ML20148J759

Monthly Oper Rept for Oct 1978

ML20148J759
Person / Time
Site:	Brunswick
Issue date:	11/02/1978
From:	Willis E CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20148J758	List: ML20148J750 ML20148J759
References
NUDOCS 7811160094
Download: ML20148J759 (9)

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l N-APPENDIX' DOCKET NO. ___

050-0325 UNIT Brunswick-No. 1

'DATE November 2,'1978 COMPLETED BY Eulis A. Willis BRUNSWICK NO 1 1

Brunswick No. 1 operated at 90.4% capacityftactor for tho month of October with'onc major power reduction for maintenance purposes and " load following" as per the dispatcher, keeping the unit from reaching full capacity.

i October 5 - Power was~ reduced to clean stator cooling

filters, i

The' monthly availability factor was 99.7% with'the unit.being'off-line 2.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on the first day of the month because of a required inspection (see Shutdowns and Power Reductions No. 033). '

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s 050-0325 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO..

e UNIT NAME : Brunswick - No. - l-DATE ' November 1, 1978 -

e" COMPLETED BY. Eulis A. ' Willis -

REPORT NONTif October 1978 TELEPHONE ~(919)' 457-6701 y

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1 N/A ZZ SUPORT To inspect-snubbers located 'in.the z

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~drywell as required by Technical.-

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' Specifications. Overtime was worked.

Inspected.and repaired snubbers as f

necessary. An improved snubber ~ test machine has been ordered which will reduce the time required.for snubber tests. Also, procedural. changes.are a

being implemented which will put BSEP in line with NRC interpretation of

- inspection requirements., Replaced retirculation' pump seals, replaced safety relief valve top works, and inspected -recirculation pump. dis- -

a charge safe end's.

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F: Forced Ruson:

Method:

Exhibit G -Instructions

- 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Dat.:

B-Maintenance ciIest 2-Manual Scram.

Entry Sheets for Licensee C-Refochng 3-Automatic Scram.

Event Report (LER) File (NUREG.

D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

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4 050-0325 DOCKET NO UNIT SHUIDOWNS ND POWER REDUCTIONS UNIT NAMf Bmswick No. ~1 DATE N ve=ber 2, 1978 COMPLETED BY Eulis A. Willis

' REPORT MONTH nenk-M78 TELEPHONE (919)457-6701 g.

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Cause & Corrective W.

Date r--

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• 781005 F

0 A

4 N/A HA FILTER Reduced power to clean stator cooling, filters. After change out and clean-ing filters, started increasing power and had to hold power at 59% due to being unable to place Reactor Feed Pump 'lAf on line.

Extensive trouble shooting of the 1A-RFP motor gear unit control circuit resulted in replacing the notor on the MGU.

After the maintenance was con-pleted Unit No. I was returned to 100%

~

power. The initial power reduction was to clean the stator cooling-filters which had a differential pressure of 18 iIsig; normal op is less than 5 psid, Overtime was worked, t

2 3

4 F: Forced Reason:

Method:

Exhibit C - Instructions S. Schedaled A-Fquipment Faihue (ExpLin) 1 -Manua!

for Prepara: ion of Data ll-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee.

C-Refueling Automatic Seram.

Event Report (LER) File (NUREG-D. Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examin4 tion F-Administ rative 5

G-Operational Ee ror (lixplain)

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to/77) li-Other (Explain) 1

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i APPENDIX DOCKET N0.

050-0324

}

UNIT Brunswick No. 2 DATE November 2, 1978 r

COMPLETED BY Eulis A. U'llis r

BRUNSWICK No. 2

-l Brunswick No. 2 had an av'ailability factor of 100% for I

the month of October, with a. capacity factor of 98.5%.

The only major power. reduction occurred on October 7, when power was reduced for-a periodic test and to clean condenser waterboxes (see Shutdowns and Power Reductions

. No. 29)~.

The unit was also " load following" as per the l

dispatchers request, another factor which attributed to the unit not' reaching full capacity.

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.s UNIT S!!UTDOWNS ND POWER REDUCTIONS DOCKET NO. 050-0324 UNIT NAME Brunswick No. 2 DATE Nm n-her ?

1078':

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REPORT MONT11 ne-enh-1978 TELEPHONE - (919)457-6701 E

E

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d $' ~

~ Licensee

,E g Cause & Currective No.

Date i

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.5 :_ 5 Event g3 gl Action to H

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Report r u) O c, O Prevent Recurrence f

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030' 781007 F

0 3

4 N/A HC

. HTEXCH Reduced Reactor power for MSIV period-ic test and waterbox 2A-North and 2A-South cleaning.

Performed MS1V periodic test,. cleaned 2A-North and 2A-South waterboxes, and returned to 100% power. Overtime was worked.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1 -Manual for Preparation of Data n-Maintenance of Test 2-Ma nual Scra m.

Entry Sheets for Licer.see C-Refueling Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Admiuist rative 5

G-Operational lin or (Eixpl. tin)

Exhibit I - Same Source (4/77)

!!-Other (Explain!

Mr. Boyce H. Grier, Director No.

2 h2/3L-0 Office of Inspection & Enforcernent, Region l U.S. Nuclear Regulatory Corrmi ssion p

631 Park Avenue d

King of Prussia, PA 19406

Dear Mr. Grier:

This LER refers to the failure of the inboard ma!n steam line drain isolation valve to close electrically which resulted in the closing of the redundant outboard isolation valve in accordance with Tech. Spec.

3 7.D.2.

Because this valve is inoperable, verification and recording of the position of the redundant isolation valve was begun per Tech. Spec.

h.7.D.2.

This is a condition of operating in the degraded mode as permitted by and reportable under Tech. Spec. 6.9 2.b.(2).

U. S. NUblE AR REGULATORY CoMMISSloN LICENSEE EVENT REPORT CONTROL BLOCK: l l

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l (PLE ASE PRINT oR TYPE ALL REQUIRED INFoRMATION 1

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i 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 C A T 58 CON'T loIil

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60 61 DOCKET NUMBE R M

69 EVEN T DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND pro 0 ABLE CONSEQUENCES h g gj j During start up cperations an attempt was made to close the inboard main l

steam line drain isolation valve (M0-2-7h) using the hand switch in the l

o ;3; l ntr 1 r

m. The valve failed to respond. The redundant outboard isolat j

Io I4 i L ion valve was placed in the closed position. Daily verification and re-l

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,g g(

cording of the outboard valve position was initiated in accordance with l

gl Tech. Spec. 3 7.D.2 and h.7.D.2. Safety significanco is minimal.

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