ML18046A741
| ML18046A741 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/17/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML18046A742 | List: |
| References | |
| IEB-79-06, IEB-79-06B, IEB-79-6, LSO5-81-06-058, LSO5-81-6-58, NUDOCS 8106250161 | |
| Download: ML18046A741 (5) | |
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~UTION Local PDR Docket No. 50-255 ORB Reading DCrutchfield Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W. Parnall Road Jackson, Michigan 49201
Dear Mr. Hoffman:
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We have completed a review of the information you have provided in.
letters dated April 27, May 18, June 5, August 8, August 10, August 16, August 21, and September 13, 1979, in response to IE Bulletins 79-06 and 79-068 for the Palisades Plant. The enclosed Safety Evaluation addresses the completeness and acceptability of the responses.
Your responses to IE Bulletin 79-06C, regarding the operation of the reactor coolant pumps following a loss-of-coolant accident will be reviewed separately as part of NUREG-0731 Item II.K.3.5.
The issuance of thi's-- evaluation completes Item II.K.1, IE Bulletins, for your facility.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page 8 10 6 2 5 0 /{,/
Sincere!~, j De~is~~Crutchfleld, Chief Operating Reactors Branch #5 Division of Licensing OFFICE~ DL: ORB #5 ' DL: ORB #4 DL:
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Docket No. 50-255 LS05-81-06-058 Mr. David P. Hoffman UNITED STATES NUCLEAR*REGULATORV COMMISSION WASHINGTON, D. C. 20555 June 17, 1981 Nuclear Licensing Administrator Consumers Power Company 1945 W. Parna 11 Road Jackson, Michigan 49201
Dear Mr.. Hoffman:
We have completed a review of the information you have provided in letters dated April 27, May 18, June 5, August.8, August 10, August 16, August 21, and September 13, 1979, in response to IE Bulletins 79-06 and 79-06B for the Palisades Plant.
The enclosed Safety Evaluation addresses the completeness and acceptability of the responses.
Your responses to IE Bulletin 79-06C, regarding the operation of the reactor coolant pumps following a loss~of-coolant accident will be reviewed separately as part of NUREG-0737 Item II.K.3.5.
The issuance of this evaluation completes Item II.K.l, IE Bulletins, for your facility.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Sincerely,
~C~h~#rifl Operating Reactors Br~n~
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Division of Licensing
Mr. David P. Hoffman cc M. I. Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, lllinois 60611 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5711 Summerset Drive Midland, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route 1, Box 10 Van Buren County, Michigan Office of the Governor (2)
Room l - Capitol Building Lansing, Michigan 48913 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103 Palisades Plant ATTN:
Mr. Robert Montross Plant Manager Covert, Michigan 49043 49043 June 17, 1981 U. s. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Charles Bechhoefer, Esq., Chairman Atomic Safety and Licensing Board Panel
- u. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. George c. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M. Stanley Livingston l 005 Cal le Largo Santa Fe, New Mexico 87501 Resident Inspector c/o U. S. NRC P. o. Box 87 South Haven, Michigan 49090
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UNITED STATES NUCLEAR HEGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INTRODUCTION FOR CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255.
On March 28, 1979 the Three Mile Island Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which were initiated by a loss of *feedwater*transient. Several aspects of the acci-dent have generic applicability at operating Co~bustion Engineering reactors.
On April 11, 1979, IE Bulletin 79-06 was sent to all Combustion Engineering operating plant licensees.
The purpose of the Bulletin was to provide information concerning the accident at TMI-2 and to request certain actions be taken by licensees to preclude a similar occurrence at their facilities.
This bulletin was superseded and expanded by IE Bulletin 79-06B dated April 14, 1979.
By letters dated April 27, May 18, June 5, August 8, August 10, August 16, August 21, and September 13, 1979, Consumers Power Company provided responses in conformance with the requirements of the Bulletins.
EVALUATlON In the two-year period since the Bulletins have been implemented we have observed, in addition. to our review of the responses enumerated above, that the licensee has complied with all the following provisions of the Bulletins:
- Understanding of the TMI-2 sequence of events.
- Review Pl ant Procedures for coping with accidents and transients.
- By review of procedures and training instructions: *.
(1) to avoid overriding automatic action of ESF, (2) to keep high pressure injection (HPI) system in operation for at least 20 minutes and to maintain 50 F subcooling margin, (3) to correlate HPI initiation with reactor coolant pump (RCP) opera-tion, and (4) to train operators not to rely on pressurizer level only to deter-mine primary coolant inventory.
Verification of emergency feedwater (EFW) valve positions and all safety-related. valve positions to ensure proper operation of EFW and ESF.
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- By review of containment isolation initiation and design for avoidance of isolating lines that are needed to avoid degraded core cooling capability.
- BY preparing and implementing procedures for all valves which could defeat or compromise flow of EFW.
- By reviewing operating modes and procedures to prevent inadvertent pumping of radioactive gasses and liquids out of th~ primary containment.
- By reviewing procedures related to maintenance and test of safety-related systems to:
(1) verify operability of redundant system prior to removal of any system from service,
{2) verify operability of all systems following maintenance or testing, and
{3) verification to operating personnel whenever a system:is removed from of returned to service.
- By developing procedures and training operators to establish and maintain natural circulation.
- By training operators to take into account reactor vessel integrity con-siderations during any accident or transient.
- By performing analyses and design modifications to reduce the likelihood of automatic PORV actuation during anticipated transients.
- By providing procedures and training operators for a prompt manual reactor trip for transients that result in a pressure increase in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled or expected condition of operation.
By proposing any needed Technical Specification changes to implement any of the above parts of the Bulletins.
CON CL US IONS Based on our review of the information provided by the licensee in. response to these IE Bulletins, we conclude that the licensee has acceptably responded to these Bulletins.
The actions taken by the licensee demonstrate its understanding of the concerns and implications of the TMI-2 accident.as they relate to the Palisades Plant. These actions have resulted in added assurance for the continued protection of the public health and safety during plant operation.
Dated:
June 17, 1981
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