ML18043A480
| ML18043A480 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/25/1979 |
| From: | Lewis J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7902200011 | |
| Download: ML18043A480 (6) | |
Text
7902200_0//
JAN 2 2 1979 Docket No. 50-255 Mr. David Bixel Nuclear Licensing-Administrator Consumers Power Company 212 West Mkhiqan Avenue Jackson, Michiqan 49201
Dear Mr. Bixel:
By letter dated Janm~ry 9, 1979!> which transmitted evaluation of nine Syste!latic Eva1uation Program topics for Palisades, we inadvertant1y included the evaluation of Topic VIII-3.A for Lacrosse.
In additi-on, a typographical er*ror appears on Page 15 of the evaluation for Safe Shutdown Systei11s (Topic VII-3). Therefore, we are enclosing the evaluation of Topic VIII-3.A for Palisades and a revised Page 15 for the evaluation of Topic VII-3.
We regret any inconvenience this error may have caused you.
Enclosures:
- 1. Topic VIII-3.A
- 2. Topic VII-3, Page 15 cc~
See next page 1so1sooo1K Sincerely, Original Si.~ns'3. "Jy:
Dennis L. Ziemaru1 Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors Oocket(50-255 NRC P Local POR ORB#2 ROG NRR ROG s1~rnx~~K OLZiemann RSilver HSmi th DELO OI&E(3)
OEisenhut TERA JRBuchanan ACRS(l6)
DDavis OFFICE~
SURNAME~
_g_g~2
~~?.
..................P.9.B.~.
.QB.~.~.?..........................................................................................................................................
- .. :~.~::::;:h:~.. ;;.:h:::::.: :.:8:?._j ___ ::~:~r..:......................R~z..t.~m.£.no.........................................................................................................................................
DATE~.... ~.!??!.?~................... ~.l.?.YJ~..................... Jl.?:?1...7.~..............
NRC FORM 318 (9-76) NRCM 0240 u: S. GOVERNMENT PRINTING OFFICES 1978 -
e26*624
Mr. David Bixel 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 0on~umers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 January 22, 1979
SYSTEMATIC EVALUATION PROGRAM BATTERY CAPACITY TESTS PALISADES DOCKET NO: 50-255 Topic VIII-3.A Station Battery Test Requirements The objective of this review is to assure that the onsite Class IE battery*
capacity to supply all safety related D-C loads is verified by periodic testing.
The testing should be 1n accordance with IEEE *standard.450-1975~ IEEE Standard 308-1974, BTP EICSB 6 and the HStandard Technical Specifications for Combustion Engineerinq Pressurized Water Reactors" (NUREG-0212).
The required tests are as follows.
- 1.
At 1 east once per 18 months, during shutdown, a battery service test should be perfonned to verify that the battery capacity is adequate to supply and maintain in operable status all of the actual emergency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 2.
At least once per 60 months, during shutdown, a battery discharge test should be performed to verify that the. battery capacity is at least 80%
of the manufacturer's rating.
The Palisades Nuclear Station battery surveillance requirements are included in Section 4. 7.2 of the station technical specifications.: There are no periodic battery service and discharge tests required. Therefore, the
'Pali sades Nuclear 'Station does n*ot ccrnply With the current licensing requ.i re-ments for station battery capacity tests *.
This deviation will be evaluated in the context nf the Design Basis Events (DBE) that rely upon these components for mitigating the consequences of the DBE.* If this deviation is determined to be unacceptable, the Technical Specifications will be appropriately revised.
References
- 1.
"Pali sades Technical Speci fications 11
, 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 Power Generating Stations", Std. No. 308-1974, The Institute of Electrical and Electronics Engineers, Inc.
- 4.
11 IEEE Recanmended Practice for Maintenance, Testing and Replacement 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 Cammi ssi on.
- and snow loading." *During the Provisional Operating License review, the staff conclud~d that the potential effects of tornadoes, floods, seiches, and-earthq~akes on structures and equipment important to*
safety were acceptable.
The effects of tornadoes will be reevaluated during the course of the SEP in Topics II-2.A 11Severe Weather Phenornena, 11 III-2 11Wind and icrnado-Loadings," and IrI-4.A i*Tornado Missiles.
11 The effects of flood on the Palisades Plant will be reassessed in the. SEP review under Topics II-3.B "Flooding Potential and Protection Requirements" and III-3 "Hydrodynamic Loads.
11 And within the SEP..
review, the pot~ntial for and consequerices of a seismic event at the Palisades site will b~ reassessed under several review topics.
GOC 3 requires structures, systems, and components important to safety to be designedand located to minimize the effects of fires
- and explosions.
Following a fire at the Brown's Ferry Nuclear Station in March 1975, the NRC reevaluated the Palisades fire protection program and issued the evaluation with License Amendment No. 42* dated September *1, 1978.
The resul_ts of this reevaluation will be inteqrated into the SEP assessment cif Palis~des Plant~
. I