ML20155F811
| ML20155F811 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/24/1988 |
| From: | Norrholm L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155F815 | List: |
| References | |
| NUDOCS 8806170062 | |
| Download: ML20155F811 (8) | |
Text
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l 41 UNITED STATES O
NUCLEAR REGULATORY COMMISSION j
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COMMONWEALTH EDIS0N COMPANY DOCKET NO 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated March 9,1988 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 confonnity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (1) 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 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 Comission's regulations and all applicable requirements have been l
satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the enclosure to this license amendment and para-graph 2.C.(2) of the Facility O'perating License No. NPF-11 is hereby amended to read as follows:
i (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 57, 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 Specif1-I cations and the Environmental Protection Plan.
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This amendment is effective on the date of issuance.
FOR THE N EAR REGULATORY COMMISSION
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b elf tor Proje t Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: May 24, 1988
ENCLOSURE TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE N0. NPF-11 DOCKET NO. 50-373 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and centains a vertical line indicating the area of change.
REMOVE INSERT 3/4 8-4 3/4 8-4
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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 j
than or equal to 638 kw for diesel generators lA and 2A, and greater than or equal to 2381 kw for diesel generator 1B 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 2 Division 2:
1)
Verifying de-energization 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 ivaded.
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 de-energization of the emergency bus.
2)
Verifying the diesel 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 1 150 volts and 60 1 1.2 Hz during this test.
5.
Verifying that on an ECCS actuation test signal, without loss of offsite power, diesel generators 0, 1A and IB 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 shali be maintained within these limits during this test.
- The specified 18 month interval may be waived for Unit 2 Division 2 provided l
the surveillance is performed during Unit 2 Refuel 2.
LASALLE-UNIT 1 3/4 8-4 Amendment No.
57
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h NUCLEAR REGULATORY COMMISSION 1;
qj WASHINGTON, D. C. 20555 44.....,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.
38 License No. NPF-18 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated March 9, 1988, 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
-provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by i
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 It 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the enclosure to this license amendment and para-graph 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 No. 38, and the Environmental Protection <lan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifi-cations and the Environmental Protection Plan.
2-3.
This amendment is effective on the date of issuance.
FOR THE N CL REGUL ATORY COMMISSION A
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teifJ!,frh m,Actir.g Director Project DTrectorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: May 24, 1988
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ENCLOSURE TO LICENSE AMENDMENT N0. 38 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET N0. 50-374 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
REMOVE INSERT 3/4 0-2 3/4 0-2 l
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APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirements.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to axceed 25% of the surveillance interval, but b.
The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.*
l 4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual Specifications.
Surveillance requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:
Inservice inspection of ASME Code Class 1, 2, and 3 components and a.
inservice testing of ASME Code Class 1, 2, and 3 pumps and vai.es shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by
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10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days
- Not applicable to 18 month surveillances required for Unit 2 Cycle 2 operation.
LA SALLE - UNIT 2 3/4 0-2 Amendment No. 38
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