ML20033C717
| ML20033C717 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/13/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| LSO5-81-11-014, LSO5-81-11-14, NUDOCS 8112030742 | |
| Download: ML20033C717 (4) | |
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Dear Mr 'Hoffman:
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.e We are continuing our review of the Probabilistic Risk Assessment results relating to the efficacy of a recirculation pump trip for the Big Rock Point Plant. We have found that additional information described in the enclosure to this letter is needed.
This request was discussed with your representative, on November 3,' 1981'.. We request your response within 30 days of your receipt of this letter.
Sincerely, Original signed by"
-Thomas V. Wambach for/
Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
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NRO FORM lHS 0&00) NHCM Om OFFiClAL RECORD COPY usam mu-mm 9
Mr. David P. Hoffman 'No'vember 13, 1981-1 cc
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Mr. Paul A. Perry, Secretary U. S. Environmental. Protection i
Consumers Power Cogany Agency-212 West Michigan Avenue.
Federal Activities Branch i
Region V Office j
Jackson, Michigan 49201-ATTN:' Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Cogany Chicago, Illinois 60604:
212 West Michigan Avenue Jackson, Michigan 49201-Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo, Esqu' ire
-V-U. S. Nuclear Regulatory Comission i
Washington, D. C.
20555 Isham, Lincoln & Beale 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Atomic Safety and Licensing Board Washingtou, D. C.
20036 ce U. S. Nuclear Regulatory Commission Peter W. St'eketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon -
Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Comission i
Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 i
Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard '
County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County 3
Charlevoix, Michigan 49720' Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semel Mr. Jim E. Mills Counsel for Christa Maria, et al.
Route 2, Box 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law
.263316th Street, NW Washington, D. C.
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lir. David P. Hoffman 3-November 13,.1981 3
cc Dr. John H. Buck Atomic Safety.and Licensing Appeal Board U. S. _ Nuclear Regulatory Comission Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Comission, Washington, D. C.
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e REQUEST FOR ADDITIONAL INFORMATION BIG ROCK POINT Based on our review of the Consumers Power Company' September 10, 1981 response to our August 5,1981 request. for additional information regarding.the. efficacy of a recirculation pump trip, and subsequent discussions with the licensee, the following information is requested:
1.
In regards to the_ inadvertent control' rod withdrawal as an ATWS initiator, provide simplified calculations to identify the following specific information:
(a) Power response of the system
.(b) Pressure response cf'the system (c) Time available for 'the operat.or to initiate the Liquid Poison System (LPS) in order.to prevent actuation of the Reactor Depressurization Systr.m.
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This information sho~uld tie fur 11shed for case's with.and without recirculation pump trip.
Information should be presented in the format of page 82 of Attachment 1 of the CPC submittalipf February 26,1981. and should include the effect of uncertainties in initial volumes as well as tany time delays for the operator to s
be made aware that a transient is in progress.
2.
As a limiting calculation of the effectiveness of euto RPT in enhancing the. operability of a non-qualified LPS, prov,ide a calculation in the format of Table 1 of Attachment 2 of the i c,
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CPC s'Jbmittal of February 26, 1981 which includes auto RCP, an environmentally qualified LPS and an environmentally qualified
... 1 Emergency Condenser System.
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3.
Provide specific data documenting a comparison of the core respoofe (power) predicted by the RETRAN model and the BRP core simulator model, and the comparison of the BRP core simulator model with the observed parameters in the BRP core.
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- 4. ' Provide additional clarification of your statement regarding the differences in initial conditions and safety valve setpoints for c.
the analysis presented in NEDE-21065 and the current analysis.
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