ML20096B203
| ML20096B203 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/03/1996 |
| From: | Latta R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20096B209 | List: |
| References | |
| NUDOCS 9601160101 | |
| Download: ML20096B203 (4) | |
Text
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k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20se6-0001
'+4 * * * *
- 4 t
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 2, 1995, complies with the standards and requ'rements of the Atomic Energy Act of 1954, as amended he Act), and the Comission's regulations set forth in 10 CFR r' cer 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 j
by this amendment can be conducted without endangering the health 1
and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations set I
forth in 10 CFR Chapter I; 1
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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable l
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:
l l
9601160101 960103 PDR ADOCK 05000373 p
PDR l
~.
' (2)
Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 108, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
i The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i 3.
This amendment is effective upon date of issuance and shall be implemented prior to the restart of Unit I from its seventh refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION h
Y
'2' Robert M. Latta, 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: January 3, 1996 4
ATTACHMENT TO LICENSE AMENDMENT N0. 108 FACILITY OPERATING LICENSE NO. 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 contains vertical lines indicating the area of change.
REMOVE INSERT 3/4 4-5 3/4 4-5' l
REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of 17 of the below listed 18 reactor coolant system safety / relief valves shall be OPERABLE with the specified code safety valve function lift setting *#; all installed valves shall be closed with OPERABLE position indication.
a.
4 safety / relief valves 01205 psig i3%
b.
4 safety / relief valves 01195 psig i3%
c.
4 safety / relief valves 91185 psig f3%
d.
4 safety / relief valves 91175 psig i3%
e.
2 safety / relief valves 91150 psig 13%
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With the safety valve function of one or more of the above required 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 position.
c.
With one or more of the above required 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 SHUTDOWN 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:
a.
CHANNEL CHECK at least once per 31 days, and 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.
Following testing, lift settings shall be within 11%.
- 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 surveillance 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.
LA SALLE - UNIT 1 3/4 4-5 Amendment No. 108