ML20031A607
| ML20031A607 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/08/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031A605 | List: |
| References | |
| NUDOCS 8109240210 | |
| Download: ML20031A607 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
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~THE CONNECTICUT LIGHT AND POWER COMPANY, THE HARTFORD ELECTRIC LIGHT COMPANY, WESTERN MASSACHUSETTS ELECTRIC COMPANY, AND NORTilEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 78 i
License No. DPR-21 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
73.e applicatio.n for amendment by the Connecticut Light and Power Company, The Hartford Electric Light Ccmpany, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated September 9,1980, complies with the standards and requirements of the A_tomic 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 confo riity 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 j
health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; l
D.
The issuance of this amendment will not be inimical to the con.:.an 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.
8109240210 010900' PDR ADOCK 05000245 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.8 of Provisional Operating License No. OPR-21 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78, are hereby incorporated in the license. Northeast Nuclear Energy Compar.y shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR t 'E NUCLEAR REGULATORY COMMISSION sptNt k *
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Dennis M. Crutch ield, hie t
Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 8, 1981 f
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I ATTACHMENT TO LICEflSE AMENDMENT NO. 78 PROVISI0flAL OPERATIflG LICENSE NO. OPR-21 DOCKET NO. 50-245 Replace Page 3/41-1 of Appendix A Technical Specifications with the enclosed page 3/4 1-1.* This revised page contains the captioned amendment number and vertical lines indicating the area of change.
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- 0verleaf page 3/41-2 also included.
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.1 REACTOR PROTECTION SYSTEf1 4.1 REACTOR PROTECTION SYSTEM Applicability:
Applicabili ty:
Applies to the instrumentation and associated devices Applies to the surveillance of the instrumentation ~
which initiate a reactor scram.
and associated devices which initiate reactor scram.
Objective:
Objective:
To assure the operability of the reactor protection To specify the type and frequency of surveillance system.
to be applied to the reactor protection instrumenta tion.
Specification:
Specification:
The setpoints, mininum number of trip systems, and minimum number of instrument channels that must be A.
Instrumentation systems shall be functionally operable for each position of the reactor mode tested and calibrated as indicated in-switch shall be as given in Table 3.1.1.
Tables 4.1.1 and 4.1.2, respectively.
The time from initiation of any channel. trip to the B.
Daily during reactor power operation, the peak de-energization of the scram solenoid relay shall heat flux shall be checked and the APRM scram j
not exceed 50 milliseconds.
and rod block settings given by the equations in Specifications 2.1.2A and 2.1.28 shall be determined.
Amendment No. 78 3/A 1-1
TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS Minimum Number
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of Operable Modes in wnich Function Inst. Channels Trip Function Trip Level Setting Must Be' Operable Action
- p.er Trip-(1)
Refuel (8)
Startup/ Hot System Standby Run s
1 Mode Switch in Shutdown X
X X
A 1
Manual-Scram X
X X
A IRM:
3 High Flux 1 120/125 of full scale X
X (5)
A 3
Inoperative A.
HI Voltage < 80 volt DC X
X X (10)
A B.
IRH Module Unplugged C.
Selector Switch not in Operate Position APRM:
2 Flow Biased High Flux See Section 2.1.2A X
X X
A or B 2
Reduced High Flux See Section 2.1.2A X
X X
A or B 2
Inoperable A:
> 50% LPRM Inputs **
X X
X A or B B.
Circuit Board Removed C.
Selector Switch not in Operate Position 2
High Reactor Pressure 1 1085 psig X
X 3
X A
2 High Drywell Pressure 1 2 psig X (9)
X (74 X (74 A
l 2
Reactor Low Water Level
> 1.0 inch ***
X X
X A
l 2
Scram Discharge Vol.
1 39 gallons X (2)
X X
A High. Level l
l Amendment No. 34 November 19, 1976 3/4 1-2
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