ML20054M144

Requests Amend to Licenses DPR-71 & DPR-62 to Provide one-time Exemption to Requirements of Tech Specs 4.0.3 for Spec 4.3.3.1,Table 4.3.3-1,Items 5.a & 5.b Re Loss of Power Surveillance

ML20054M144
Person / Time
Site:	Brunswick
Issue date:	07/01/1982
From:	Howe P CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
References
NUDOCS 8207120005
Download: ML20054M144 (4)

Text

-

^

Sp&L Carolina Power & Light Company JUL 011982 Office of Nuclear Reactor Regulation ATTN: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 United States Nuclear Regulatory Commission Washington, D.C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT -

LOSS OF POWER SURVEILLANCE REQUIREMENTS

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Part 50.90 and Part 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Operating Licenses for Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The revisions are to provide a "one-time" exemption to the requirements of Technical Specification 4.0.3 for Specification 4.3 3 1, Table 4.3 3-1, Items 5.a and 5.b. Issuance of these revisions is being requested on an expedited basis to allow continued operation of Brunswick 1 in the interim until the required surveillances can be performed and to provide additional time in which to perform the required surveillances on Brunswick 2.

BACKGROUND During review of the June 28, 1982 Unit 1 scram caused by degraded voltage on emergency bus E-2 following the start of a circulating water pump, it was determined that the surveillance requirements for the undervoltage and degraded voltage relays of the loss of power circuitry had not been performed. Based on discussions on June 30, 1982 with members of the Staff and IE Region II, CP&L hereby requests a "one-time" exemption to the requirements of Specification 4.0 3 for performing the surveillance requirements of Specification 4.3.3.1, Table 4.3 3-1, Items 5.a and 5.b. A discussion of the basis of this request is provided below.

,/c/s</r '

jf y yeno oo C20712OOOS 820701 PDR ADOCK 05000324 P PDR a

411 FayettewHe Street

• P. O. Box 1551 e Raleigh, N. C. 27602 M4MGG: - " " M %LD.4LT M s M ua d M

a i

DISCUSSION As of July 1, 1982, two shift channel checks per unit have been performed with satisfactory results. These channel checks will continue to be performed each shift per Technical Specification Table 4.3.3-1 for each unit and are expected to continue to yield satisfactory results.

Carolina Power & Light Company will perform a channel functional test for the loss of power degraded voltage circuitry pursuant to Technical r Specification Table 4.3 3-1 as soon as a procedure is developed, approved by the Plant Nuclear Safety Committee (PNSC), and implemented. The channel functional test for Unit 1 will be completed no later than July 15, 1982. The Unit 2 channel functional test will be performed in conjunction with the channel calibration test prior to startup for Cycle 5 or July 15, 1982, whichever occurs first.

Carolina Power & Light Company will have a procedure for performing the channel calibration test developed, approved and implemented no later than July 7, 1982. The Unit 2 channel calibration test will be performed prior to startup for Cycle 5 or July 15, 1982, whichever occurs first. The Unit 1 channel calibration test will be performed following approval of the channel calibration procedure, but no later than July 15, 1982.

The loss of power circuitry is identical in design for both Unit 1 and Unit 2. Based on this similarity of design, and the expected satisfactory results for the Unit 2 testing, we believe the continued operation of Unit 1 in the interim is justified, pending final completion of the Unit 2 testing.

As demonstrated by the Unit 1 event discussed above, the Unit 1 degraded voltage relays will, in fact, separate the off-site power from the emergency buses in the event of degraded voltage on the off-site power supply.

l ADMINISTRATIVE INFORMATION You will find enclosed the proposed Brunswick 1 Operating License Paragraph 2.C.(2)(a) and the proposed Brunswick 2 Operating License Paragraph 2.C.(2)(b). The proposed Operating License revisions have been reviewed and approved by the Brunswick PNSC. We have evaluated this request in accordance with the criteria in 10CFR170.22, and believe this request involves a single technical issue; therefore, a Class III and a Class I license amendment fee are required for Brunswick 1 and Brunswick 2, respectively. Our check for $4,400.00 is enclosed in payment of these fees.

1 l

f k

- - - , - - - _ . , _ _ . . . . _ - - - . . - - - , - c---,- - ...-----.-.-.-1.-

I 1 ,

Should you have any questions regarding this matter, please contact us.

Yours very truly, G co.

P. W. Howe Vice President Technical Services WRM/1r (231c2T3)

Enclosure cc: Mr. J. P. O'Reilly (NRC-RII)

Mr. J. Van Vliet (NRC)

NRC Resident Inspector P. W. liowe, having been first duly sworn, did depose and say that the information contained herein is true and correct to his own personal knowledge or based upon information and belief.

/ A' ,,Yl /Mf/lfk Notary '(Seal)

My commission expires: OCT 041986 ' L[

h'

• s .

! [2%c

y. .

%)Ml

~'khEili&'Glbf' j

i

.- _. ~ .. .- .-.. - -__ _. -

. t ENCLOSURE 1 t

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 PROPOSED OPERATING LICENSE CONDITION i

Operating License Paragraph 2.C.(2)(a) '

i

, (a) Effective June 30, 1982, the surveillance requirements listed i.

below need not be completed until July 15, 1982. Upon ,

accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.

Specification 4.3.3.1 Table 4.3 3-1, Items 5.a and 5.b. .

t BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 PROPOSED OPERATING LICENSE CONDITION Operating License Paragraph 2.C.(2)(b)

(b) Effective June 30, 1982, the surveillance requirements listed ,

below need not be completed until restart for Cycle 5 or July 15, 1982, whichever occurs first. The unit shall not be l 4 operated in Conditions 1, 2 or 3 until the surveillance [

requirements listed below have been completed. Upon  !

accomplishment of the surveillances, the provisions of ,

Technical Specification 4.0.2 shall apply. [

i Specification 4.3 3 1, Table 4.3 3-1, Items 5.a and 5.b i i

t I

i t

b 1 r

?

r i

i i

. . . - . . . . . _ _ . _ _ _ _ _,._.. -.__.-._ _ __. _ .._.__ _._._ .__ ._ _ .,_ _. ~ ._ . . _ , . . _ , . . . . _ _ . . . . . . _ . _ . . - _ . . . _ . . . _ , . _ _ .

_