ML20150A639

Amend 18 to License DPR-21,revising Tech Spec Section 3.5.C, Core & Containment Cooling Sys - Feedwater Coolant Injection Subsys, by Increasing Min Required Condensate Storage Tank Vol to 250,000 Gallons

ML20150A639
Person / Time
Site:	Millstone
Issue date:	06/27/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20150A621	List: ML20150A617 ML20150A639 ML20150A671
References
NUDOCS 8807080112
Download: ML20150A639 (5)

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1. p v Csa o, UNITED STATES

! 7. NUCLEAR REGULATORY COMMISSION g E WASHINGTON, D. C. 20666

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NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. DPR-21

1. The Nuclear Regulatory Commission (the Comission) has found that:

A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated August 17, 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; B. The facility will operate in conformity 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 l this amendment can be conducted without endangering the health and i 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 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 Comission's regulations and all applicable requirements have been satisfied, l

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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 an.coccd to read as follows:

(2) Technical Specifications The Techt.ical Specifications contained in Appendix A, as revised through Amendment No.18 , are hereby incorporated in the license.

The licr.asee shall oper. ate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of issuance.

F0P. THE NUCLEAR REGU TORY COMMISSION oh N . Stolz, Director Pr ject Directorate I-vision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 27,1988 I

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. ATTACHMENT TO LICENSE AMENDMENT N0.18 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by arendment number and contains vertical lines indicating the areas of change. The corresponding overleaf page is provided to maintain document completeness.

Remove , Insert 3/4 5-5 3/4 5-5

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LIMITING CONDITION FOR OPERATION 35 CORE AND CONTAINMENT COOLING SYSTEMS C. FWCI Subsystem

1. Except as specified in 3 5.C.3 below, the FWCI subsystem shall be operable whenever the reactor coolant temperature is greater than 3300F and irradiated fuel is in the reactor vessel.

2. There shall be a minimum of 250,000 gallons of useable water in the condensate storage tank for operation of the FWCI.

3 From and after the date that the FWCI subsystem is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days, unless such subsystem is sooner made operable, provided that during Juch seven days all active components of the Automatic Pressure Relief Subsystem, the core spray subsystems, LPCI subsystem, and isolation condenser system are operable.

4. If the requirements of 3 5.C cannot be met, an orderly shutdown shall be initiated and the reactor coolant temperature shall be less than 3300F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENT 4.5 CORE AND CONTAINMENT COOLING SYSTEMS C. Surveillance of FWCI Subsystems shall be performed as follows:

1. Item Frequency

a. Pump and valve Per Surveillance operability Requirement 4.13

b. Simulated Automatic Every refueling Actuation Test outage

2. Once a week the quantity of water in the condensate storage tank shall be logged.

Millstone Unit 1 3/4 5-5 Amendment No. 7,18

LIMITING CONDITION FOR OPERATION

' 3. 5 CORE AND CONTAINMENT COOLING SYSTEMS D. Automatic Pressure Relief (APR) Subsystems

, 1. Except as specified in 3.5.D.2 below, the APR subsystem shall be operable whenever the reactor coolant temperature is greater than 330'F and irradiated fuel is in the reactor vessel.

2. From and after the date that one of the four relief / safety valves of the automatic pressure relief subsystem is made or found to be inoperable when the reactor coolant temperature is above 330*F with irradiated fuel in the reactor vessel, reactor op'eration is permissible only during the succeeding seven days unless repairs are completed and the subsystem made fully operable and provided that during such time the remaining automatic pressure relief valves, FWCI subsystem, and gas turbine generator are operable.

3. If the requirements of 3.5.0 cannot be met, an orderly reactor shutdown shall be initiated and the coolant temperature shall be less than 330*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENT 4.5 CORE AND CONTAINMENT COOLING SYSTEMS D. Surveillance of the Automatic Pressure Relief Subsystem shall be performed as follows:

1. During each operating cycle, the following shall be performed:

a. A simulated automatic initiation of the system throughout its operating sequence, but excluding actual valve opening, and

b. With the reactor at low pressure, each relief valve shall be i

manually opened until valve operability has been verified by torus water level instrumentation, or by an audible discharge detected by an individual located outside the torus in the vicinity of each relief line, l

} 2. When it is determined that one safety / relief valve of the automatic pressure relief subsystem is inoperable, the actuation logic of the remaining APR valves and FWCI subsystem shall be demonstrated to be operable immediately and daily thereafter.

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Millstone Unit 1, 3/4 5-6