ML20237H060

Amend 8 to License DPR-21,revising Tech Specs to Allow CRD Removal & Repair or Replacement W/Reactor Vessel Head on, Cavity Not Flooded & Spent Fuel Pool Gates in Place

ML20237H060
Person / Time
Site:	Millstone
Issue date:	08/14/1987
From:	Thomas C Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237H057	List: ML20237H054 ML20237H060 ML20237H070
References
NUDOCS 8709030103
Download: ML20237H060 (4)

Text

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1. 'o g UNITED STATES 8, o NUCLEAR REGULATORY COMMISSION g nE WASHINGTON, D. C. 20555 -

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• e NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT-NO. 1 AMENDMENT TO FACILITY OPERATING EICENSE Amendment No. 8 License No. DPR-21 )

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1. The Nuclear Regulatory Commission (the Commission) has_found that: )

A. The application for amendment by the Northeast Nuclear Energy Company, (the licensee) dated August 11, 1987 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; i

B. The facility will operate in conformity with the application, the provisions of~the Act, and the rules and regulations of the .<

Commission; j 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 regulations and all applicable requirements have been satisfied.

8709030103 870814 DR ADOCK OS0 g 5 .

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2. Accordingly, the license is amended by changes to the Technical-Specifications as indicated in.the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating ' License No. DPR-21'is hereby amended to read as.follows: '

(2) Technical Specifications The Technical Specifications' contained in Appendix A, as evised through Amendment No. 8, are.hereby incorporated in the license. The licensee shall operate the facility'in accordance with the Technical. Specifications, j

3. - This license amendment is effective as of the date of its issuance, j FOR THE NUCLEAR REGULATORY COMMISSION.

b8 0, Wk w Cecil 0. Thomas, Director 1 Integrated Safety Assessment 1 Project Directorate k Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: Aug.ust 14, 1987 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Revise Appendix A Technical Specifications by removing the page indentified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contain a marginal line indicating the area of change.

REMOVE INSERT Page 3/4 5-9 Page 3/4 5-9 9

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1 LIM 1?ING CONDITION FOR OPERATION 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 3.5.F.7. When irradiated fuel is in the reactor vessel and the reactor is in the REFUEL CONDITION, a single control rod may be withdrawn and the drive mechanism replaced or fuel removal and replacement may be conducted provided that the following conditions are satisfied.

(a) The reactor vessel head is removed.

(b) The cavity is flooded. -

(c) The spent fuel pool gates are removed.

(d) Water level is maintained within the limits of Specification 3 10.C.

j (e) Either (1) both core spray systems, (ii) both low pressure coolant injection systems or (iii) one core spray system ,

and one low pressure coolant injection system, each j combination being supplied by independent electrical power, shall be operable or available for operation with the respective 4160 volt supply breaker (s) racked out.

( f) With the torus drained, -(i) the ECCS configuration required in 3.5.F.7(e) shall be aligned with the condensate storage tank and the condensate storage tank suction valve V7-58 locked open, (ii) the condensate storage tank shall contain 1 at least 414,000 gallons of usable water.. ')

(g) The minimum electrical power source requirements shall be the same as specified in paragraph 3 7.B.4. 1 (h) No work will be performed in the reactor vessel other than fuel sipping while a control rod drive housing is open.

(i) Fuel removal and replacement will not be done without a full complement of control rods.

(j) During fuel movement, no work being done which has the, .!

potential for ' draining the vessel. '

(k) For purposes of control rod drive mechanism removal and/or j replacement, specifications 3.5.F.7(a), (b) and (c)'do not apply provided ECCS systems identified .in 3.5.F.7(e) are operable with the 4,160 volt supply breaker (s) racked in.

Millstone Unit 1 3/4 5-9 Amendment No. 2, 8

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