Text

Amends 110 & 95 to Licenses NPF-11 & NPF-18,respectively, Revising TSs to Incorporate 10CFR50,App J, Primary Containment Leakage Testing for Water-Cooled Power Reactors, Option B
	ML20101B818
Person / Time
Site:	LaSalle
Issue date:	03/11/1996
From:	Lynch M; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20101B820	List: ML20101B818; ML20101B830;
References
	NUDOCS 9603150073
	Download: ML20101B818 (26)
	v • d • e

p UNITED STATE 8 g

g NUCLEAR REllULATORY COMMISSION e

WASHINITCN, D.C. 300s6 e001 COPMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. NPF-11 1.

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

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated November 14, 1995, as supplemented January 4, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provicions of the Act, and the regulations of the Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.

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

E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:

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PDR

(2)

Technical Soecifications and Environmental protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.110, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Prctecticn Plan.

1 3.

This amendment is effective.upon the date of issuance and shall be implemented no later than Ju'ne 30, 1996.

FOR THE NUCLEAR REGULATORY COMISSION A$4 M. David Lynch, Senior Project Manager Project Directorate III-2 l

Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

j Changes to the Technical Specifications Date of Issuance:

flarch 11, 1996 i

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ATTACHMENT TO LICENSE AMENDMENT NO.110 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by unendment number and contain a vertical line indicating the area of change.

REMOVE INSERT I

I 1-4 1-4 3/4 6-1 3/4 6-1 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 4

3/4 6-23 3/4 6-23 B 3/4 6-1 B 3/4 6-1 B 3/4 6-la B 3/4 6-la B 3/4 6-4a B 3/4 6-4a 6-20a 6-20a l

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NUCLEAR REQULATORY COMMISSION t

tllTASHIN 2TcN, D.C. - aaai

'+4.....

COMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE C0dNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. NPF-18 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated November 14, 1995, as supplemented January 4, 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 ir. 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.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment 1

and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is l

hereby amended to read as follows:

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M DEFINITIONS

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SECTION j

1.0 DEFINITIONS MGE 1.1 ACTI0N...........................................................

1-1

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1.2 AV E RAG E PLANAR EX POSURE..........................................

1 - 1 i

i 1.3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.......................

1-1 j

1.4 CHANNEL CALIBRATION..............................................

1-1 i

1.5 CHANNEL CHECK....................................................

1-1

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1.6 CHANNEL FUNCTIONAL TEST..........................................

1-1 l

1.7 CORE ALTERATION..................................................

1-2 t

1.8 CORE OPERATING LIMITS REP 0RT.....................................

1-2 I

1.9 CRITICAL POWER RATI0.............................................

1-2 1.10 DOSE EQUIVALENT I-131............................................

1-2 1

1.11 E-AVERAGE DISINTEGRATION ENERGY..................................

1-2 1.12 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME...............

1-2 l.13 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME........

1-2 1.14 FRACTION OF LIMITING POWER DENSITY...............................

1-3 l

1.15 FRACTION OF RATED THERMAL P0WER..................................

1-3 1.16 FREQUENCY N0TATION...............................................

1-3 1

1.17 GASEQUS RADWASTE TREATMENT SYSTEM................................

1-3 1.18 IDENTIFIED LEAKAGE...............................................

1-3 4

1.19 ISOLATION SYSTEM RESPONSE TIME...................................

1-3 1.20 DELETED..........................................................

1-4 i

1.21 LIMITING CONTROL R0D PATTERN.....................................

1-4 1.22 LINEAR HEAT GENERATION RATE......................................

1-4 1.23 LOGIC SYSTEM FUNCTIONAL TEST.....................................

1-4 I

l 1.24 MAXIMUM FRACTION OF LIMITING POWER DENSITY.......................

1-4 j

1.25 MEMBER (S) 0F THE PUBLIC..........................................

1-4 1.26 M I N I MUM C R I T I CAL POW E R RAT I 0.....................................

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3 LA SALLE - UNIT 1 I

Amendment No.110 1

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DEFINITIONS 1.20 DELETED LIMITING CONTROL R0D PATTERN 1.21 A LIMITING CONTROL R00 PATTERN shall be a pattern which results in the core being on a themal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE 1.22 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat eeneration per unit I

length of fuel rod.

It is the integral of the heat flux over the heat l

transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST 1.23 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components 1.e, all relays and contacts, all trip units, solid state logic elemenfs, i

etc. of a logic circuit from sensor through and including the actuated device to verify OPERABILITY. THE LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequentialsuch that the entire logic system is fested.

overla MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.24 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

MEMBERS (S) 0F THE PUBL.1,(

1.25 MEMBER (S)d with the plant.0F THE PUBLIC shall include all persons who are n associate This category does not include employees of the l

licensee, its contractors, or vendors. Also excluded from this categor persons who enter the site to service equipment or to make.eliveries. y are This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

i MINIMUM CRITICAL POWER RATIO 1.26 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

OFFSITE DOSE CALCULATION MANUAL 1.27 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents in the calculation of gaseous and liquid effluent monitoring Alare Setpoints, and in the conduct of the Environmental Radiological Mon /Triito ing Program. The ODCM shall also contain (Mo)nitorinthe Radioactive Effluent Controls and Radiological 1

Section 6.2.F.4 and (2)g Programs required by Technical Specification Environmental descri tions of the information that should be included in the Annual Radiolo ical Environmental Operating and Semi-Annual Radioactive Effluent Re ease Reports required by Technical Specification Sections 6.6.A.3 and 6.6.A.4.

I LA SALLE UNIT I I-4 Amendment No. 110

3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAIMENT INTEGRITY

,tIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour 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 CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least oncy, 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 for valves that are open under administrative control as permitted by Specification 3.6.3.

b.

Perform required visual examinations and leakage rate testing except for primary containment air lock testing and main steam lines through the isolation valves, in accordance with and at the frequency specified by the Primary Containment Leakage Rate Testing Program.

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 diinerted since the last verification or more often than once per 92 days.

LA SALLE - UNIT 1 3/4 6-1 Amendment No. 110

CONTAIMENT SYSTEMS l'

PRIMARY CONTAIMENT AIR LOCKS l-LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERABLE.

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

ACTION:

With one primary containment jair 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 l

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 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 1

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.

LA SALLE - UNIT 1 3/4 6-5 Amendment No. 110 i

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i CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:

By performing required primary containment air lock leakage testing a.

in accordance with and at the frequency s Containment Leakage Rate Testing Program,pecified by the Primary b.

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

I

Results shall be evaluated against acceptance criteria applicable to Specification 4.6.1.1.b.

- 0nly required to be performed upon entry into primary containment air lock when the primary containment is de-inerted.

LA SALLE - UNIT 1 3/4 6-6 Amendment No.110

CONTAllMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.3.1 Each primary containment isolation valve shall be demonstrated OPERA 8LE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

4.6.3.2 Each primary containment automatic isolation valve shall be demonstrated OPERABLE during COLD SHUTDOWN or REFUELING at least once nr 18 months by verifying that on a containment isolation test signal eact automatic isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each primary containment power operated or automatic isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each reactor instrumentation line excess flow check valve shall be demonstrated OPERABLE at least once per 18 months by verifying that the valve checks flow.

4.6.3.5 Each traversing in-core probe system explosive isolation valve shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying the continuity of the explosive charge.

b.

At least once per 18 months by removing the explosive squib from at least one explosive valve such that the explosive squib in each explosive valve will be tested at least once per 90 months, and initiating the explosive squib. The replacement charge for the exploded squib shall be from the same manufactured batch as the one fired or from another batch which has been certified by having at least one of that batch successfully fired. No explosive squib shall remain in use beyond the expiration of its shelf-life and operating-life.

4.6.3.6 At the frequency specified by the Primary Containment Leakage Rate Testing Program:

a.

Verify leakage rate through all four main steam lines through the isolation valves is s 100 scfh when tested at 2 25.0 psig.

l b.

Verify combined leakage rate through hydrostatically tested lines that penetrate the primary containment is within limits.

LA SALLE - UNIT 1 3/4 6-23 Amendment No. 110

3/4.6 CONTAIMENT SYSTEMS 1

RASES 3/4.6.1 PRIMARY CONTAIMENT 3/4.6.1.1 PRIMARY CONTAIMENT INTEGRITY PRIMARY CONTAIMENT 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.

4 The structural integrity r' the primary containment is ensured by the successful completion of the Inservice Inspection Program for Post Tensioning Tendons and by associated visual inspections of the steel liner and penetrations for evidence of deterioration or breach of integrity. This ensures that the structural integrity of the primary containment will be maintained in accordance with the provisions of the Primary Containment Tendon Surveillance Program. Testing and Frequency are consistent with the recommendations of Regulatory Guide 1.35, Revision 3, except that the Unit I and 2 primary containments shall be treated as twin containments even though the Initial Structural Integrity Tests were not within 2 years of each other.

4 PRIMARY CONTAINMENT INTEGRITY is maintained by limiting leakage to i

s 1.0 L except prior to the first startup after performing a required leakage test. ktthistime,PrimaryContainmentLeakageRateTestingProgramleakage limits must be met. Compliance with this LCO will ensure a primary containment configuration, including equipment hatches, that is structurally

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sound and that will limit leakage to those leakage rates assumed in the safety analyses.

The maximum allowable leakage rate for the primary containment (L is 0.635% by weight of the containment atmosphere per day at the design ba.)is s

LOCA maximum peak containment pressure (P,) of 39.6 psig.

Individual leakage rates specified for the primary containment air lock, main steam lines through the isolation valves, and valves in hydrostatically tested lines are addressed in LCO 3.6.1.3, and Surveillance Requirement 4.6.3.6.

Surveillance Requirement 4.6.1.1.b maintains PRIMARY CONTAINMENT INTEGRITY by requiring compliance with the visual examinations and leakage rate test requirements of the Primary Containmer.t Leakage Rate Testing Program.

Failure to meet air lock leakage testing (4.6.1.3) or main steam iso ation valve leakage (4.6.3.6.a) does not necessarily result in a failure of this Surveillance Requirement, 4.6.1.1.b.

The impact of the failure to meet these Surveillance Requirements 4.6.1.3 and 4.6.1.1.b must be evaluated against the Type A, 8, and C acceptance criteria of the Primary Containment Leakage Rate Testing Program. The leakage limits for main steam lines through the isolation valves and leakage test results of Surveillance Requirement 4.6.3.6.a are not included in the total sum of Type B and C tests (approved exemption). As-left leakage prior to the first startup after perfoming a required leakage test is required to be < 0.60 L, for combined Type B and C l

1eakage, and < 0.75 L, for overall Type A leakage. At all other times LA SALLE - UNIT 1 B 3/4 6-1 Amendment No.110

3Is.e LumIAImtNI SYSTEMS

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BASES 3/4.6.1 PRIMARY CONTAIMENT PRIMARY CONTAIMENT INTEGRITY (Continued) between required Type A tests, the acceptance criteria is based on an overall Type A leakage limit of s 1.0 L,.

At s 1.0 L the offsite dose consequences-are bounded by the assumptions of the safety, analysis.

The Frequency is required by the Primary Containment Leakage Rate l

Testing Program.

3/4.6.1.2 DELETED 3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS I

The limitation on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the primary containment leakage rate given in Specification 3/4.6.1.1.

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.

t Maintaining primary containment air locks OPERABLE requires compliance with the leakage rate test requirements of the Primary Containment Leakage Rate Testing Program. The surveillance requirements reflect the leakage rate testing requirements with respect to air lock leakage (Type B leakage tests).

The acceptance criteria were established during initial air lock and primary containment OPERABILITY testing. The periodic testing requirements verify that air lock leakage does not exceed the allowed fraction of the overall l

l primary containment leakage rate. The Frequency is required by the Primary i

Containment Leakage Rate Testing Program. Additional annotation is provided to require the resultt> of air lock leakage tests being evaluated against the acceptance criteria applicable to the surveillance requirements.

This ensures that the air lock leakage is properly accounted for in determined the combined j

Type B and Type C primary containment leakage.

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l-LA SALLE - UNIT 1 B 3/4 6-la Amendment No. 110 l

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CONTAIMENT SYSTEMS BASES 4

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PRIMARY CONTAlfetENT ISOLATION VALVES (Continued) with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude assess to close the valves and that i

this action will prevent the release of radioactivity outside the primary containment.

i Surveillance Requirement 4.6.3.6.a verifies leakage through all four main steam lines is s 100 scfh when tested at 2 P, (25.0 psig). The transient i

and accident analyses are based on leakage at the specified leakage rate. The leakage rate for main steam lines through the isolation valves must be

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verified to be in accordance with the Primary Containment Leakage Rate Testing i

Program.

A~ Note has been added to this Surveillance Requirement requiring the i

results to be excluded from the total of Type B and Type C tests. This ensures that leakage rate for main steam lines through the isolation valves is properly accounted for in determining the overall primary containment leakage rate. The Frequency is required by the Primary Containment Leakage Rate Testing Program.

Surveillance Requirement 4.6.3.6.b test of hydrostatically tested lines 1

provides assurance that the assumptions of UFSAR Section 6.2 are met. The i

combined leakage rates must be demonstrated in accordance with the leakage l

rate test at a frequency in accordance with the Primary Containment Leakage l

Rate Testing Program.

I 3/4.6.4 VACUUM RELIEF Vacuum relief breakers are provided to equalize the pressure between the suppression chamber and drywell. This system will maintain the structural integrity of the primary containment under conditions of large differential pressures.

1 The vacuum breakers between the suppression chamber and the drywell must not be inoperable in the open position since this would allow bypassing of the suppression pool in case of an acc: dent. There are four valves to provide i

redundancy so that operation may continue for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with one vacuum breaker inoperable provided that the manual isolation valves on each side are 4

in the closed position.

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i LA SALLE - UNIT 1 B 3/4 6-4a Amendment No. 110 I

ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) 6.2.F.7 Primary Containment Leakaae Rate Testina Proaram i

A program shall be established to implement the leakage rate testing of the primarycontainmentasrequiredby10CFR50.54(oDand10CFR50 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-BasedContainmentLeak-TestingProgram,"datedSeptember1995.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P, is 39.6 psig.

The maximum allowable primary containment leakage rate, L., at P, is 0.635% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Primary containment overall leakage rate acceptance criterion is $1.0 L During the first unit startup following testing in accordance with this,.

program, the leakage rate acceptance criteria are s 0.60 L for the combined Type B and Type C tests, and s 0.75 L, for Type A, tests, 4

b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is 50.05 L, when tested at 2 P.,

1 2)

For each door, the seal leakage rate is s 5 scf per hour when the gap between the door seals is pressurized to 2 10 psig.

The provisions of specification 4.0.2 do not apply to the test frequencies i

specified in the Primary Containment Leakage Rate Testing Program.

The provisions of specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:

i a.

The Connission shall be notified and a Licensee Event Report submitted 2

pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the Onsite Review and Investigative Function.

LA SALLE - UNIT 1 6-20a Amendment No.110

(2)

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 95, and the Environmental Protection Plan contained in A>pendix B, are hereby incorporated in the license.

The licensee stall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective upon the date of issuance and shall be implemented no later than June 30, 1996.

FOR THE NUCLEAR REGULATORY COM11SSION C?-

M. David Lynch, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 11, 1996 I

I ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.

4 REMOVE INSERT l

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l-3 1-3 3/4 6-1 3/4 6-1 l

3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 3/4 6-26 3/4 6-26 8 3/A 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2 B 3/4 6-4a B 3/4 6-4a 6-20a 6-20a 1

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E DEFINITIONS SECTION 1.0 DEFINITIONS PAGE l.1 ACTI0N...........................................................

1-1 1.2 AVERAGE PLANAR EXP05URE..........................................

1-1 1.3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.......................

1-1 1.4 CHANN E L CAL I BRAT I ON..............................................

1 - 1 1.5 CHANNEL CHECK....................................................

1-1 1.6 CHANNEL FUNCTIONAL TEST..........................................

1-1 1.7 CORE ALTERATION..................................................

1-2 1.8 CORE OPERATING LIMITS REP 0RT.....................................

1-2 1.9 CRITICAL POWER RATI0.............................................

1-2 1.10 DOSE EQUIVALENT I-131............................................

1-2 1.11 E-AVERAGE DISINTEGRATION ENERGY..................................

1-2 1.12 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME...............

1-2 1.13 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME........

1-2 1.14 FRACTION OF LIMITING POWER DENSITY...............................

1-3 1.15 FRACTION OF RATED THERMAL P0WER..................................

1-3 1.16 FREQUENCY N0TATION...............................................

1-3 1.17 GASEOUS RADWASTE TREATMENT SYSTEM................................

1-3 1.18 IDENTIFIED LEAKAGE...............................................

1-3 1.19 ISOLATION SYSTEM RESPONSE TIME...................................

1-3 1.20 DELETED..........................................................

1-3 1.21 LIMITING CONTROL ROD PATTERN.....................................

1-4 1.22 LINEAR HEAT GENERATION RATE......................................

1-4 1.23 LOGIC SYSTEM FUNCTIONAL TEST.....................................

1-4 1.24 MAXIMUM FRACTION OF LIMITING POWER DENSITY.......................

1-4 1.25 MEMBER (S) 0F THE PUBLIC..........................................

1-4 1.26 MINIMUM CRITICAL POWER RATI0.....................................

1-4 LA SALLE - UNIT 2 I

Amendment No. 95

DEFINITIONS FRACTION OF LIMITING POWER DENSITY 1.14 The FRACTION OF LIMITING POWER DENSITY qFLPD)LHGR limit for that bundlesh at a given location divided by the spec 1fied type.

FRACTION OF RATED THERMAL POWER 1.15 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.

FREQUENCY NOTATION 1.16 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GASEOUS RADWASTE TREATMENT SYSTEM 1.17 A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.18 IDENTIFIED LEAKAGE shall be:

a.

Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both s)ecifically located and known either not to interfere with t1e o)eration of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

ISOLATION SYSTEM RESPONSE TIME 1.19 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

1.20 DELETED LA SALLE - UNIT 2 1-3 Amendment No. 95

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3/4.6 ~ CONTAIMENT SYSIItL1

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3/4.6.1 PRIMARY CONTAIh4![I PRIMARY CONTAIMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

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

4 ACTION:

4' Without PRIMARY CONTA!WENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour 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 .

1 SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least oncp,per 31 days by verifying that all primary containment i_

penetrations not capable of being closed by OPERABLE containment i

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 for valves that are open under administrative control as permitted by Specification i

3.6.3.

b.

Perform required visual examinations and leakage rate testing except for primary containment air lock testing and main steam lines j

through the isolation valves, in accordance with and at the frequency specified by the Primary Containment Leakage Rate Testing i

Program.

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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 perfomed when the primary containment has not been deinerted since the last verification or more often than once per 92 days.

LA SALLE - UNIT 2 3/4 6-1 Amendment No. 95

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CONTAINMENT SYSTEMS frill &RY GQliTA1AEllI AIR LEKit LINITING CONDITION FOR OPERATION i

3.6.1.3 Each primary containment air lock shall be OPERABLE.

APPLICABJU,It OPERATIONAL CONDITIONS 1, 2*, and 3.

l E.UM:

With one primary containment air lock door inoperable:

a.

1 l.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within j

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 i

required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least j

once per 31 days.

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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 .

l 4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the primary containment air lock inoperable, except as a result 1

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 l

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

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See Special Test Exception 3.10.1.

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LA SALLE - UNIT 2 3/4 6-5 Amendment No. 95 i

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

By performing required primary containment air lock leakage testing a.

in accordance with and at the frequency s Containment Leakage Rate Testing Program,pecified by the Primary b.

Atleastonceper6monthsbyverjfyingthatonlyonedoorineach air lock can be opened at a time.

"Results shall be evaluated against acceptance criteria applicable to Specification 4.6.1.1.b.

,,Only required to be performed upon entry into primary containment air lock when the primary containment is de-inerted.

LA SALLE - UNIT 2 3/4 6-6 Amendment No. 95

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CONTAllfiENT SYSTEMS SURVEILLANCE REQUIREMENTS 1

4.6.3.1 Each primary containment isolation valve shall be demonstrated OPERA 8LE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

4.6.3.2 Each primary containment automatic isolation valve shall be demonstrated OPERABLE during COLD SNUTDOWN or REFUELING at leart once wr 18 months by verifying that on a containment isolation test signal enci automatic isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each primary containment power operated or automatic isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each reactor instrumentation line excess flow check valve shall be demonstrated OPERABLE at least once per 18 months by verifying that the valve checks flow.

4.6.3.5 Each traversing in-core probe system explosive isolation valve shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying the continuity of the explosive charge.

b.

At least once per 18 months by removing the explosive squib from at least one explosive valve such that the explosive squib in each explosive valve will be tested at least once per 90 months, and initiating the explosive squib. The replacement charge for the exploded squib shall be from the same manufactured batch as the one fired or from another batch which has been certified by having at least one of that batch successfully fired. No explosive squib shall remain in use beyond the expiration of its shelf-life and operating-life.

4.6.3.6 At the frequency specified by the Primary Containment Leakage Rate Testing Program:

a.

Verify leakage rate through all four main steam lines through the isolation valves is s 100 sefh when tested at it 25.0 psig.

I b.

Verify combined leakage rate through hydrostatically tested lines that penetrate the primary containment is within limits.

LA SALLE - UNIT 2 3/4 6-26 Amendment No. 95

3/4.6 CONTAIMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAIMENT 3/4.6.1.1 PRIMARY CONTAIMENT INTEGRITY PRIMARY CONTAIMENT 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 structural integrity of the primary containment is ensured by the successful completion of the Inservice Inspection Program for Post Tensioning Tendons and by associated visual inspections of the steel liner and penetrations for evidence of deterioration or breach of integrity. This ensures that the structural integrity of the primary containment will be maintained in accordance with the provisions of the Primary Containment Tendon Surveillance Program. Testing and Frequency are consistent with the recommendations of Regulatory Guide 1.35, Revision 3, except that the Unit I and 2 primary containments shall be treated as twin containments even though the Initial Structural Integrity Tests were not within 2 years of each other.

PRIMARY CONTAINMENT INTEGRITY is maintained by limiting leakage to s 1.0 L except prior to the first startup after performing a required leakage test. At this time, Primary Containment Leakage Rate Testing Program leakage limits must be met. Compliance with this LCO will ensure a primary containment configuration, including equipment hatches, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analyses.

The maximum allowable leakage rate for the primary containment (L ) is 0.635% by weight of the containment atmosphere per day at the design ba, sis LOCA maximum peak containment pressure (P,) of 39.6 psig.

Individual leakage rates specified for the primary containment air lock, main steam lines through the isolation valves, and valves in hydrostatically tested lines are addressed in LC0 3.6.1.3, and Surveillance Requirement 4.6.3.6.

Surveillance Requirement 4.6.1.1.b maintains PRIMARY CONTAINMENT INTEGRITY by requiring compliance with the visual examinations and leakage rate test requirements of the Primary Containment Leakage Rate Testing Program.

Failure to meet air lock leakage testing (4.6.1.3) or main steam isolation valve leakage (4.6.3.6.a) does not necessarily result in a failure of this Surveillance Requirement, 4.6.1.1.b.

The impact of the failure to meet these Surveillance Requirements 4.6.1.3 and 4.6.1.1.b must be evaluated against the Type A, B, and C acceptance criteria of the Primary Containment Leakage Rate Testing Program. The leakage limits for main steam lines through the isolation valves and leakage test results of Surveillance Requirement 4.6.3.6.a are not included in the total sum of Type B and C tests (approved exemption). As-left leakage prior to the first startup after performing a required leakage test is required to be < 0.60 L, for combined Type B and C l

1eakage, and < 0.75 L, for overall Type A leakage. At all other times LA SALLE - UNIT 2 8 3/4 6-1 Amendment No. 95

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 1

PRIMARY CONTAINMENT INTEGRIII (Continued) between required Type A tests, the acceptance criteria is based on an overall Type A leakage limit of s 1.0 L,.

At s 1.0 L the offsite dose consequences are bounded by the assumptions of the safety, analysis.

The Frequency is required by 10 CFR 50, Appendix J, as modified by approved exemptions. Thus, 4.0.2 (which allows Frequency extensions) does not apply to Surveillance Requirement 4.6.1.1.b.

3/4.6.1.2 DELETED 3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitation on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the primary containment leakage rate given in Specification 3/4.6.1.1.

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 4

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

Maintaining primary containment air locks OPERABLE requires compliance with the leakage rate test requirements of the Primary Containment Leakage Rate Testing Program. The surveillance requirements reflect the leakage rate testing requirements with respect to air lock leakage (Type B leakage tests).

The acceptance criteria were established during initial air lock and primary containment OPERABILITY testing. The periodic testing requirements verify that air lock leakage does not exceed the allowed fraction of the overall primary containment leakage rate. The Frequency is required by the Primary Containment Leakage Rate Testing Program. Additional annotation is provided to require the results of air lock leakage tests being evaluated against the acceptance criteria applicable to the surveillance requirements. This ensures that the air lock leakage is properly accounted for in determined the combined Type B and Type C primary containment leakage.

3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance for the main steamline 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 degradation has LA SALLE - UNIT 2 B 3/4 6-2 Amendment No. 95

CONTAIMENT SYSTEMS BASES PRIMARY CONTAINMENT ISOLATION VALVES (Continued)

This specification provides assurance that the PCIVs will perform their designed safety functions to control leakage from the primary containment during accidents.

i The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1) stationing an operator, who is in constant communication i

with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude assess to close the valves and that this action will prevent the release of radioactivity outside the primary i

containment.

l Surveillance Requirement 4.6.3.6.a verifies leakage through all four main steam lines is s 100 scfh when tested at 2 P, (25.0 psig). The transient l

and accident analyses are based on leakage at the specified leakage rate. The l

1eakage rate for main steam lines through the isolation valves must be verified to be in accordance with the Primary Containment Leakage Rate Testing l

Program. A Note has been added to this Surveillance Requirement requiring the results to be excluded from the total of Type B and Type C tests. This i

ensures that leakage rate for main steam lines through the isolation valves is properly accounted for in determining the overall primary conttinment leakage rate. The Frequency is required by the Primary Containment Leakage Rate Testing Program.

Surveillance Requirement 4.6.3.6.b test of hydrostatically tested lines provides assurance that the assumptions of UFSAR Section 6.2 are met.

The combined leakage rates must be demonstrated in accordance with the leakage j

rate test at a frequency in accordance with the Primary Containment Leakage i

Rate Testing Program.

3/4.6.4 VACUUM RELIEF Vacuum relief breakers are provided to equalize the pressure between the suppression chamber and drywell. This system will maintain the structural integrity of the primary containment under conditions of large differential j

pressures.

The vacuum breakers between the suppression chamber and the drywell must i

not be inoperable in the open position since this would allow bypassing of the suppression pool in case of an accident. There are four valves to provide redundancy so that operation may continue for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with one vacuum breaker inoperable provided that the manual isolation valves on each side are in the closed position.

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i LA SALLE - UNIT 2 B 3/4 6-4a Amendment No. 95 4

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ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) the Initial Structural Integrity Tests were not within 2 years of each other.

The Onsite Review and Investigative Function shall be responsible for reviewing and approving changes to the Inservice Inspection Program for Post Tensioning Tendons.

The provisions of 4.0.2 and 4.0.3 are applicable to the Tendon Surveillance Program insepction frequencies.

6.2.F.7 Primary Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option 8, as modified by approved exemptions. This program shall >e in accordance with the guidelines contained in Regulatory Guide 1.163,

" Performance-Based Containment Leak-Testing Program," dated September 1995.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P, is 39.6 psig.

The maximum allowable primary containment leakage rate, L, at P, is 0.635% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Primary containment overall leakage rate acceptance criterion is s1.0 L During the first unit startup following testing in accordance with this,.

program, the leakage rate acceptance criteria are 5 0.60 L for the combined 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 50.05 L, when tested at 2 P,.

2)

For each door, the seal leakage rate is s 5 scf per hour when the gap between the door seals is pressurized to 210 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 provisions of specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed pursuant to Specification 6.1.G.2.c(1).

LA SALLE - UNIT 2 6-20a Amendment No. 95

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ML20101B818

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