ML20079M096
| ML20079M096 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/29/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20079M099 | List: |
| References | |
| DPR-35-A-073 NUDOCS 8401270175 | |
| Download: ML20079M096 (4) | |
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UNITED STATES y?, ~' j7 j NUCLEAR REGULATORY COMMISSION 3 'K
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BOSTON EDIS0N COMPANY DOCKET N0. 50-293 PI'. GRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated April 5, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 (i) 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 reculations and all applicable recuirements have been satisfied.
2.
Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
8401270175 831229 PDR ADOCK 05000293 P
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. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
73, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Chanoes to the Technical Specifications Date of Issuance: Deceuber 29, 1983 t
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ATTACHMENT TO LICENSE Af1ENOMENT NO. 73 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET N0. 50-293 i
Replace the following page of the Appendix "A" Technical Specifications with the enclosed pace.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Remove Insert 22 22 4
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1.2 SAFETY LIMIT 2.2 LIMITING SAFETY SYSTEM SETTING 1.2 REACTOR COOLANT SYSTEM INTEGRITY 2.2 REACTOR C0OLANT SYSTEM INTEGRITY Applicability:
Applicability:
Applies to limits on reactor Applies to trip settings of the in-l coolant system pressure.
struments and devices which are pro-vided to prevent the reactor system safety limits from being exceeded.
Objective:
Objective:
To establish a limit below which To define the level of the process the integrity of the reactor cool-variables at which automatic pro-ant system is not threatened due tective action is initiated to to an overpressure condition.
prevent the pressure safety limit from being exceeded.
Specification:
Specification:
The reactor vessel dome pressure The limiting safety system settings shall not exceed 1325 psig at any shall be as specified below:
time when irradiated fuel is pre-sent in the reactor vessel.
Limiting Safety Protective Action System Setting A.
Scram on Re-1085 psig actor Vessel high pressure B.
Relief / Safety Nominal setpoint valve settings will be selected'be-tween 1095 and 1115 psig. All valves shall be set at this nominal setpoint +--
11 psi.
C.
Safety valve 1240 psig + 13 psi settings Auendment No. 73 22