ML19274D455
| ML19274D455 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/12/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19274D454 | List: |
| References | |
| NUDOCS 7902010190 | |
| Download: ML19274D455 (5) | |
Text
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U!t:TED STATES NUcLsAR REGULATORY COMMISslCN W ASHINGToN, D. C. 20555
%* - +.( j CONNECTICUT LIGHT AND POWER COMPANY THE. HARTFORD. ELECTRIC LIGHT COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPANY NORTHEAST NUCLEAR E!4ERGY COMPANY DOCKET N0. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDi'.ENT TO PROVISIONAL OPERATING LICENSE Amendment No. 58 License No. DPR-21 1.
The *:uclear Regulatory Commission (the Cornission) has found that:
A.
The application for amendment by Connecticut Light and Power Company, The Hartford Electric Light Compary, Western Massachusetts Electric Company, and the Northeast Nuclear
~
Energy Company (the licensees) dated March 15, 1978, 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 1; 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 sill not be inimical to the common defense and security or to the health and safety of thc public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Ccamissi<m's regulations and all applicable requirements have been satisfied.
7902010/90
4 Accordi gly, the license is amended by changes to the Technical 2.
n Specifications as indicated in the attachment to this license amencment and paragraph 3.B of Provisional Operating License No.
DPR-21 is hereby amended to read as follows:
B.
Technical Soecifications~
The Technical Specifications contcined in Appendices A and B, as revised through Amendment No. 58, are hereby incorporated in the license. The licensees shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ef fective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Dennis L. Ziemann, Chief Operating Reactors Branch #2 I
Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: January 12, 1979 e
ATTACHMENT TO LICENSE AMENDMENT NO. 58 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Remove the following page of the Appendix "A" Technical Specifications and insert the enclosed page. The revised page contains the captioned amendment number and a vertical line indicating the area of change.
Overleaf page (3/4 7-10) is provijed for document completeness.
Remove Insert 3/4 7-9 3/4 7-9*
- Please note that the specificatian section number and +he page number as proposed by the licensee have been changed to reflect revisions issued by Amendment No. 51, dated July 6,1978.
titilTli1G C0f4DITIO1 FOR OPERATI0ii SURVEILLAtlCE REQUIREMEllT 4.
Pressure suppression chamber - reactor (c) Any one main steam building vacuum breakers:
line isolation valve 11.5 scf/hr at 25 a.
Except as specified in 3.7.A.4.b psig.
below, two pressure suppression chamber-reactor building vacuum g.
Continuous leak rate monitor:
breakers shall be operable at all times when primary containment (1) When the primary containment integrity is required. The set-is inerted, the containment point of the differential pressure shall be continuously instrumentation which actuates the monitored for gross pressure suppression chamber-leakage by review of the reactor building vacuum breakers inerting system makeup l
shall be from 0.4 to 0.5 psid.
requirements.
b.
From and after the date that one of (2) This monitoring system the pressure suppression chamber-may be taken out of reactor building vacuum breakers is service for the purpose made or found to be inoperable for of maintenance or testing any reason, reactor operation is but shall be returned to permissible only during the suc-service as soon as ceeding seven days unless such practical.
vacuum braaPer is sooner made operable, provided that the repair h.
The interior surfaces of the procedure does not violate primary drywell shall be visually containment integrity.
inspected each operating cycle for evidence of deterioration.
4.
Pressure suppression chamber -
reactor building vacuum breakers:
a.
The pressure suppression chamber-reactor building vacuum breakers and associated instrumentation including setpoint shall be checked for proper operation every three months.
3/4 7-9 Amendment fio. 9, 57, 58