ML18046A738
| ML18046A738 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/19/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-06-10.A, TASK-6-10.A, TASK-RR LSO5-81-06-061, LSO5-81-6-61, NUDOCS 8106240159 | |
| Download: ML18046A738 (4) | |
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Docket No. 50-255 LSOS-81-06-061 t.'
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Mr. David P. Hoffman Nuclear licensing Administrator Consumers Power Company 1945 w. Parnall Road Jackson, Michigan 49201
Dear Mr. Hoffman:
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SUBJECT:
SEP TOPIC V I-10.A, TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLUDING RESPONSE TIME TESTING, SAFETY EVALUA~*'*
TION FOR PALISADES The enclosed revised staff safety evaluation is based on a contractor document that has been* made available to you previously and has been modified to cite the current standard. This evaluation supports the findings of the staff safe-ty evaluation of Topic VI-10.A and proposes modifications to the Technical Specifications and some equipment to implement. a response time testing program.
The :need to actually implement these changes wi 11 be determined during the in-tegrated safety assessment.
This topic assessment may be revised in the future..
if your facility design is changed or if NRC criteria relating to this topjc are modified before the integrated assessment is completed.
Enclosure:
As stated cc w/enclosure:
See next page 8106240/59 f
Sincerely.
Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of licensing
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NRC FORM 318 118/801 NRCM 82-4()
OFFICIAL RECORD COPY
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. T UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Dock et* No. 50-255 LS05-81-06-061 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 w. Parnall Road Jackson, Michigan 49201
Dear Mr. Hoffman:
June 19, 1981
SUBJECT:
SEP TOPIC VI-10.A, TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLUDING RESPONSE TIME TESTING, SAFETY EVALUA-TION FOR PALISADES The enclosed revised staff safety evaluation is based on a contractor document that has been made avai'lable to you previously and has been modified to cite the current 'standard.
This evaluation supports the findings of the staff safe-ty evaluation of Topic VI-10.A and proposes modifications to the Technical Specifications and some equipment to implement a response time testing program.
The need to actually implement these changes will be determined during the in-*
tegrated safety assessment.
This topic assessment may be -revised in the future if your facil.ity design is changed or if NRC criteria relating to this topic*
are* modified before the integrated assessment is completed *.
Enclosure:
As stated cc w/enclosure:
See next page Sincerely, jJ **.*.. 71(.~~**
~utchfield, Chi Operating Reactors Branch
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- Division of Licensing
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Mr. David P. Hoffman c~c M *. I. Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Corrpany 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 Chi9ago,. Illinois 60611 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5711 Summerset Drive Midland, Michigart 48640
- Kalamazoo Public Library 315 South Rose Street Kalamazoo, Mfchigan 49006 Township Supervisor Covert Township
- Route l,* Box 10 Van Buren County, Michlgan 49043 Office of the Governor (2)
Room 1 - Capitol Building
.Lansing, Michigan 48913 William J. Scanlon, Esquire.
2034 Pauline Boulevard Ann Arbor, Michigan 48103 Pa 1 i sades. P 1 ant ATTN:
Mr. Robert Montross Plant Manager Covert, Michigan
- 49043 PALISADES Docket No. 50-255 U. S. Environmental Protection Ag'cncy Federal Activities Branch Region V Office ATTN:
EIS COORDINATOR 230 South Dearborn Street
- Chicago~ Illinois 60604 Charles Bechhoefer, Esq., Chairman Atomi~ Safety and Licensing Board Panel
- u. S. Nuclear Regulatory Corrmission Washington, o. c.
20555.
Or. George c. Anderson
. Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M *. Stanley Li vi ngst.oi'l 1005 Calle 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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TOPIC:
VI-10.A, TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLUDING RESPONSE TIME TESTING I.
INTRODUCTION The purpose of this Topic is to review the reactor trip system (RTS) and engineered safety features (ESF) test program for verification of RTS and ESF operability on a periodic basis and to verify RTS and ESF response time in order to assure the operability of the RTS and ESF.
Response
times should not exceed those assumed in the plant accident analyses.
Accordingly, the test program of the RTS and ESF was reviewed in accord-ance with the Standard Revi-ew Plan, including applicable Branch Technical Positions.
II.
REVIEW CRITERIA The review criteria are presented in Section 2 of EG&G Report 1183-4170, "Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing".
However, due to changes made to the applicable Standard, Regulatory Guide 1.118 references should be replaced by a refer-ence to IEEE Std. 338-1977.
III.
RELATED SAFETY TOPICS AND INTERFACES Topic VI-7.A.3 discusses the question of testing protection systems under conditions as close to design condition as practical. There are no topics that are dependent on the p_resent topic information for their completion.
IV.
REVIEW GUIDELINES Review guidelines are presented in Section 3,of Report 1183-4170. These guidelines should also reference IEEE 338 in lieu of the Regulatory Guide.
V.
EVALUATION Palisades complies with the current licensing criteria, except for Section 6.3.4 of IEEE Std. 338-1977 (response time test) *..
VI.
CONCLUSION It is the staff 1s position that the design of systems which are required for safety shall include provisi-0ns for periodic verification th~t the-minf111.1m performance of instruments and control is not less than that which was assumed in the safety analyses.
The bases for this position are Gen-eral Design Criterion 21, Section 3.9 of IEEE Std. 279-1971, and IEEE Std *.
- 338-1977. Therefore, the licensee should implement a program for response time testing of all reactor protection systems {including engineered safe-ty features systems such as containment isolation).
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