMITINGCONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation for up to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months each 365 days with the supply and exhaust isolation valves in one supply line and one exhaust line open for inerting, deinerting

,or pressure control."

Y: OPERATIONAL CONDITIONS 1, 2, and 3.

hGIJQH:

a.

With a

drywell and/or suppression chamber purge supply and/or exhaust isolation valve open, except as permitted

above, close the valve(s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 .

b.

With a containment purge supply and/or exhaust isolation valve(s) with resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.8.2, restore the inoperable valve(s) 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust butterfly isolation valves shall be verified not to have been open for more than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months in the previous 365 days. "

4.6.1.8.2 Each 18-inch and 24-inch drywell and suppression chamber purge supply and exhaust with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program at least once per 6 months.

Valves open for pressure control are not subject to the 90 hour0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 day limit provided the 2-inch bypass line is being utilized.

SUSQUEHANNA - UNIT 2 3/4 6-11 Amendment No. 129

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BASES PRIMARY CONTAINMENTINTEGRITY 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.

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 design basis LOCA maximum peak containment pressure of 45.0

psig, P,.

As an added conservatism, the measured overall integrated leakage rate (Type A test) is further limited to less than or equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

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

The surveillance testing for measuring leakage rates is consistent with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

The frequency for performing the Type A tests is consistent with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

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The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and Specification 6.8.5, Primary Containment Leakage Rate Testing Program.

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

SUSQUEHANNA - UNIT 2 B 3/4 6-1 Amendment No. g9, 'f2', 129

BASES 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 containment will withstand the maximum pressure of 45.0 psig in the event of a LOCA. A visual inspection in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing

Program, is sufficient to demonstrate this capability...

The limitations on drywall and suppression in chamber internal pressure ensure that the containment peak pressure of 45.0 psig does not exceed the design pressure of 53 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 5 psid. The limit of 2.0'psig for initial positive containment pressure will limit the total pressure to 45.0 psig which is less than the design pressure and is consistent with the safety analysis.

The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340'F during LOCA conditions and is consistent with the safety analysis.

The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting and pressure control. The 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 day limit on purge valve operation is imposed to protect the integrity of the SGTS filters. Analysis indicates that should a LOCA occur while this pathway is being utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS. This limit is not imposed, however, on the subject valves when pressure control is being'performed through the 2-inch bypass

line, since a

pressure surge through this line does not threaten the OPERABILITYof SGTS.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.

The 0.60 L, leakage limit shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

SUSQUEHANNA - UNIT 2 B 3/4 6-2 Anendment No. 129

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4 (Continued) 6.8.5 A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program", dated September 1995

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I The peak calculated containment internal pressure for the design basis loss of coolant accident, P is 45.0 psig.

The maximum allowable primary containment leakage rate, Lat Pshall be 1% of the primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

a.

Primary Containment leakage rate acceptance criterion is 5 1.0 L,.

During each unit startup following testing in accordance with this program, the leakage rate acceptance criteria are ~ 0.60 L, for Type B and Type C tests and s 0.75 L, for Type A tests;

b. Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is 5 0.05 L, when tested at 2 P 2)

For each door, leakage rate is 5 5 scfh when pressurized to c 10 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provision of Specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

SUSQUEHANNA - UNIT 2 6-16a Amendment No. 129

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ML17158B717

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