ML20137Y986
| ML20137Y986 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/01/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137Y991 | List: |
| References | |
| NUDOCS 8510080133 | |
| Download: ML20137Y986 (8) | |
Text
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(p.a<eogjo UNITED STATES g
NUCLEAR REGULATORY COMMISSION n
t
.p WASHINGTON, D. C. 20555 s...../
COMMONWEALTH EDISON C0l! pal $
DOCKET N0. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. hPF-11 1.
The Nuclear Regulatory Comission (the Ccmission or the NRC) having found that:
A.
The application f or amendment filed by the Ccnronwealth Edison Company, dated September 23, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and thc Comission's regulations set forth in 10 CFR Chapter I; E.
The facility will operatt in conformity with the applicaticr., tte provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this amenoment can be conducted without endangering the health and safety of the it'blic, and (ii) that such activities will be concutted in coupliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuarce of this amendment will not be inimical to the comon defense ano security cr tc. the health and safety of the public; and E.
The issuance of tFis arrendment 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 Specificatiens as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Techrical Specifications contained in Appendix A, as revised through Amendment No. 25 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 Specificaticrs and the Environmental Protecticn Plan.
851000013385M373 PDR ADOCK PDR P
_2 This arendrient is effective es of Scpter:ber 26, 1985.
FCk THE NUCLEAR REGULATORY Coll!GSS'.Ol' Walter R. Butler, Chief Licensing Branch ho. 2 Division of Licensing Encicsure:
Changes to the Technical Specif icatior.s Date of Issuance:
October 1,1985
ENCLOSURE TO LICENSE AMENDMENT N0. 25 FACILITY OPERATIh6 LICEt.EE FO. NPF-11
~~IdEKET NO. 50-373 0
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised ficc is identified by Amendment ntnbcr a r.d contain a vertical line indic6tir.g the area of change.
REMOVE INSERT 3/4 5-4 3/4 5-4 l
l
I I
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.1 ECCS divisions 1, 2 and 3 shall be demonstrated OPERABLE by:
At least once per 31 days for the LPCS, LPCI and HPCS systems:
a.
1.
Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.
2.
Performance of a CHANNEL FUNCTIONAL TEST of the:
a)
Discharge line " keep filled" pressure alarm instrumentation, and b)
'ieader delta P instrumentation.
3.
Verifying that each valve, manual, power operated or automatic, in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
4.
Verifying that each ECCS corner room watertight door is closed, except during normal entry and exit from the room.
b.
Verifying that, when tested pursuant to Specification 4.0.5, each:
1.
LPCS pump develops a flow of at least 6350 gpm against a test line pressure greater than or equal to 290 psig.
2.
LPCI pump develops a flow of at least 7200 gpm against a test line pressure greater than or equal to 130 psig.
3.
HPCS pump develops a flow of at least 6250 gpm against a test line pressure greater than or equal to 370 psig.
For the LPCS, LPCI* and HPCS systems, at least once per 18 months:
c.
l 1.
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verifying that each automatic valve in the flow path actuates to its correct position.
Actual injection of coolant into the reactor vessel may be excluded from this test.
2.
Performing a CHANNEL CALIBRATION of the:
a)
Discharge line " keep filled" pressure alarm instrumentation and verifying the:
1)
High pressure setpoint and the low pressure setpoint of the:
- The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
LA SALLE - UNIT 1 3/4 5-4 Amendment No. 25
p ue
'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION n
5
.p WASHINGTON, D. C. 20555
's, p
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 13 License No. NPF-18 1.
The Nuclear Regulatory Connission (the Comission or the NRC) having found that:
1 A.
The application for amendrient filed by the Commonwealth Ecisen i
Ccrpany, September 23, 1985, cortplies with the standards and require-nents of the Atomic Energy Act of 1954, as amendeo (the Act), and the Comissicn's regulations set forth in 10 CFR Chapter I; I
B.
The facility v.i'1 crerete in conformity with the application, the i
provisicus of the Act, and the regulaticns of the Comission; L.
There is reasunable asst.rtrce:
(i) that the activities cuthcriac by this anendment can be conducted without endangering the health anc safety of the public, and (ii) that such activities will be 1
conducted in compliance with the Conuission's regulations set forth in 10 CFR Chapter 1; L.
The issuance of this ancndrert will not be inimical to the cu,ron defense and security or to the Fet!th and safety of the public; anc E.
The issuance of this amendment is in tccordance with 10 CFR Part 51 of the Comission's reculations and all applicable requiren,ents have been satisfiec.
i 2.
Accordingly, the license is amended by changes.to the Technicai 4
l Specifications as indicated in the attachnent to this license amendment and paragraph 2.C.(2) of Facility Operating License No. 18 is hereby I
amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendnent No. 13, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the
'acility in accordance with the Technical Specifications and the Environmental Protection Plan.
I i
i
Thi s Sr..enar,,en: 1s efrectist as of Scptember 26, 1985.
FOR THE NUCLEAR REGULATORY C0lu::5S;0h Ualter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
Changes to the Technical Specificatiers Date of Issuccce:
October 1,1985
ENCLOSilRE TO LICEliSE AftENDMENT NO.13~
FACILITY OPERATlf.G LICEh5E h0. hPF-18 DOCKET NO. 50-374 Replace the fellowing page of the Appendix "A" Technical Specifications with the cnclosed page. The revisec pese is identified by Amendment nurber erd certain a vertical line indicating the area of change.
REMOVE INSERT 3/4 8-4 3/4 8-4
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months
- during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.
2.
Verifying the diesel generator capability to reject a load of greater than or equal to 1190 kW for diesel generator 0, greater than or equal to 638 kW for diesel generators IA and 2A, and greater than or equal to 2381 kW for diesel generator 2B while maintaining engine speed less than or equal to 75% of the difference between nominal speed and the overspeed trip setpoint or 15% above nominal, whichever is less.
3.
Verifying the diesel generator capability to reject a load of 2600 kW without tripping.
The generator voltage shall not exceed 5000 volts during and following the load rejection.
4.
Simulating a loss-of offsite power by itself, and:
a)
For Divisions 1 and 2 and for Unit 1 Division 2:
1)
Verifying deenergization of the emergency busses and load shedding from the emergency busses.
2)
Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 13 seconds, energizes the auto-connected loads and operates for greater than or equal to 5 minutes while its generator is so loaded.
After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 1 150 volts and 60 1 1.2 Hz during this test.
b)
For Division 3:
1)
Verifying deenergization of the emergency bus.
2)
Verifying the 'liesel generator starts on the auto-start signal, energizes the emergency bus with its loads with-in 13 seconds and operates for greater than or equal to 5 minutes while its generator is so loaded. After energization, the steady-state voltage and frequency of the emergency bus shall be maintained at 4160 t j
150 volts and 60 1 1.2 Hz during this. test.
i 5.
Verifying that on an ECCS actuation test signal, without loss-of-offsite power, diesel generators 0, 2A, and 28 start on the auto-start signal and operate on standby for greater than or equal to 5 minutes.
The generator voltage and frequency shall be 4160 + 416, -150 volts and 60 + 3.0, -1.2 Hz within 13 seconds after the auto-start signal; the steady-state generator voltage and frequency shall be maintained within these limits during this test.
^The specified 18 month interval may be waived for Unit 1, Cycle 1, provided the surveillance is performed during Unit 1, Refuel 1.
l LA SALLE - UNIT 2 3/4 8-4 Amendment No.13
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