Text

Amends 67 & 49 to Licenses NPF-11 & NPF-18,respectively, Revising Tech Specs by Allowing Operation of Both Units W/Suppression Pool Temps Up to 105 F
	ML20246F872
Person / Time
Site:	LaSalle
Issue date:	07/07/1989
From:	Shemanski P; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20246F874	List: ML20246F872; NUREG-0783, Safety Evaluation Supporting Amends 67 & 49 to Licenses NPF-11 & NPF-18,respectively;
References
	NUDOCS 8907140078
	Download: ML20246F872 (12)
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j WASHINGTON, D. C. 20555 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE J

Amendment No. 67 License No. NPF-11 1.

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

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 7,1988 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 Connission; C.

There is reasonable assurance: (i)thattheactivitiesauthorizedby 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 Contr.ission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this emendment 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 E' ?

the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions 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:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 67, 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 Specification; and the Environmental Protection Plan.

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This amendment is effective upon date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G J c.r M Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

Changes to the Technical Specifications Date of Issuance:

July 7, 1989

ENCLOSURE TO LICENSE AMENDMENT NO. 67 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO.60-373 Replace the following ) ages of the Appendix "A" Technical Specifications with the enclosed pages. T1e revised pages are identified by amendment number and

.contain a vertical line indicating the area of change.

REMOVE INSERT 3/4 6-16 3/4 6-16 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 B

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' CONTAINMENT' SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS

-SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION

_3.6.2.1-The suppression chamber shall be OPERABLE with:

a.

The pool water:

1.

Volume between 131,900 ft3 3

and 128,800 ft, equivalent to a level between +3 inches ** and -4 1/2 inches **, and a 2.

Maximum average temperature of 105 F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase to:

a) 110 F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.

b) 120 F with the main steam line isolation valves closed following a scram.

b.

Drywell-to-suppression charmer bypass leakage less than or equal to 10%oftheacceptableA/[kdesignvalueof0.03ft, 2

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With the suppression chamber water level outside the above limits, restore the water level to within the limits 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 .

b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average water temperature greater than or equal to 105 F, stop all testing which adds heat to the suppression pool, and restore the average temperature to less than or equal to 105 F 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 , except, as permitted above:

1.

With the suppression chamber average water temperature greater than 110 F, place the reactor mode switch in the Shutdown position and operate at least one residual heat removal loop in

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the suppression pool cooling mode.

2.

With the suppression chamber average water temperature greater than 120 F, depressurize the reactor pressure vessel to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

See Specification 3.5.3 for ECCS requirements.

- Level is referenced to a plant elevation of 699 feet 11 inches (See Figure B 3/4.6.2-1).

LA SALLE - UNIT 1 3/4 6-16 Amendment No. 67

c CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) c.

With one suppression chamber water level instrumentation channel inoperable and/or with one suppression pool water temperature instrumentation division inoperable, restore the inoperable instrumentation to OPERABLE status within 7 days or verify suppres-sion chamber water level and/or temperature to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by local indication.

d.

With both suppression chamber water level instrumentation channels inoperable and/or with both suppression pool water temperature instrumentation divisions inoperable, restore at least one inoperable water level channel and one water temperature division to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 , With the drywell-to-suppression chamber bypass leakage in excess of e.

the limit, restore the bypass leakage to within the limit prior to increasing reactor coolant temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:

a.

By verifying the suppression chamber water volume to be within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber average water temperature to be less than or equal to 105 F, except:

1.

At least once per 5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber average water temperature less than or equal to 105 F.

2.

At least once per 60 minutes when suppression chamber average water temperature is greater than 105 F, by verifying suppression chamber average water temperature less than or equal to 110 F and THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.

3.

At least once per 30 minutes following a scram with suppression chamber average water temperature greater than or equal to l

105 F, by verifying suppression chamber average water temperature less than or equal to 120 F.

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LA SALLE - UNIT 1 3/4 6-17 Amendment No. 67

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CONTAINMENT SYSTEM 5-

. SURVEILLANCE REQUIREMENTS (Continued) c.

By verifying at least two suppression chamber water level instru-mentation channels and at least 14 suppression pool water temperature instrumentation channels, 7 in each of two divisions OPERABLE by performance of a:

1.

CHANNEL CHECK.at least.once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 2.'

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.

CHANNEL CALIBRATION at least once per 18 months.

The. suppression chamber water level and suppression pool temperature alarm setpoint shall be:

a)

High water level 5 +2 inches

b)

. Low water level.)_-3 inches

c)

High temperature 1 105 F d.

By conducting drywell-to suppression chamber bypass leak tests and verifying that the A/ # calculated from the measured leakage is

.within the'specified limit when drywell-to-suppression chamber bypass-' leak tests are conducted:

1..

At least once per 18 months at an initial differential pressure

.of 1.5 psi', and 2.

At'the first refueling outage and then on the schedule required for Type A Overall Integrated Containment Leakage Rate tests by Speci-fication 4.6.1.2.a; at an initial differential pressure of 5 psi, except that, if the first two 5 psi leak tests performed up to that time result in:

1.

A calculated A/# within the specified limit, and 2.

The A/# calculated from the leak tests at 1.5 psi is 1 20% of the specified limit, 1

then the leak tests at 5 psi may be discontinued.

Level is referenced to a plant elevation of 699 feet 11 inches (See Figure B 3/4.6.2-1).

LA SALLE - UNIT 1-3/4 6-18 Amendment No. 67

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UNITED STATES

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~ WASHINGTON, D. C. 20555 pf COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLECOUNTYSTATION, UNITE AMENDMENT TO FACILITY OPERATING LICE >SE Amendment No. 49 License No. NPF-18 1.

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

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 7, 1988 complies with the standards and

-requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's regulations set ft.-th in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the 1

provisions of the Act, and the regulations of the Comission; l

C.

.There is reasonable assurance: (!) that the activities aut orized by h

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph y

2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment Nc. 49, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the ftetlity in accordance with the Technical Specifications and the Environmental Protection Plan.

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This amendment is effective upon date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

($

Paul C. Shemanski, heting Director Project Directorate I.'I-2 Division of Reactor Projects-- III.

IV, Y and Special Projects

Enclosure:

- Changes to the Technical Specifications Date of Issuance:

July.7, 1989 o

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ENCLOSURE'TO LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. NPF-18 i

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 verticril line indicating the area of change.

REMOVE INSERT 3/4 6-19 3/4 6-19 3/4 t,-20 3/4 6-20

'3/4 6-21 3/4 6-21 l

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o CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS-SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION 3.'6.2.1

The suppression chamber shall be OPERABLE with:

a.

.The pool water:

1.

Volume between 131,900 ft8 3

and 128,800 ft, equivalent to a level between +3 inches ** and -4 1/2-inches **, and a 2.

Maximum average temperature'of 105 F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase to:

a) 110 F with THERMAL POWER less than or equal to 1% of RATED-THERMAL POWER.

b) 120 F with the main steam line isolation valves closed i

following a scram.

b, Drywell-to-suppression chamber bypass leakage less than or equal to 10% of the acceptable A/JE design value of 0.03 ft,

2 APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the suppression chamber water level outside the above limits, a.

restore the water level to within the limits 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 .

b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average water temperature greater than or equal to 105 F, stop all testing which adds heat to the suppression pool, and restore the average temperature to less than or equal to 105 F 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 , except, as permitted above:

1.

With the suppression chamber average water temperature greater than 110 F, place the reactor mode switch in the Shutdown position and operate at least one residual heat removal loop in the suppression pool cooling mode.

2.

With the suppression chamber average water temperature greater than 120 F, depressurize the reactor pressure vessel to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

See Specification 3.5.3 for ECCS requirements.

- Level is referenced to a plant elevation of 699 feet 11 inches (See figure B 3/4.6.2-1).

LA SALLE - UNIT 2 3/4 6-19 Amendment No. 49

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) c.

'With one suppression chamber water level instrumentation channel

. inoperable and/or with one suppression pool water temperature instrumentation division inoperable, restore the inoperable instrumentation to OPERABLE status within 7 days or verify suppres-sion chamber water level and/or temperature to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by local indication.

d.

With both suppression chamber water level instrumentation channels inoperable and/or with both suppression pool water temperature instrumentation divisions inoperable, restore at east one inoperable water level channel and one water temperature division to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least.OT 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 , e.

With the drywell-to-suppression chamber bypass leakage in excess of the limit, restore the bypass leakage to within the limit prior to increasing reactor coolant temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.2.1 The suppression chamber sha71 be demonstrated OPERABLE:

a.

By verifying the suppression chamber water volume to be within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

At'least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber average water temperature to be less than or equal to 105 F, except:

1.

At least once per 5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber aserage water temperature less than or equal to 105 F.

2.

At ler:,t once per 60 minutes when suppression chamber average water temperature is greater than 105 F, by verifying suppression chamber average water temperature less than or equal to 110 F and THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.

4 3.

At least once per 30 minutes following a scram with suppression chamber average water temperature greater than or equal to 105 F, by verifying suppression chamber average water temperature less than or equal to 120 F.

LA SALLE - UNIT 2 3/4 6-20 Amendment No. 49

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.

By verifying at least 2 suppression chamber water level instru-mentation channels and at least 14 suppression pool water temperature instrumentation channels, 7 in each of two divisions, OPERABLE by performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 2.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.

CHANNEL CALIBRATION at least once per 18 months.

The suppression chamber water level and suppression pool temperature alarm setpoint shall be:

a)

High water level < +2 inches

b)

Low water level > -3 inches

c)

High temperature 5 105 F d.

By conducting drywell-to-suppression chamber bypass leak tests and verifying that the A/8 calculated from the measured leakage is within the specified limit when drywell-to-suppression chamber bypass leak tests are conducted:

1.

At least once per 18 months at an initial differential pressure of 1.5 psi, and 2.

At the first refueling outage and then on the schedule required for Type A Dverall Integrated Containment Leakage Rate tests by Speci-3 fication 4.6.1.2.a., at an initial differential pressure of 5 psi,

]

except that, if the first two 5 psi leak tests performed up to that time result in:

j 1

1.

A calculated A/8 within the specified limit, and 2.

The A/8 calculated from the leak tests at 1.5 psi is < 20% of i

the specified limit, then the leak tests at 5 psi may be discontinued.

Level is referenced to a plant elevation of 699 feet 11 inches (See Figure B 3/4.6.2-1).

LA SALLE - UNIT 2 3/4 6-21 Amendment No. 49

ML20246F872

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