ML20149E752
| ML20149E752 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/16/1997 |
| From: | Linh Tran NRC (Affiliation Not Assigned) |
| To: | Powers K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TAC-M98388, NUDOCS 9707210054 | |
| Download: ML20149E752 (3) | |
Text
3 Mr. K;nnsth P. Pow rs
' July 16, 1997 D
G:nsr:I Manag:r Big Rock Point Plant Consumers Energy Company.
10269 U.S. 31 North Charlevoix, MI 49720
SUBJECT:
BIG ROCK POINT PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING RERATING OF PORTIONS OF THE POST-INCIDENT SYSTEM (TAC NO. M98388)
Dear Mr. Powers:
In reviewing your evaluation of the licensing-basis loss-of-coolant accident event associated with the rerating of portions of the post-incident system, we find that the additional information identified in the enclosure is needed to continue our review. We request that you respond to the enclosed request for additional information within 30 days
~
of receiving this letter. If you have any questions regarding this request, please contact me at 301-415-1361.
Sincerely, ORIGINAL SIGNED BY Linh N. Tran, Project Manager Project Directorate ill 1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation Docket No. 50-155
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e, Mr. Kenneth P. Powers Big Rock Point Plant cc:
Mr. Thomas A. McNish Michigan Department of Attomey Vice President & Secretary General Censumers Energy Company Special Litigation Division 212 West Michigan Avenue 630 Law Building Jackson, Michigan 49201 P.O. Box 30212 Lansing, Michigan 48909 Judd L. Bacon, Esquiro Consumers Energy Company 212 West Michigan Avenue Jackson, Michigan 49201 Jane E. Brannon, County Clerk County Building Annex 203 Antrim Street 3
Charlevoix, Michigan 49720 ONice of the Govemor Room 1 - Capitol Building l
Lansing, Michigan 48913 Regional Administrator, Region ill U.S. Nuclear Regulatory Commission i
801 Warrenville Road Lisle, Illinois 60532-4351 Drinking Water and Radiological s
Protection Division Michigan Department of Environmental Quality L
3423 N Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Omce Big Rock Point Plant 10253 U.S. 31 North Charievoix, Michigan 49720 Mr. Robert A. Fenech, Sr Vice Pres Nuclear, Fossil, and Hydro Operations Consumers Energy Company 212 West Michigan Avenue
- Jackson, Michigan 49201 Apre 1907 a
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1 REQUEST FOR ADDITIONAL INFORMATION in reviewing your evaluation of the post-incident system (PIS) for the licensing-basis LOCA
[lossef coolant accident] event, the staff has identified questions regarding the operability of a cast-iron body valve (VSW-3), which is an isolation valve between the PIS and the service water system. In your evaluation, it was determined that this valve has a temperature and pressure rating of 175 7 and 200 psig. While the maximurn system pressure is expected to remain below the 200 psig pressure rating limits, the peak containment temperature is significantly above 175 T. It was determined that insulating the valve body will adequately limit the temperature of the valve for the containment accident conditions.
Because it has apparently not been known what the temperature of the valve would be during j
the licensing-basis accident conditions, the staff believes that the valve had been in an undetermined state of operability before being insulated. The staff had requested that the Consumers Energy Company provide an analysis or other justification that demonstrated that j
the valve was operable in the uninsulated condition for the licensing-basis accident conditions.
Consumers Energy Company provided engineering analysis, EA-SC-97-007-BB-02, which analyzed the VSW-3 valve without the insulation installed. In your analysis, you stated that the temperature rise at the time of containment spray actuation was calculated to be 39 T, 4
assuming an initial temperature of 90 T, which is below the rated temperature of 175 T.
The staff noted that the calculated valve body temperature response for VSW-3 provided on page 4 of this analysis was only for the first 100 seconds. The staff believes that beyond 100 l
seconds, through extrapolation, the VSW-3 valve body temperature response would be above 175 T. Based on the above discussion, you are requested to provide the following
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information relative to valve VSW-3:
1.
Provide an additional analysis or other justification that demonstrated that the valve j
was operable in the uninsulated condition for the licensing-basis accident conditions.
2.
If applicable, provide the time frame in which the valve was determined to bc inoperable.
J 4
ENCLOSURE i
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