NUREG/CR-1833, Forwards Request for Addl Info Necessary to Complete SEP Seismic Review.Info Identified as Open Items from Draft NUREG/CR-1833, Seismic Review of Palisades Nuclear Power Plant,Unit 1,As Part of Sep. W/O NUREG
| ML18046A327 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/19/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-03-06, TASK-03-11, TASK-3-11, TASK-3-6, TASK-RR LSO5-81-01-024, LSO5-81-1-24, NUDOCS 8101220472 | |
| Download: ML18046A327 (5) | |
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Docket No. 50-255
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Mr. David P. Hoffman Consumer's Power Company 212 West Michigan Avenue Jackson, Michigan 49201
Dear Mr. Hoffman:
DISTRUBITION Docket fi.l es NRC PDR L PDR SEP reading DCrutchfield TWambach WRussell RHermann TCheng OELD I&E (3)
ACRS _ ( 16)
JBuchanan, NSIC
SUBJECT:
SEP TOPICS III-6, SEISMIC DESIGN CONSIDERATIONS, AND III-11, COMPONENT INTEGRITY - PALISADES NUCLEAR POWER PLANT JHeltemes DEisenhut RPurple Gla,inas JRoe RDiggs SEP File GCwalii1a As you are aware, the staff and it's consultants have completed the review of Palisades Nuclear Power Plant. Enclosure 1 is a copy of draft of NUREG/CR-1833, "Seismic Review of the Palisades Nuclear Power Plant Unit 1 as Part of the Systematic Evaluation Program.
11 This report will serve as the principal input for the staff's final assessment for Systematic Evaluation Program topics III-6, "Seismic Design Considerations" and I II-11, "Component Integrity". Pl ease inform us if your as-built facility differs from the licensing basis assumed in our assessment.
According to our review, some open items have been identified (Enclosure 2} related to these topics. The detailed evaluation of these open items can be found in the attached report.
In order to complete our review on these topics, we require additional information from you.
You should submit within 30 days from the date of this letter information which is requested in Enclosure 2.
In the event that analysis is necessary for you to complete your evalua-tion, you should submit a schedule for completion of each open item.
Proposed modifications identified in our report are representative of the types of modifications which should be considered to upgrade seismic safety margins. Pursuant to 10 CFR 50.59 you should indepen-dently evaluate the necessity of any modifications to your facility.
Enclosures:
As stated Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
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Docket No. 50-255 LS05-8l-Ol-024 Mr. David P. Hoffman Consumer's Power Company 212 West Michigan Avenue Jackson, Michigan 49201
Dear Mr. Hoffman:
WASHINGTON, D. C. 20555 JAN 1 9 1931
SUBJECT:
SEP TOPICS III-6, SEISMIC DESIGN CONSIDERATIONS, AND III-11, COMPONENT INTEGRITY - PALISADES NUCLEAR POWER PLANT As you are aware, the staff and it's consultants have completed the review of Palisades Nuclear Power Plant. Enclosure l is a copy of draft of NUREG/CR-1833, "Seismic Review of the Palisades Nuclear Power Plant Unit l as Part of the Systematic Evaluation Program."
This report will serve as the principal input for the staff's final assessment for Systematic Evaluation Program topics III-6, "Seismic Design Considerations" and III-11, "Component Integrity". Please inform us if your as-built facility differs from the licensing basis assumed in our assessment.
According to our review, some open items have been identified (Enclosure 2) related to these topics.
The detailed evaluation of these open items can be found*in the attached report.
In order to complete our review on these topics, we require additional information from you.
You should submit within 30 days from the date of this letter information which is requested in Enclosure 2.
In the event that analysis is necessary for you to complete your evalua-tion, you should submit a schedule for completion of each open item.
Proposed modifications identified in our report are representative of the types of modifications which should be considered to upgrade seismic safety margins.
Pursuant to 10 CFR 50.59 you should indepen-dently evaluate the necessity of any modifications to your facility.
Enclosures:
As stated cc w/enclosures:
See next P.age Sincerely, L 111.,~A&AW. ~
Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing
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M~. David P. Hoffman cc Mr. Paul A. Perry, Secretary Consumers Power Conµany 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Conµany 212 West Michigan Avenue Jack son, Michigan 49201 Joseph Gallo, Esquire Isham, Lincoln & Beale 1120 Connecticut Avenue Room 325.
Washington, D. C.
20036 Peter W. Steketee, Esquire 505 Peoples Building Grand Rapids, Michigan 49503 Alan S. Rosenthal, Esq., Chairman Atomic Safety & Licensing Appeal Board U. s. Nuclear Regulatory Conmission Washington, D. c. 20555 Mr. John O'Neill, II Route 2. Box 44 1 Maple City,_Michigan 49664 Charlevoix Public Library 107 Clinton S~reet Charlevoix, Michigan Chairman County Board of Supervisors Charlevoix County Charlevoix, Michigan 49720 Office of the Governor (2)
Room 1 - Capitol Building Lansing, Michigan 48913 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. s. Environmental Protection Agency Washington, D. C.
20460 U. s. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board
- u. S. Nuclear Regulatory Corrmission Washington, D. c. 20555 Dr. Oscar H. Paris Atomic Safety and Licensing Board U. s. Nuclear Regulatory Corrmission Washington, D. c. 20555 Mr. Frederick J. Shon Atomic Safety and Licensing Board
- u. s. Nuclear Regulatory Corrmission Washington, D. c. 20555 Big Rock Point Nu cl ear Power Plant ATTN:
Mr. C. J. Hartman Plant Superintendent Charlevoix, Michigan 49720 Christa-Maria Route 2, Box 108C Charlevoix, Michigan 49720 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103 Resident Inspector Big Rock Point Plant *
. c/o U.S *. NRC RR fl 3, B*ox 600 Charlevoix, Michigan 49720 ~
Mr. Jim E. Mills Route 2, Box 108C Charlevoix, Michigan 49720 Thomas s. Moore Atomic Safety & Licensing Appeal Board
- u. s. Nuclear Regulatory Corrmission Washington, o. c. 20555
ENCLOSURE 2 OPEN ISSUES PALISADES NUCLEAR POWER STATION The following list documents issues that developed as a result of our seismic review of the Palisades facility. These issues have been highlighted for a variety of reasons.
In some cases, a lack of adequate documentation exists. Designation here does not necessarily imply a safety deficiency.
However, the NRC staff has determined that further documentation of the seismic resistance capacity of these items is requested.
This documentation should include an evaluation by Consumer's Power Company.
- 1.
Essential Service Water Pump - Insufficient information was provided to (1) determine stresses and the material used in the discharge head, thus, allowable stresses in the head are unknown, and (2) evaluate the functional adequacy of the pump.
- 2.
Auxiliary Feedwater Pump - Insufficient information was provided to evaluate the functional adequacy of the pump.
- 3.
Diesel Generator Oil Storage Tank - No information was provided for evaluation.
- 4.
Safety* Injection Tank - Provided information is insufficient to demonstrate structural integrity of the tank and its support.
- 5.
Motor-Operated Valves - Sample small p1p1ng seismic analysis report has been received (12/4/80 submittals). According to our review, this analysis was not performed based on the as-built condition. Thus, no evaluation can be made at this time until additional information is provided.
- 6.
Control Rod Drive Mechanism - Insufficient information was provided to evaluate the functional adequacy.
- 7.
Steam Generator - Insufficient information was provided to verify design adequacy.
- 8.
Reactor Coolant Pump - Insufficient information was provided to verify design adequacy.
- 9.
Reactor Vessel Supports and Inter.vals - Insufficient information*
was provided to verify design adequacy.
- 10.
Battery Racks - Racks O.K., with the exception of wooden lateral bracing which should be replaced or strengthened to carry full seismic inertia loads.
', 11.
Motor Control Centers - No information available to evaluate rack structural adequacy or electrical component functionality.
- 12.
Switchgear - No information available to evaluate switch-gear rack structural adequacy or electrical component functionality.
- 13.
Control Room Electrical Panels - Insufficient information was provided to verify design adequacy.
- 14.
Transformers - No information was available to evaluate electrical functionability.
- 15.
Electrical Cable Raceways - No information was provided to evaluate design adequacy.