ML20235C978

Responds to 710428 Twx Re 710422 Inoperability of HPCI Sys. Tech Spec Section 3.5.H Incorporated to Provide Power Under Critical Conditions.Due to Higher Possibility of Malfunction During Startup Testing,Section 3.5.H Should Not Be Invoked

ML20235C978
Person / Time
Site:	Monticello, 05000000
Issue date:	04/29/1971
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Dienhart A NORTHERN STATES POWER CO.
Shared Package
ML20235B311	List: IA-87-111, Submits Rept on Plant,As Discussed in ACRS 150th Meeting on 721012-14.Listed Items Can Be Resolved During Const & Facility Can Be Constructed W/Reasonable Assurance for Operation W/O Undue Risk to Public Safety IR 05000254/1972009 IR 05000358/1972003 IR 05000358/1973001 IR 05000358/1973002 IR 05000358/1973003 IR 05000358/1973005 IR 05000358/1973006 IR 05000358/1973007 IR 05000358/1974001 IR 05000358/1974002 IR 05000358/1974003 IR 05000358/1975004 ML20235B308 ML20235B364 ML20235B401 ML20235B405 ML20235B424 ML20235B456 ML20235B461 ML20235B465 ML20235B477 ML20235B488 ML20235B507 ML20235B552 ML20235B582 ML20235B585 ML20235B588 ML20235B605 ML20235B618 ML20235B623 ML20235B649 ML20235B656 ML20235B662 ML20235B670 ML20235B679 ML20235B683 ML20235B687 ML20235B702 ML20235B708 ML20235B713 ML20235B714 ML20235B718 ML20235B720 ML20235B730 ML20235B734 ML20235B748 ML20235B754 ML20235B762 ML20235B764 ... further results
References
FOIA-87-111 NUDOCS 8709250075
Download: ML20235C978 (1)

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Docket-AEC PDR DR Reading DRL Reading BWR-1 File FSchroeder,'DRL April 29, 1971 SHanauer, DR-

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.TRWilson, DRL RSBoyd, DRL' Do'cket No. 50-263 RDeYoung, DRL DSkovholt, DRL EGCase, DRS JKnotts,-OGC DThompson, DRL Northern States Power Company LRogers, REP ATTN: Mr. Arthur.V. Dienhart NDube, DRL (w/3.encis) l Vice President SNKari, DRL 414 Nicollet Hall. Compliance (2)

Minneapolis, Minnesota. 55401 VBenaroya,~DRL Gentlemen ,

t Your TWK dated April 28, 1971, informed us that the HPCI system became inoperable on April 22, 1971, and stated that you would operate the plant with the HPCI system inoperable until Wednesday, May 5, 1971, in accordance with Section 3.5.H of the Technical Specifications.

Section 3.5.H is incorporated in the Technical Specifications in order to continue to provide power under certain critical conditions. Since the Monticello plant is undergoing startup tests we do not believe the provisions of this section should apply at this time. We consider the availability of safety systems'of a plant to be more essential during plant checkout, when all systems have not been completely tested, and the possibility of malfunctions occurrence is higher than during routine operation.

Accordingly, we conclude that it is not in the interest of public health and safety to invoke Section 3.5.H of the Technical Specifications and therefore conclude that the provisions 'of Section 3.5.D4 should apply.

In the near future, the Monticello Technical Specifications will be revised to make them more consistent with other facilities on areas relating to allowable equipment repair periods.  ;

Sincerely, PYri. MNs k 37 2I 6d7f .l g Peter A. Morris, Director Division of Reactor Licensing omcz, .?RL,:B,WR ,1 ,, ,,, ,D,RL,:ByR-1, ,

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