ML20071L437

From kanterella
Jump to navigation Jump to search
Responds to GL 89-10, Safety-Related MOV Testing & Surveillance
ML20071L437
Person / Time
Site: Prairie Island  
Issue date: 07/28/1994
From: Richard Anderson
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-10, NUDOCS 9408030108
Download: ML20071L437 (2)


Text

Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 July 28, 1994 Ceneric Letter 89-10 U S Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR CENERATING PLANT Docket Nos. 50-282 License Nos. DPR 42 50-306 DPR-60 Response to NRC Ceneric Letter 89-10,

" Safety-related Motor-operated Valve Testine and Surveillance" Our response to Generic Letter 89-10 follows:

Reportine Reautrement (Item m. of the June 28. 1989 Ceneric Letter);

aach licensee shall notify the NRC in writing within 30 days after the actions described in the first paragraph of item 1. have been completed.

Response

On June 28, 1994 during the Prairie Island Unit 1 refueling outage, we completed the initial testing and setup of the valves included in the Generic Letter 89-10 motor-operated valve (MOV) program.

All design changes to MOVs, initiated from Generic Letter 89-10 MOV program reviews and analyses, have been completed in both units (constituting approximately one-fourth of all valves in the program) with the exception of motor brake removal on several Unit 2 valves. These will be removed during the Spring 1995 Unit 2 refueling outage as we committed in our response, of February 4, 1994, to the Region III MOV inspection report, of December 2, 1993.

j In our original response (dated December 28, 1989) to Generic Letter 89-10, we stated that " Differential pressure testing will be performed to the extent practicable." There are two groups of valves which we consider to not be included in this category. The first group contains those valves which cannot be dynamically tested at full design basis conditions due to plant design.

These valves have been set up statically using the best available Prairie steolo..nd G10127 b

940ao 020s 940,2g 0

ca aoock o,0002s2 i

se PDR

e USNRC Page 2 of 2 July 28, 1994 Island or industry data.

These valves are planned to be evaluated using the EPRI MOV Performance Prediction Program methodology as it becomes available.

The second group includes those valves for which no meaningful data can be obtained by performing differential pressure testing, thus making the testing not practicable (performing the testing would involve increasing the costs and risks associated with testing with no compensating knowledge of the conditions of the valves).

These are valves which have low design basis differential L

pressures relative to other valves (e.g., small dynamic component of total seating / unseating force).

In cases where a dynamic test would not provide useful data to aid in the setting of the valve, we have chosen to shift resources to other, significant, testing.

Such valves also have been set up statically using the best available Prairie Island or industry data.

Region III inspectors evaluating our MOV testing program considered this treatment of the second group of valves to represent a change of previous commitment which requires written communication with NRR per the requirements of Generic Letter 89 10.

This discussion is therefore intended to clarify our previous commitment.

In this letter we are making no new NRC commitments but are clarifying an earlier commitment:

" Differential pressure testing will be performed to the extent practicable" refers to the exclusion of differential pressure testing of both those valves which are not testable due to plcnt design and those valves for which differential testing will provide no meaningful information.

Please contact Jack Leveille (612-388-1121, Ext 4662) if you have any questions related to our response.

aavb o %UC AA.

gn, Roger O Anderson Director Licensing and Management Issues c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager. NRC J E Silberg l

f steolo..no j

i

, - - -