ML20148J158

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Safety Evaluation Supporting Amend 10 to License DPR-3
ML20148J158
Person / Time
Site: Yankee Rowe
Issue date: 11/27/1974
From: Burger A, Purple R
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20148J149 List:
References
NUDOCS 8011210218
Download: ML20148J158 (2)


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4 UNITED STATES .E l- l ,] r-)h ,,5 , ATOMIC ENERGY COMMISSION -

k WASH I N GTON. D.C. 20545 I"E naen e . .

c SAFETY EVALUATION BY THE DIRECTORATE OF LICENSING

/ SUPPORTING AMENDMENT NO.10 TC FACILITY LICENSE NO. DPR-3 .._,y (CHANGE NO.115 TO THE TECHNICAL SPECIFICATIONS) ... .g ,

' YANKEE'ATOMTC, ELECTRIC COMPANY

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YANKEE-ROWE ATOMIC POWER PLANT E...

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Introduction , . . . . . , _

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By Ictters dated'May 13, 1974, September 5, 1974, and October 4, 1974, 5 Yankee Atomic Electric Company requested changes to the Technical'Spect- yjs-fications appended to Facility Operating License No. DPR-3 for Yankee Rowe Nucicar Power Station. The proposed. change involves the addition of limiting conditions for operation (LCO) and the surveillance require-ments for the new diverse emergency core coolant injection actuation channels.

Discussion .

G By letters dated September 14, 1973, and supplemented by letters dated I January 16 and 31, 1974, Yankee Atomic Electric Company (licensee) pro-posed the installation of an additional signal source to provide a diversity of signals for actuating.the Yankee Rowe Emergency Core Ccoling System (ECCS). The proposed signal consisted of two separate containment pressure sensing channels which would be combined in a one-out-of-two logic to actuate the ECCS should the containment pressure reach 5 psig.

These pressure channels were installed and put into operation during the May 1974 refueling outage.

The setpoint for the new channels is presently at 5 psig.

Our letter of March 5,1974, approved the installation of this equipment and concluded that it was in conformance with IEE Standard 279. We also =

requested, at that time, that the licensee submit appropriate limiting ~"

conditiens for operation and surveillance requirements for the Yankee Rowe Technical Specifications. By letter dated May 13, 1974, supplemented by letters dated September 5, 1974, and October 4, 1974, the licensee fur-nished the proposed technical specifications as requested.

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The establishment of 5 psig seepoint'as the LCO for the containment r =

/ overpressure signal was reviewed and approved by the staff in conjunc- , p:

tion with our approval of the installation (cur letter of March 5,1974).

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The proposed surveillance requirements include the following: (1) A l" channel check each shift, (2) A monthly operational check of the two containment' air pressure switches, and (3) A channel calibration and a e-channel functional test at each refueling. We find this acceptable. ~ll,,_

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This change, which administrative 1y incorporates the LCO and surveillance  : '

requirements for the new system in the Yankee Rowe Technical Specifications, E l will not increase the probability or consequence of an accident and '

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will not decrease any margin'of, safety. :jjj

3 Conclusion -

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We have concluded based on the reasons discussed above that the authorization [

of t'!s change'.does not involve a significant hazards consideration. We als' >nclude that there is reasona.ble assurance (1) that the activities aut. :1 zed by this amendment can be conducted without endangering the

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her* h and safety of the public and (ii) that such activities will~ be ccac cted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common deferse and security or to the health and safety of the public.

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AlfredBurg[r We fb E

Operating Reactors Branch #1 '

Directorate of Licensing g.

Robert A. Purple, Chief f::/

Operating Reactors Branch #1 $ ,1 Directorate of Licensing

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. Date: November 27, 1974 p

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