ML20138P726

Amends 28 & 15 to Licenses NPF-11 & NPF-18,respectively, Revising Setpoints & Setpoint Tolerance for 18 safety-relief Valves in Tech Specs

ML20138P726
Person / Time
Site:	LaSalle
Issue date:	10/31/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20138P728	List: ML20138P726 ML20138P730
References
TAC-62045, NUDOCS 8511070391
Download: ML20138P726 (10)

Text

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C0ttChtEAL1h EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION. UNIT 1 Al4Eh0hENT TO FACILITY OPERATING LICENSE

. Ar cr.crert No. 29 License No. NPF-11 1.

The Nuclear Regulatory Cerrissicn (the Comission or the hkC) beving fccrd that:

A.

The application for crcrcrent filed by the Cortronwealth Edisen Ccrpeny, dated August 19, 1985 as supplemented by letter catec Septersber 5,1985, complies with the standards and requirements of the Aterric Ercr9y Act of 1954, as amended (the Act), tnd the Comission's reg. lotions set forth in 10 CFR Chapter I; E.

The f acility will operate ir, conformity with the applicatien the previsiers of the Act, and the regulatioris of the Comission; C.

There is reasonable assurance:

(i) that the activities cuthorized by this at:entrert can be conducted without endanSering the health and sofet, cf tte public, and (ii) that such activities will be concucted in cctpliance with the Cerreission's regulatices sct forth in 10 CFR Chapter I; D.

The issuerce of this amendment will not be intm. cal to the comon defense anc security or to the health and safety of the public; and E.

The issuance c.f tMs crerdirent is in accordance with 10 CFh 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 Specificaticr.s as indicated in the attachment to this license anendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby arnended tc read as follcws:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2A and the Environn. ental Protection Plan contained in Appendix b, are hereby incorporated in the licerst.

The lictrice shall operate the facility in accordance with the Technical Specifications and the Environmental Prctcction Plan.

8511070391 8 1 1

PDR ADOCM 0 373 P

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This aendnent is effective as of date of issuance.

FOR THE NUCLEAR REGULAT0ftY C0fst:ISSION a.

Walter R. Butler, Chief Licensing Branch lio. 2 Divisicn of Licensing

Enclosure:

Changes tc tiie Tutt ical Specifications Late of Istverce:

October 31, 1985

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This amendment is effective as of date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

- Changes to the Technical Specifications Date of Issuance: October 31, 1985 h

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o ENCLOSURE TO LICEllSE At'ENLhENT hC. 28 FACIL.iTY OVERATING LICENSE NO. NPF-11 LLCAEl h0. 50-373 Peplece tte following page of the Appenaix "A" Technical Specifications with the enclosed page. The revised page is identified by Arcencircer.t r.trter and contains a vertical line ir.diccting the area of change.

REPCVE INSERT 3/ 44-5 3/4 4-5

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. Me REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION s

3.4.2 The safety valve function of eighteen reactor coolant system safety /

reliefvalvessgallbeOPERABLEwiththespecifiedcodeisafetvvalvefunction lift settings.*

a.

4 safety / relief valves @ 1205 psig +1%, -3%

b.

4 safety / relief valves @ 1195 psig +1%, -3%

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c.

4 safety / relief valves @ 1185 psig +1%, -3%

d.

4 safety / relief valves @ 1175 psig +1%, -3%

e.

2 safety / relief valves @ 1150 psig +1%, -3%

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the safety valve function of one or more of the above required a.

safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 110 F, close the stuck open relief valve (s); if unable to close the open valve (s) within 2 minutes or if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown 1

position.

c.

With one or more safety / relief valve stem position indicators inoperable, restore the inoperable stem position indicators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the follswing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

.s SURVEILLANCE REQUIREMENTS s 4.4.2.1 The safety / relief valve stem position indicators of each safety / relief valve shall be demonstrated OPERABLE by performance of a:

a.

CHANNEL CHECK at least once per 31 days, and a s

b.

CHANNEL CALIBRATION at least once per 18 months.**'

4.4.2.2 The low low set function shall be demonstrated not to interfere with the OPERABILITY of the safety relief valves or the ADS by peh,'ormahre of a CHANNEL CALIBRATION at least once per 18 months.

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• The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

1. Up to two inoperable valves may be replaced with spare 0PERABLE valves with

'S lower setpoints until the next refueling outage.

A

• • The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam prsssure is adequate to perform the test.

L' LA SALLE-UNIT 1 3/4 4-5 Amendment No. 28

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I9 UNITED STATES 4

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NUCLEAR REGULATORY COMMISSION 5

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CCIA0hkEALTh EDIS0N COMPAN)

DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 V

MEh[JhT TO FACILITY OPERATIfiG LICENSE frrerdirent No.15 License No. NPF-18 1.

The fiuclear Regulatory Commission (the Corrission or the NRC) havir:9 founo that:

A.

The applicatice fer arcrdment filed by the Connerxealth Loison ated August 19, 1985 es suppleraented by letter datec Cccpany, (5,19d5, con. plies with the stardards and requirements September c4 'thk Atorric Energy Act of 1954, as amended (the Act), ai.d the s'

Conmission's regulations set forth in 10 CFR Chapter I;

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B.

The facility will operate in conforr.iity with the application, the previsions of the Act, and the regulations of the Commission; ss C.

There.is reasonable assurance:

(i) that the activities authcrized by'this anendirent can be conducted without eridangering the health

- g and safety of the rtblic, and (ii) that such activities will be conducted in coraplit.nce with the Commission's regulaticns set forth in 10 CFR Chapter I; D.

The issuance of this anendment will not Le ininical to the contuon defense ano security cr to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 LFR Part 51 of the Comission's regulations and all applicabl( rcr4uireraents have been satisfied.

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2.

Accordingly, the lice'nse is amendea by changes to the Technical Specifications as indicated in the attachment to this license arrer.dr:ent and paragrapb 2.C.(2) of Facility Operating License No. NPF 18 is hereby l

amended to read as folicws:

e (2) Technical Secif kations and Environmental Protection Plan The T(chnical Specifications contained in Appendix A, as revised thrcugh Amendment lio. 15 and the Environmental Frctection Plan contained in Apperdix B, are hereby 11.ccrpcrated in the license. Thc licensee shall operate the facility in acccrdance with the Technical Specifications and the Environmer.tol Protection Plan.

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2 3.

This arrencntr,t is effective as of date of issuarct.

FOR THE NUCLEAR REGULATCRY COMMISSION

/

9 kalter R. Butler, Chief

' Licensing Branch hu, E Division of Litersing

Enclosure:

Cher.ges to the Technical Specifications Cete of Issuance:

October 31, 1985

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. 3.

This amendment is effective as of date of issuance.

FOR THE NUCLEAR REGULATORY C0!34ISSIOh Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

Changes to the Technical Specifications Date of Issuance: October 31, 1985 1

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m El:CLOSLhE TC LICENSE AMENDMEf;T h0.15 FACILlWT)TIERATil!G LICENSE NO NPF-18 00LAEl fiO. 50-374 Replace the following re.gt of the Appendix "A" Technical Specifications with the encicsed page. The revised page is identified by Amendment number and contairs e vertical line indicating the area of ct.ange.

REMOVE IllSERT 3/4 4-6 3/4 4-6

REACTOR COOLANT SYSTEM i

3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of 18 reactor coolant system safety / relief valves shall be OPERABLE with the specified code safety valve function lift settings.* #

a.

4 safety / relief valves @ 1205 psig + 1%, -3%

b.

4 safety / relief valves @ 1195 psig + 1%, -3%

c.

4 safety / relief valves @ 1185 psig + 1%, -3%

d.

4 safety / relief valves @ 1175 psig + 1%, -3%

e.

2 safety / relief valves @ 1150 psig + 1%, -3%

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the safety valve function of one or more of the above required a.

safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 110 F, close the stuck open relief valve (s); if unable to close the open valve (s) within 2 minutes or if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown position.

With one or more safety / relief valve stem position indicators c.

inoperable, restore the inoperable stem position indicators to OPERABLE status within 7 days or be in at least HOT SHUTDGWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.2.1 The safety / relief valve stem position indicators of each safety / relief valve shall be demonstrated OPERABLE by performance of a:

CHANNEL CHECK at least once per 31 days, and a a.

b.

CHANNEL CALIBRATION at least once per 18 months.**

4.4.2.2 The low low set function shall be demonstrated not to interfere with the OPERABILITY of the safety / relief valves or the ADS by performance of a CHANNEL CALIBRATION at least once per 18 months.

• The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

1. Up to two inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling outage.

• • The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

l LA SALLE - UNIT 2 3/4 4-6 Amendment No. 15 l

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