ML20133K200

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Application for Amend to License DPR-3,revising Tech Specs to Accommodate Mods to RCS Vent Sys Valve Power Supplies.Fee Paid
ML20133K200
Person / Time
Site: Yankee Rowe
Issue date: 10/15/1985
From: Heider L
YANKEE ATOMIC ELECTRIC CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20133K203 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM FYR-85-110, NUDOCS 8510210119
Download: ML20133K200 (3)


Text

r YANKEE ATOMIC ELECTRIC COMPANY Tc':pho"e(6")*'

00 TWX 710-380-7619 1671 Worcester Road, Framingham, Massachusetts 01701 2 C.15.1 v E_,iy FYR 85-110 8 / N K il h.

PC # 195 October 15, 1985 United States Nuclear Regulatory Comission Washington, DC 20555 Attention:

Office of Nuclear Reactor Regulation

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b) YAEC Letter to USNRC, dated April 17, 1984 (c) YAEC Letter to USNRC, dated April 30, 1985 Subj ect:

Request for Change to Technical Specifications 3/4.4.11 and 3.4.11 Main Coolant System Vents

Dear Sir:

Pursuant to Section 50-59 of the Commission's Rules and Regulations, the Yankee Atomic Electric Company hereby requests the authorization to make the following changes:

PROPOSED CHANGE Reference is made to the Proposed Change 183 to the Technical Specifications of License No. DPR-3..

This change was submitted for staff review by Reference (b).

We propose to modify the license as follows:

1.

Replace Page 3/4 4-39 with the attached revised Page 3/4 4-39, 2.

Replace Page B 3/4 4-13 of the Bases Section with the attached revised Page B 3/4 4-13.

REASON AND BASIS FOR CHANGE These Technical Specification changes are necessary to accommodate modifications to the power supplies of the Reactor Coolant System Vent System valves comitted to by Yankee Atomic Electric Company in Reference (c).

The reactor head vent line and pressurizer vent line are each isolated with two motor-operated valves in series: VD-MOV-559 and 561, and PR-MOV-558 and 560, respectively. As discussed in Attachment (b) of Reference (c), a 8510210119 051015 Qh$ d'h PDR ADOCK 05000029 P

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United States Nuclear Regulatory Commission October 15, 1985 Attention: Office of Nuclear Reactor Regulation page 2 fire affecting the control cables of these valves can cause an inadvertent actuation if power is available to the motor operators. Therefore, to insure the valves remain closed, power will be normally removed from all four valve operators. However, this will first require relocating the power supplies for all four valves to the Switchgear Room. This area is accessible after an accident requiring operation of these valves so that power can be resupplied to the valve operators when they are required to operate.

This modification and Technical Specification change will satisfy the following NRC criteria:

1.

All four valves will be powered from emergency buses as required by NUREG-0737, Item II.B.1.

2.

Power will be normally removed from these circuits so that a fire affecting them will not cause an inadvertant opening of two valves and the resultant loss of coolant, as required by Section III.G of Appendix R to 10CFR50, 3.

The power supplies for all four valves will le located in the Switchgear Room which is accessible following the accident they were designed to operate for, per NURgG-0737, Item II.B.1.

SAFgTY CONSIDgAATION The significant hazards consideration is based on the guidance provided by example in 48FR14870. The change described herein is classified according to the following examples of actions involving no significant hazards:

(1) A change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in keeping with the regulations.

The above change represents an additional operational requirement not presently included in the Technical Specification. However, this change ensures that the Reactor Coolant System Vent System valves remain closed to prevent an uncontrolled loss of primary coolant.

Based on the consideration contained herein, it is concluded that there is reasonable assurance that operation of the Yankee plant consistent with the proposed Technical Specification will not endanger the health and safety of the public. This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.

FEE DETERMINATION An application fee of $150.00 is enclosed in accordance with 10CFR170.21.

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United States Nuclear Regulatory Connaission October 15, 1985 Attention: Office of Nuclear Reactor Regulation Page 3 SCHEDULE OF CHANGE These changes to the Yankee Technical Specification will be implemented upon comunission approval. A timely review and approval of this submittal consistent with our schedule for Core XVIII would be appreciated. The refueling outage is scheduled to conunence on or about October 19, 1985.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY Y

M L. H. Heider Vice President / Manager of Operations LNH/glw r

C00000NWEALTH OF MASSACHUSETTS)

)ss MIDDLESEK COUNTY

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Then personally appeared before me, L. H. Heider, who, being duly sworn, did state that he is Vice President / Manager of Operations of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Yankee Atomic Electric Company and r

that the statements therein are true to the best of his knowledge and belief.

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h Robert H. Groce Notary Public My Conunission Expires August 29, 1991 f

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