ML17055D201

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Rev 1 to Summary of 870818 Meeting W/Util to Discuss Drawdown Time Calculations.Unreviewed Safety Issues Not Covered by 10CFR50.59,contrary to Statement on Original Summary
ML17055D201
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 09/01/1987
From: Haughey M
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8709140058
Download: ML17055D201 (2)


Text

September 1,

1987 Rev.

Docket Ho. 50-410 LICENSEE:

FACILITY:

SUBJECT; DISTRIBUTION NRCPDR Niagara Mohawk Power Corporation 'ocal PDR'DI-1Rdg.

Nine Mile Point Unit 2 "MHaughcy R. Capra

SUMMARY

OF MEETING HELD ON AUGUST 18, 1987 WITH NIAGARA MOHAMK POWER CORPORATION (NMPC)

OGC JCraig EJordan JPartlow ACRS(10)

BClayton

JJohnson, RI DNeighbors PGoel JKudrick On August 18, 1987 the NRC staff met with representatives of NMPC to discuss drawdown time calculations for Nine Mile Point Unit 2 (NMP-2).

NMPC had recently -determined that the original calculations to determine drawdown time for NMP-2, which assumed loss of offsite power, did not represent the worst case condition.

At the meeting, NMPC presented thc results of the revised, more conservative calculations.

The new analysis applies to the first cycle of operation only.

Thc analysis for operation beyond the first cycle will be completed at a later date.

NMPC has performed the new analysis under the provisions of 10 CFR 50.59.

If the NRC staff determines that this is~ an unreviewed safety issue, and thcrcfore not covered by the provisions of 10 CFR 50.59, the licensee will be informed.

Because NMPC intends to opera e NMP-2 under restrictions more stringent than those presently in thc Techni al Specifications in order to bc bounded by the new analysis, HMPC is no pr osing a change to the Technical Specifications.

In addition to the discussions concerning the revised drawdown time, the recent amendment request to revise the allowable service water temperature to 81'F was discussed; Thc 'licensee agreed to provide additional information concerning (1) procedures to be used to bring thc third closed loop cooling water (CCP) heat exchanger on line when needed; (2) procedures concerning radwaste loads in the turbine area; and (3) what was involved in reducing the K factors.

Enclosure 1 contains a copy of the handout supplied by NMPC during the meeting.

Enclosure 2 contains a list of meeting attendees.

870%i 40058. 87090i PDR ADOCN, 05000410 P

Enclosures:

As stated cc:

Sce.next page Mary F. Haughey, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II MHaughey g/I /87 rivisrbn iz Ze'n i'sauna 6 carr~cP At A<g us Jnf~'ca/rd Jp Cnc/~Wreg, Sc'c

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