ML20002C767

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Responds to AEC Re Violations Noted in Insp Rept 50-155/73-01.Asserts That Tech Specs Requirement Met If One Emergency Condenser Loop Operable & Available for Automatic Initiation
ML20002C767
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/05/1973
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Grier B
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20002C765 List:
References
NUDOCS 8101100836
Download: ML20002C767 (2)


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comm General Off ces 272 West MacNgan Avenue. Jackson. M.cNgan 43201. Area Code S17 788 0550 March 5,1973 Mr. Boyce H. Grier, Regional Director Re: Docket No 50-155 Directorate of Regulatory Operations License No DPR-6 US Atomic Energy Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr. Grier:

This is in response to your letter addressed to Mr. R. L. Haueter dated February 12, 1973 concerning certain Big Rock Point Plant license activities which are viewed an being in apparent nonce =pliance with cer-tain AEC license requirements.

Spec.ifically, Item 1 of that letter stated that the ' emergency condenser was not operable during the period from December 22,1(J72 to January 10, 1973 when one of the two steam inlet valves was closed. The emergency condenser was considered operable because Section B6.2.1 of our Procedures Manual specifically states that "If one bundle should develop a leak during power operation, it will be permissible to valve it out until the next outage," thereby allowing for one loop operation. As noted in our letter to Mr. O' Leary dated January 16, 1973, the emergency condenser loops were isolated individually to determine which tube bundle was leaking.

The emergency condenser acts as a backup heat sink for reactor decay heat when the main condenser is unavailable. It will also bach up the shutdown cooling system but only when the reactor head is bolted in place. The availability to operate with one emergency condenser loop out of service has been pemissible in the Plant Operating Procedures since Big Rock Point became operational in 1962. It is based on our interpre-tation of Section 5.8 9 of the Final Hazards Su= mary report which states specifically that "A radiation monitor on the emergency condenser vent stack will detect a release of primary steam, as may occur in the event of a tube rupture and cause an alarm in the control room. Under this con-dition, the operator isolates the system by closing both condensate return valves and two motor-operated valves on the steam inlet lines to the con-densing tubes. He can then reopen one system at a time to detemine which tube bundle is still operative." Section 12 517 also states that " Failure of a tube in one of the condenser tube bundles would not interfere with the ability of the remaining tube bundle to cool the reactor. Any failed tube bundie can be isolated by manual actuation (from the control room) of the motor-operatedvalvEh.i 1973 f/0//0 ON

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L:chet:0 50-155, Licence No DPR 6 March 5, lc/73 In cunz:ary, our interpretation in that Section 4.1.2(b) of the Technical Specificationc 10 met if one loop of the energency condencer 10 operable and available for automatic initiation.

Yourc very truly, i

RE3/enp Ralph B. Sewell Nuclear Licensing Administratcr

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