ML20211M404

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Forwards Corrected Page 2 of Evaluation Encl W/Nrc to Util
ML20211M404
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 02/20/1987
From: Rooney V
Office of Nuclear Reactor Regulation
To:
NRC
References
NUDOCS 8702270276
Download: ML20211M404 (2)


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February 20, 1987

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SUBJECT:

ERRATA - FEBRUARY 18, 1987 LE' ITER FROM NRC TO VERMONT-l' '

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Please substitute the enclosed page 2 for page 2 of the evaluation enclosed with your copy of the NRC letter to Ver@t Yankee dated February 18, 1987.

N4 The second paragraph has been corrected by adding:

2 "and 400 manhours each in _the I&C and Electrical Engi,neering disciplines".

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.., analytical techniques and accounted for the design features specific to Vermont Yankee which affect the plant's ability to respond to a severe accident.

VYNPC subsequently met several times with the NRC staff and representatives of the State of Vermont and provided responses to NRC staff questions and comments thereby laying the groundwork for Vermont Yankee Containment Safety improvements while advancing the NRC generic Mark I Containment Safety activities by providing a sample case for a typical Mark I reactor containment. The licensee stated that as a result of the resources expended on this effort to date and those anticipated in the future it has concluded that the relative safety importance of the f

planned containment safety efforts warrant a modification to the remaining NUREG-0737, Supplement 1, commitments involving SPDS, f

Regulatory Guide 1.97 and DCRDR. Specifically, resources expended to date on the CSS include approximately 1,000 manhours in the PRA disciplines, 1,000 manhours in the System Engineering discipline, and 400 manhours each in the I&C and Electrical Engineering disciplines. VYNPC described planned CSS activities and estimated that resource requirements associated with these planned activities totaled an additional 2,000 manhours.

In the December 19, 1986 submittal VYNPC stated that it has identified significant resource shortages in concurrently developing containment initiative tasks, and SPDS design and Installation and Test Procedure packages. Additionally, due to further developed design details, it can now identify significant amounts of SPDS work which can be completed during plant operation. The licensee therefore requested that the schedular commitment for SPDS be modified. The licensee stated that, as previously required, the SPDS would be installed and functional at the end of Cycle 14. The change in SPDS requirements which the licensee proposed is that startup testing, system verification and validation, and operator training be conducted during Cycle 14 rather than prior to the iMtiation of Cycle 14. We find that the delay of these testing and training activities is compensated for by the importance of the planned containment safety activities. Therefore, the staff concludes that there is adequate justification for modification of the Commission Order.

The licensee stated that during the 1986 refueling outage, VYNPC completed all Regulatory Guide 1.97 installation / upgrades associated with their Environmental Qualification Program. The previously planned work scope for the 1987 refueling outage included completion of all remaining Regulatory Guide 1.97 installation / upgrades.

Recently the licensee determined that the LPRM power supplies should have been included in the work scope for the remaining Regulatory Guide 1.97 modifications.

However, due to the difficulty of including this recently determined upgrade in the 1987 outage work scope in view of the containment resource commitments previously discussed and based on the fact that, with the exception of this one item, all Regulatory Guide 1.97 installation /

upgrades will be completed in accordance with the existing schedule coamitment; the licensee requested that the subject Order be modified to extend the Regulatory Guide 1.97 schedular commitment for this specific l

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