ML19345C896
| ML19345C896 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/17/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345C897 | List: |
| References | |
| NUDOCS 8012080573 | |
| Download: ML19345C896 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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BOSTON EDISON COMPANY DOCKET N0. 50-293 PILGRIM NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-35 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated October 31, 1980, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and 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 rules and Regulations of the Commission; 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 Commission's regulations; D.
The issuance of this amendment 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 51 of the Commission'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 attachment to this license amendment and paragraph 3.B of Facility License No. DPR-35 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44 are hereby incorporated in the license. The licensee shall operate the facility in accordance l
with the Technical Specifications.
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8012080671
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This license amendment is effective as of October 31, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION
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m ito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 17, 1980
ATTACH" INT TO LICENSE AMENDMENT N0. 44 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise Appendix A as follows:
Remove Insert 106 106 107 107
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LIMITING CONDITION FOR OPERATION SURVEILI.ANCE REQUIRD(ENT
~g-l *3.5.B Contairunent Cooling Subsystem 4.5.3 Containment Cooling Subsystem 1.
Except as specified in 3.5.3.2, 1.
Containment Cooling Subsystem Teating-3.5.3.3, and 3.5.F.3 below, shall be as follows:
both containment cooling subsystem Item _
Frequency loops shall.h operabia whenever irradiated fuel is in the reactor Pump & Valva Operability Once/3 months vassel and reactor coolant temper-a.
and Onee/ cycle stare is greater than 212*F, and I
from the Alternate prior to reactor startup from a Shutdown :;tation Cold Condition.
b..
Pump Capacity Test After pump Each RBCCU pump shall raintenance deliver 1700 gym at and every 70 ft. TDH.
Each SSWS 3 months pump shall deliver 2700 4.
gpm at 55 ft. TDH.
c.
Air test on drywe?.1 and Once/i years torus headers and nozzles
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- Conditional relief granted from this LCO
.EE for the period October 3t, 1980 through 2$7 November 7, 1980.
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Amendment No. 44 106
LIMITING CONDITION FOR OPERATION SURVEILIANCE REQUIREMENT
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l *3.5.B Containment Cooling subsystem 4.5.3 Containment Coolina subsystem (Cont'd)
(Cont'd) 2.
From and af ter the date that one 2
When one containment cooling subsystem containment cooling subsystem loop loop becomes inoperable, the operable is made or found to be inoperable subsystem loop and its associated for any raason, continued reactor diesel generator shall be demonstrated operation is permissible only during to be operable issnediately and the the succeeding seven days unless operabia containment cooling subsystem such subsystem loop is sooner made loop daily thereafter.
operable, provided that the other conta'inment cooling subsystem loop, including its associated diesel generator, is operable.
3.
If the requirements of 3.5.B can-I not be met, an orderly shutdown l
shall be initiated and the reac-l tor shall be in a Cold Shutdown i
Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
HPCI Subsystem 5$
1.
The HPCI Subsystem shall be oper-EEr able whenever there is irradiated 1.
HPCI Subsystem testing shall be per-fuel in the reactor vessel, reactor formed as fo11ews:
pressure is greater than 104 psig, a.
Simulated Auto-Once/ operating and prior.to reactor startup from a Cold Condition, except as speci-matic Actuation cycle find in 3.5.C. 2 and 3.5.C.3 below.
Test b.
Pump Operability once/ month and Once/ cycle from the Alternate Shut-down Station c.
Motor Operated Once/ month and Valve Operability Once/ cycle from the Alternate Shutdown Station g d.
Flow Rate at Once/3 months 1000 psig e.
Flow Rate at Once/ operating 150 psig cycle
- Conditional relief granted from this LCO am..
.?j[I for the period October 3L,1980 through g3 43 O
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- Fr November 7, 1980.
A=endment No. 44
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