ML19345A494

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Submits Proposed Change 116 to Tech Specs,Amending Safety Injection Sys Paragraph of Section 509 to Include Comparision of Separate Pressure Indication by Each Shift & Calibr & Functional Testing for Refueling
ML19345A494
Person / Time
Site: Yankee Rowe
Issue date: 09/05/1974
From: Heider L
YANKEE ATOMIC ELECTRIC CO.
To:
US ATOMIC ENERGY COMMISSION (AEC)
References
WYR-74-21, NUDOCS 8011210761
Download: ML19345A494 (4)


Text

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S.ropond Changs No. 116

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.pplemnt No.1 Telephone 617 366 9011 rwx 710-390-0739 YANKEE ATOMIC ELECTRIC COMPANY wa 74-11 710 20 Turnpike Road Westborough, Massachusetts 01581

.YAAKElE September 5, 1974

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United States Atomic Energy Con: mission 7

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20545 Attention: Directorate of Licensing

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Reference:

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

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2) Yankee Atomic Electric Company Proposed Change No. 111, Diverse Initiation of Safety Injection

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3) Yankee Atomic Electric Company Proposed Change No 116,

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43 Revision of Technical Specifications and Proposed Final Safety Analysis Report M

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4) Telephone conversation with Mr. Leo McDonough on g

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Dear Sir:

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Reference No. 2 transmitted revisions and additions to sections of t

[77; current Technical Spa.cifications and the Proposed Final Safety Analysis Report. As was discussed with Mr. McDonough (Ref. 4) Table 1 as submitted was incorrect in that it did not agree with Table 1 of the approved change 111. Please delete it from the Proposed Change No. 116.

In Proposed Change No. 116 (Ref. 3) we did not submit a revision to our current Technical Specifications to describe the Surveillance Require-ments for the two containment pressure switches added in Reference 2.

Paragraph D.2.I, Routine and Continuous Tests, of Appendix "A" Yankee Atomic Electric Company Technical Specifications reads as follows: " Routing and periodic tests shall be made at the times and in the manner set forth in Section 509 of the license application".

Section 509 is arranged in paragraphs devoted to particular subjects and prescribes the routine tests that will be accomplished for the subject.

We propose to amend the " Safety Injection System" paragraph of Section 509 as follows:

Surveillance of the Safety Injection Actuation Signal (SIAS)

Initiation Channels will include:

1.

a comparison of the separate pressure indications by each shift; 2.

a channel calibration each refueling by applying known pressures to each sensor; 3.

a system functional test each refueling by application of test signals to each channel to verify system capability.

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8011210 76(

REGULAT RY DOCKET FILE COPY s

Unittd States Atomic Enrrgy Commission Ssptsmbsr 5, 1974 Attn: Directorate of Licensing Pegn Two We are ir:luding with this Supplement the pertinent page from Section 509 as amende. to include the above proposed sentence.

We trust you will find this information satisfactory; however, should you desire additional information feel free to contact us.

Respectfully submitted, YANKEE ATCMIC ELECTRIC COMPANY Louis H. Heider Assistant Vice Presidenc LHH/kg COMMONWEALTH OF MASSACHUSETTS)

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COUNTY OF WORCESTER

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Then personally appeared before me, Louis H. Heider, who, being duly sworn, did state that he is Assistant Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the fore-going request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his knowledge and

belief, h

/T EM Armand R. Soucy Notary Public My Commission Expires September 9, 1977

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Safety Iniection System - Weekly, during power operation, all of the pumps in the safety injection system will be operated individually from the safety injection control panel in the control room to detemine their serviceability and correct light position indication. The pumps will be operated only on by-pass to the safety injection-shield tank cavity water storage tank. Monthly, the pumps will be operated as in the weekly test plus the loop fill valves will be opened witn the injection valve closed tight. All locked-open and locked-closed valves outside the vapor container will be checked at the conclusion of the tests to verify their correct position.

During refueling when the reactor plant is shutdown and depressuri:cd, the entire safety injection system will be checked in the automatic and manual mode of operation to verify the operation of the safety injection control switches provided on the nuclear section of the main control board. Surveillance of the Safety Injection Actuation Signal (SIAS) Initiation Channels will include:

1. a comparison of the separate pressure indications by each shift; 2. a channel calibration each refueling by applying known pressures'to each sensor; 3. a system functional test each refueling by application of test signals to each channel to verify system capability.

Pressurizer Soray System - In order to assure reliable perfomance, the pressurizer surge and circulation spray systems will be tested periodically, preferably during the normal start operation. hhile maintaining normal operating ccnditions in the main coolant system and the pressure control and relief system, that is with surge spray deenergized, it is detemined that correct circulation spray exists (hand control valve initially positioned so as to maintain pressurizer equilibrium conditions) by noting frequency of heater cycling while maintaining pressuri:er at nomal values.

Verification of the motor operated surge spray will be accomplished by obtaining maximum spray flow and observing the resultant pressurizer pressure decrease, temperature increase of water flowing through the surge line. This valve is operated on plant cooldowns to collapse the pressurizer bubble.

Pressurizer Solenoid Relief Valve - The pressurizer solenoid relief valve, which is provided to limit the duty of the pressurizer safety valves, will be tested after any maintenance on this valve.

Pressurizer Cede Safety Valves - The pressuriner code safety valves will be tested at each refueling.

The valves will be removed from the pressurizer and mounted on a test stand.

A leak test will be conducted while increasing the pressure to the

, pop point of the valve. The set pressure shall be verified to be correct, after the valve has been lifted a final leak test is conducted with the use of a water manometer on the valve discharge.

Scram Alams Check Points and Instrumentation Calibration Checks - In order

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to assure safe operation of the plant, certain instrumentation checks will be performed periodically. Only those checks that can be made without disconnecting the scram circuit during plant operation will be perfomed. No tests or checks will-be made on any equipment if there is a possibility of initiating a false scram. All calibra-tion will be made before starting or during scheduled shutdown periods, except where-calibration is required at a power level.

Proposed Change No. 116 September, 1974

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EUCLCSURES:

Ltr re their Proposed change #116 to the Tech Corrections to change #116...re tables &

Specs trans the following.....

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