ML18046A880

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Submits Addl Info Re SEP Topic V-6, Reactor Vessel Integrity. Work Associated w/NUREG-0569 Has Been Completed & SEP Topic V-6 Issue Resolved
ML18046A880
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/18/1981
From: Vincent R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0569, RTR-NUREG-569, TASK-05-06, TASK-5-6, TASK-RR NUDOCS 8108240152
Download: ML18046A880 (1)


Text

consume11 Power company General Offices: 212 Wast Michigan Avenue, Jackson, Ml 49201 * (517) 788-0550 August 18, 1981 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC V-6, REACTOR VESSEL INTEGRITY By letter dated March 5, 1980, the NRC tra.nsmittedNUREG 0569, "Evaluation of the Integrity of SEP Reactor Vessels", which provided the NRC evaluation of SEP Topic v~6.

This NUREG contained the recommendation that fluence estimates for the Palisades reactor vessel wall be recalculated and submitted to the NRC in light of previous experience at Fort Calho.un.

This recommenda-tion is still being c.arried as an open item within the SEP.

Consumers Power Company letter dated July 2, 1979 submitted a Technical Speci-fication change request to revise the plant heatup and cooldown curves.

Included with that request was a Battelle Columbus Laboratories report dated March 13, 1979 which discussed test results of irradiated surveillance specimen tests and provided revised fluence estimates for the reactor vessel.

NRC letter of August 21, 1979 questioned those calculations.

A meeting was held between CPCo, its consultant and the NRC on September 26, 1979 to discuss the issue, including the relationship between BNL work on Fort Calhoun and Palisades.

The NRG minutes of that meeting were issued on October 2, 1979.

As a result of the meeting and associated discussions, the reactor vessel fluence calculations were revised, and new heat up/ cooldown curves were sub-mitted to the NRC in CPCo letter of November 6, 1979.

On March 6, 1980, the NRC issued Amendment 55 to the Technical Specifications which incorporated new heatup and cooldown curves based on the revised fluence estimates.

Since the October, 1979 manuscript completion date for NUREG 0569 preceded much of the CPCo -

NRC interaction on this issue, the NUREG does not reflect the current. status.

Cons.umers Power Company considers that all necessary work associated with the recommendation in NUREG 0569 has been completed.

From the standpoint of SEP Topic V-6, therefore, this issue shoUld be considered to be resolved.

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Robert A Vincent PDRr ADOCK 05000255' Staff Licensing Engineer p

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  • CC Director, Region III, *USNRC NRC Resident Inspector