ML20010H418

Forwards Safety Evaluation of SEP Topic VII-6 Re Frequency Decay.Facility Meets Current Licensing Criteria

ML20010H418
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/21/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Linder F DAIRYLAND POWER COOPERATIVE
References
TASK-07-06, TASK-7-6, TASK-RR LSO5-81-09-058, LSO5-81-9-58, NUDOCS 8109240441
Download: ML20010H418 (4)

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September 21, 1981 N 1- @l I A,e

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Docket No' 50-409 LS05-81-09,052 L,Y fg g

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Mr. Frank Linder General Manager D61rylaed Power Cooperative p

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--La' Crosse, Wisconsin 54601

SUBJECT:

SEP TOPIC VII-6, FREQUENCY DECAY SAFETY EVALUATION FOR LA CROSSE The enclosed staff safety evaluation is based on a contractor document that has been made available to you previously. This evaluation is the staff's position regarding design of your facility in the subject area.

With regard to the referenced topic, the staff has concluded your facility meets current licensing criteria.

Sincerely.

l Dennis H. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

l As stated

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NRC FORM 318 (10-80) NRCM O243 OFFICIAL RECORD COPY usa m m _ m..so 4

r Mr. Frank Linder cc Fritz Schubert, Esquire U. S. Environmental Protection Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN: EIS C0ORDINATOR 230 South Dearborn Street O. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.

Mr. John H. Buck Washington, D. C.

20036 Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.

20555 La Crosse Boiling Water Reactor Dairyland Power Cooperative Dr. Lawrence P. Quarles P. O. Box 135 Kendal at Longwood, Apt. 51 Genoa, Wisconsin 54632 Kenneth Square, Pennsylvania 19348 Ms. Anne K. Morse Charles Bechhoefer, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Bosrd P. O. Box 1583 U. S. Nuclear Regulatory Commission La Crosse, Wisconsin 54601 Washington, D. C.

20555 La Crosse Public Library Dr. George C. Anderson 800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Secttle, Washington 98195 U. S. Nuclear Regulatory Commission Residerit 11spectors Office

.ir. Ralph S. Decker Rural Route #1, Box 276 Route 4, Box 190D Genoa, Wisconsin 54632 Cambridge, Maryland 21613 Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board Route 1 U. S. Nuclear Regulatory Commission Genoa, Wisconsin 54632 Washington, D. C.

20555 Chairman, Public Service Commission of Wisconsin Hill Farns State Office Building Madison, Wisconsin 53702 Alan S. Rosenthal, Esq., Chairnen Atomic Safety and Licensing Appeal Board j

U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. Frederick Milton Olsen, III l

609 North lith Street l

Lacrosse, Wisconsin 54601

e SYSTEMATIC EVALUATION PROGRAM TOPIC Vll-6 LA CROSSE TOPIC VII-6 FREQUENCY DECAY I.

Introduction _

. Issue 9 of NUREG-0138 states that the staff should require that a post-ulated rapid decay of the frequency of the offsite power system be included in the accident analysis and that the results be demonstrated to be acceptable..Alternativelf, the reactor coolant pump (RCP) circuit breakers should be designed to protection system criteria and tripped to separate.the pump motors from the offsite power system because rapid i

decay of the frequency of offsite power system has the potential for slowing down or braking the RCP thereby reducing the coolant flow rates to levels not considered in previous analyses.

II. Review Criteria The review criteria for reactor trip systems are presented in Table 7-1 of the Standard Review Plan.

III. Related Safety Tooics and Interfaces Set Points (Topic V?I-1.A) and Degraded Grid (Topic VIII-l.A) are relat-ed review areas that are outside the scope of this Topic.

Although Topic VIII-1.A is not dependent on the present topic for comp

• letion, the conclusions with regard to frequency decay should be compat-able.

IV. Review Guidelines l

l Issue 9 of NUREG-0138, " Staff Discussion of Fifteen Technical' Issues Listed in Attachment to November 3,1976 Memorandum from Director, NRR to NRR Staff," provides suitable guidance for this review.

V.

Evaluation, Oak Ridge National Laboratory (ORNL), under a technical assistance program, reviewed the frequency decay rate pheromena and its effects on RCP's. The results of the review are presented in Section 4 of NUREG CR 1464, " Review of Nuclear Power Plant Offsite Power Source Reliability and Related Recom-mended Changes to the NRC Rules and Regulations." In sumary, the report shows that the conditions required for dynamic braking of reactor coolant pumps are a sustained and rapid decrease in frequency while maintaining bus voltage. These wnditions are only realized in a highly capacitive system using large amounts of buried transmission cables (such as Long Island).

The Dairyland Power system does not use large amounts of buried transmission cable.

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. VI. Conclusion

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The conditions necessary fo.' an unacceptable frequency decay rate are -

not present in the La Crosse offsite electrical distribution system.

5 Accordingly,' the staff considars this issue not to be applicable to La Crosse.

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