ML18046A365

From kanterella
Jump to navigation Jump to search
Forwards Evaluation of SEP Topic VIII-3.A Re Battery Capacity Tests,Revised to Reflect Comments Provided in
ML18046A365
Person / Time
Site: Palisades 
Issue date: 01/28/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Hoffmann D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-08-03.A, TASK-8-3.A, TASK-RR LSO5-81-1-031, LSO5-81-1-31, NUDOCS 8102090176
Download: ML18046A365 (7)
v • d • e


Text

    • .
    • ~-

r-i..

Docket No. 50-255 Mr. David P. Hoffman Nuclear Licensing Administrator Consumews Power Company 1945 W Parnall Road Jackson, Michigan 49201

Dear Mr. Hoffman:

~"r-- ---

DISTRIBUTION:

SE01

SUBJECT:

SEP TOPIC VIII-3.A, BATTERY CAPACITY TESTS (PALISADES NUCLEAR GENERATING STATION}

Enclosed is a revised copy of our evaluation of Systematic Evaluation Program Topic VIII-3.A, Bateery Capacity Tests. This report has not been revised to reflect all of the conments provided by your letter of April 3, 1979, because the Standard Technical Specifications were not implemented.

This evaluation will be a basic input to the integrated safety assessment -

for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are mocili.:fied before the integrated assessment is completed.

Enclosure:

SEP Topic VIII-3.A cc w/enclosure:

See next page

/

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

~

/

.... -,/

l>SU. U.'i (!.r.)- 04 t~*1s 1--=-------;*:cs::.ee~previous yellow for additional concurrences.

OFFlCE~ SEPB:DL SEPB:DL:SL SEPB:DL:C ORB#5:DL:PM ORB#5:DL:C SURNAME~

  • iis*~~;~;*;*;cii<.. *R:H~~*~a:~*~****** ****wR~5*5~;*,.**** *-rwaiiib"adi*...... **ocY..Lii:*c:hf.ieici **Gl***.* ;;5********....................

DATE~.~(.~.~(.~~.:* ***** ** 1.e:.(~~..... ;...

1 /21 /81 1 /26/81 1 /26/81 1

J NRC FORM 3181101801 NRCM 0240 OFFICIAL RECORD COPY

"'USGPO: 1980-329-824

(-r.-

~-,.

O**

Docket No. 50-255 Mr. David P. Hoffman Nuclear*Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201

Dear Mr. Hoffman:

(~-r DISTRIBUTION:

Docket

**~--"--

NRC POR/

LPDR,,.

. TERA OELD I&E (3)

ACRS (16)

JBuchanan, NSIC/

JHe 1 temes, AEOD WRussell DCrutchfield HSmi th TWambach EMcKenna RScholl RHermann

SUBJECT:

SEP TOPIC VIII-3.A, BATTERY CAPACITY TESTS (PALISADES NUCLEAR GENERAT!NG STATION GCwalina SEP File SEP Rdg.

DEisenhut RPurple JRoe RDiggs GLainas Enclosed is a revised copy of our evaluation of Systematic Evaluation Program ToJ>tc.. VlH.;.3.A, Battery Capacity Tests. This report has not been revised *to-reflect the comments provided by your letter of April 3, 1979, because the Standard Technical Specifications were not implemented.

- This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This topic assessment may be

  • revised in the future if your facility design is changed or i-f NRC criteria relating to this topic are modified befor_~_-the-**rneegrated assessment is completed.

Enclosure:

SEP Topic VIIl-3.A cc w/enclosure:

See next page Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

  • J.n.N 2 8 1981 Docket No. 50-255 LS05-81-l-031 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201

Dear. Mr. Hoffman:

SUBJECT:

SEP TOPIC VIII-3.A, BATTERY CAPACITY TESTS *

(PALISADES NUCLEAR GENERATI.NG STATIONr.

Enclosed is a revised copy of our evaluation of Systematic Evaluatfon Program Topic VIII-3.l\\, Battery Capacity Tests._ This repoY't has nqt been revised to reflect al.l of the conments provided by your letter of April 3, 1979, because the Standard Technical Specifications were not impleni~nted.

This.evaluation will be a basic input to the integrated safety assessment' for your facility unless you identify changes needed to reflect the as-built conditions at your facility. Th.is topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before*the integrated assessment: is completed.

Sincerely, L nr'-'"""T~~

Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing

Enclosure:

. SEP Topic VIII-3.A cc w/enclosure:

See next page

.Mr. David P. Hoffman cc Mr. Paul A. Perry, Secretary

  • Consumers Power Corrpany 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power ColllJany 212 West Michigan Avenue Jackson, 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 Maple City, Michigan 49664 Charlevoix Public Library 107 Clinton Street Charlevoix, Michigan Chairman County Board of Supervisors Charlevoix County Charlevoix, Michigan 49720 Office of the Governor (2)

Room l - 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 Conmission 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 Conmission Washington, D. c. 20555 Big Rock Point Nuclear Power Plant ATTN:

Mr. C. J. Hart.man 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 #3, Btix 600*

Mr. Jim E. Mills Route 2, Box 108C Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety & Licensing Appeal Board

u. s. Nuclear Regulatory Conmission Washington, D. c. 20555

~;.. *.~

~-:

~* ____

I I

(

. ~--

-~-------- ---------

SEP TECHNICAL EVALUATION.

TOPIC VIII-3.A BATTERY CAPACITY TESTS FINAL*DRAFT PALISADES Docket No. 50-.255 December 1979 E. w. Roberts.

1322F 12-20-79

  • 'I
  • SEP TECHNICAL EVALUATION TOPIC VIII-3.A BATTERY CAPACITY TESTS FINAL DRAFT PALISADES Topic VIII-3.A Station Battery Test Requirements The objective of this review is to assure that the onsite *Class IE batteries have their capacity to supply all safety related D-C loads verified by periodic testing.

The testing should be in accordance with IEEE Standard 450-1975, IEEE Standard 308-1974, BTP EICSB 6, and the "Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors" (NUREG-0212).

The required tests are as follows:

(1)

At least once per 18 months, during shutdown, a battery service test should be performed to verify that the battery capacity is adequate to supply and maintain in operable status all of the actual emer-gency loads for two hours.

(2)

At least once per 60 months, during shutdown, a battery discharge test should be performed to veri-fy that the battery capacity is at least 80% of the manufacturer's rating.

The Palisades Nuclear Station battery surveillance requirements are incuded in Section 4.7.2 of the station Technical Specifications.

There are no periodic battery service and discharge tests required.

Therefore, the Palisades Nuclear Station does not comply with the cur-rent licensing requirements for station battery capacity tests.

This deviation will be evaluated in the context of the Design Basis Events (DBE) that rely upon these components for mitigating the consequences of the DBE.

If this deviation is determined to be unac-

" ceptable, the Technical Specifications will be appropriately revised.

1

l.

/~.... **.'\\

References *

1.

"Palisades Technical Specifications", Consumers Power Company.

2.

Standard Review Plan, Appendix 7-A, BTP EICSB 6, "Capacity _Test Requirements of Station Batteries--Technical Specifications,"

U.S. Nuclear Regulatory Commission.

3.

"IEEE Standard Criteria for Class IE Power Systems for Nuclear Pow~r Generating Stations," Std. No. 308-1974, The Institute of Electrical and Electronics Engineers, Inc.

4.

"IEEE Recommended Practice for Maintenance, Testing, and Replace-ment of Large Lead Storage Batteries for Std. No. 450-1975, The Institute of Electrical and Electronics~Engineers, Inc.

5.

"Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors," NUREG-0212, U.S. Nuclear Regulatory Commission.

2

Retrieved from "https://kanterella.com/w/index.php?title=ML18046A365&oldid=5024773"