ML19290A318
| ML19290A318 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/15/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A317 | List: |
| References | |
| NUDOCS 7911060558 | |
| Download: ML19290A318 (5) | |
Text
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- r UNITED STATES y s.
yt NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20555
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1 AMENCMENT TO FACILITY OPERATING LICENSE Anendment No. 21 License No. OPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (the licensees) dated June 17, 1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and 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; 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 Specifications as indicated in the attachment to this license amendment.
1555 221 7911060 F 8
2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q.A~O44 0 U Robert V. Reid, Chief Opsrating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: September 15, 1976 1555 222
h ATTACHMENT TO LICENSE AMENDMENT N0. 21 FACILITY OPERATING LICENSE N0. OPR-50 DOCKET N0. 50-289 Remove pages 3-21 and 3-22 from the Appendix A Technical Specifications and insert the attached replacement pages. The changed areas on the revised page are shown by marginal lines.
Page 3-22 is unchanged and is included for convenience only.
1555 223
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Annlienbility UI Applies to the operating status of the emergency core cooling, reactor building emergency cooling, and reactor building spray systems.
Chiective To define the conditions necessary to assure i= mediate availability of the emergency core cooling, reacter building emergency cooling and reactor building spray systems.
Srecification 3.3.1 The reactor shall not be made critical unless the fol1cving conditions are met:
3.3.1.1 Injection systems a.
The borated water storage tank shall contain a minimum of 350,000 gallons of water having a minimum concentratien of 2,270 ppm boron at a temperature not less than h0 F.
b.
Two makeup pumps are operable in the enginee ed safeguards mode povered from independent essential busses.
c.
Two decay heat removal pumps are operable.
d.
Two decay heat re= oval coolers and their cooling vster supplies are operable.
(See Specification 3.3.1.h) e.
Two BWST level instrument channels are operable, f.
The two reactor building sump isolation valves (DHV6A/B) shall be either manually or remote-manually oprable.
3.3.1.2 Core Floodina System 3
a.
Two core flooding tanks each containing 10h0 ! 30 ft of berated water at 600 1 25 psig shall be available, b.
Core flooding tank boron concentration shall not be less than 2,270 ppm boron.
c.
The electrically operated discharge valves from the core flood tank vill be assured open by administrative control and position indication lamps on the engineered safeguards status panel.
Respective breakers for these valves shall be open and con-spicuously marked.
d.
One ecre fleed tank pressure instrumentation channel and one core flood tank level instrumentation channel per tank shall be operable.
1555 224 3-21 Amendment No. 21
- 3. 3.1. 3 Reactor Building Soray System and Reactor Buildine Emer ency Cooling System The following components =ust be operable:
Two reactor building spray pu=ps and their associated spray a.
nozzles headers and two reactor building emergency cooling fans and associated cooling units (one in each train).
b.
The sodium thiosulfate tank shc11 contain not less than 3h,000 pounds of sodiu= thiosulfate and not more than 36,000 pounds of sodium thiosulfate. The sodium thiosulfate vill be stored at a nominal 30 veight percent solution with no=inal 1.5 weight percent boric acid-sodium hydroxide buffer at a pH of approxi=ately 9 to 10.
The sodium hydroxide tank shall contain not less than 16,000 pounds of sodium hydroxide and not more than 17,000 pounds of sodium hydroxide. The sodit= hydroxide vill be s*wred at a nomial 20 veight percent solution, All manual valves in the discharge lines of the sodiua thiosulfate c.
and sodium hydroxide tanks shall be locked open.
- 3. 3.1.h Cooling Water Syste=s Two nuclear service closed cycle cooling water pu=ps must be a.
b.
Two nuclear service river water pu=ps must be operable.
Two decay heat closed cycle cooling vater pu=ps must be operable, c.
d.
Two decay heat river water pu::ps must be operable, Two reactor. building emergency cooling river water pu=ps =ust be e.
3.3.1 5 Engineered Safeguards Valves and Interlocks Associated with the Syste=s in Specifications 3 3.1.1, 3 3 1.2, 3 3.1. 3, 3 3.1.h are operable.
3 3.2 Maintenance shall be allowed during power operation on any co=ponent(s )
in the makeup and purification, decay heat, RB e=ergency cooling vater, R3 spray, CW pressure instru=entation, CK level instru=en-tation, BWST level instru=entation, or cooling water syste=s which vill not re=ove more than one train of each system frem service.
Co=ponents shall not be removed from service so that the affected system train is inoperable for more than k3 consecutive hours. If the system is not restored to meet the requirements of Specifications 3.31 within LS hours, the reactor shall be placed in a cold shutdovn condition within tvelve hours.
1555 225 3-22