ML19210C442

Monthly Operating Rept for Oct 1979

ML19210C442
Person / Time
Site:	Brunswick
Issue date:	11/09/1979
From:	Willis E CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19210C439	List: ML19210C438 ML19210C442
References
NUDOCS 7911140269
Download: ML19210C442 (11)

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. DOCKET NO. 050-0324 UNil SilUIDOWNS AND POWER REDiffilONS UNil NAh1E Brunswiciclinit. No. 2 DAIE EQVemhcr , 1922.

REPOR I 410 Nill October.1979 COMPl.E B ED ilY Eulis A. Willis IEl PilONE 119-457-9521 l

C N"

7., 3E 'b $ Ed I l'e nsce & *,, E9. Cause & Corsettive DJa c E, ~,? @ 2s5 livent U. ? 6? At ilon in F

fE 5 3g=

Repois c EC 2' Prevens Retunence g u o

020 791018 1 4.25 A 1 N/A CF litexch Reduced reactor power in preparation for placing the reactor in hot shut-down. The "B" Residual lleat Removal Exchanger had previously been'taken out of service due to a leak in a weld joint in the service water supply line. A lengthy temporary repair was required. While the repair was being made, the time permitted by Technical Specifications for the system being out of service expired, requiring ihat the unit be placed in hot shutdown.

Before the unit was removed from ser-vice, the repair was completed.

The leak was stopped with a temporary weld repair. Permanent repairs will b 3 ,,

completed during the 1980 refueling outage. Overtime was worked.

i 2 .I .I IL 1 ortetl Re non. hielln il .

S St hetinicil l.sinha G - Insoninons A.l~igmpnieni I:aihne (l.splain) I hlannal los Piepaiau.ni ol' Daia Il Alainicnance or Test .' hiannal Scr.un.

g; I un> Sheces hn I acensee C Reincimg .1 Antomanc S. sam. liens Rtposi11 i Hil ele INilRIG D-Regulatos) Rest ricnon

< -4 Othes llSpl.nu) 0161) l Operaios Iranung & I n ense i .s.unination ILAdnu m>n aine 5 N G Operational I nos (INplani) *

< I sinbH I - S.une Son ce P8/77) ll Othes (Ibplami a-A e i

J J J IINil' Silu lDOWNS AND i>OWI.It itFDilCilONS IH)CKET NO 050-0324 .

~ NAMlf _]}runswif;k Unit No. 2 DAIE _Hityember . 1979 Ett P O ll'8 M O N'lli October, 1979 COMI't.El ED llY _.Eulis A. Willis

., ,,, ,g g ,. 919_ g g 7,95 g c

-, 5g 'h j !!" Q I itensee H r,, {7, Cause & Conective No Dale r- 52 j yy 1:veni gy 4 9y Atesonto S jj d 3 y, =$ ltep.u s e A0 h' l'aevens Itceursence e o 6

t 021 791025 F 79.25 B 1 N/A 11C li texch Reduced power to repair leaks in A-South, ll-North, and ll-South water-boxes.

Waterboxes were inspected for leaks using the helium leak detection method .

A total of 50 leaking tubes were plugg ad .

A Ic.nk at the tube sheet joint in the

. 2B-North waterbox could not be im-mediately repaired; but it is current! /

being controlled such that the box can remain in service. It will be re-scheduled for repair when mat. rials .

arrive on site. Overtime was worked.

I 1 2 .I 1 l' 1:.n eil ite.non Mello,J.

I:xhibit G hesisucisons S St heduleil A lignipniene l'ailme(I xplain) 1 Manual los Psepaunon of Data lj 41.aintenance oi 'l es 2 Manual S. ram. linis) Sheets foi 1.kemce C ltelnelmg 4. Automatic Stiam. 1:. vent l<epois il l'Iti 1: ale INtilli G.

.y D llegulatoi> ltestiktion .I Olhes ll spl.sm) Otoll s 1. Opeu to Tsaining X i accine 1.unnnasion f I .Adnenatiative G O pe,.i,,,,n.a is,.iii spi.insi 5

rsiiihii i . S.nne S..n.ee l'8/ / 7 ) ll Othes 11:spl.sini LD

• i

APPENDIX DOCKET NO: 050-0324 UNIT UNIT: Brunswick Unit No. 2 DATE: November, 1979 COMPLETED BY: Eulis A. Willis OPERATIONS

SUMMARY

BRUNS *4ICK NO. 2 Brunswick Unit Ne, 2 had an availability factor of 1007. fer the month of October, with a capacity factor of 87.67.. Two major power reductions prevented a higher capacity factor for the =onth:

October 18 - Power was reduced in preparation to take the unit off line because of required maintenance to "3" residual heat removal heat exchanger. Repairs were completed before the unit was separated from the grid.

October 25 - Power was reduced to repair a leak in the condenser water-boxes.

Power was also limited in order to enhance an even fuel burn throughout the core cycle.

There are 132 BWR spent fuel assemblies and 91 FWR spent fuel asse=blies stored in the BSEP 42 spent fuel pool.

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'.7 'T

DOCKET NO. 050-0125 UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT N AM E Brunswick #1 DATE November 1979 D BY M IS L Wilb REPORT MONTil O('TOH FR 1979 TELErlf0NE (919) 457-9521 w.

No. Date o

g

.!'E 3g

);;

Y jgy Licensce Event

@r, gy a3

, Cause & Correceive Action su H

$5 5 e~dg Repor # mU !O u

Psevent itecurrence O

019 791008 F 18.2 A 3 N/A 'ZZ CKT8HK water level, caused by reduction of

. feed flow. The steam flow' signal to the feed control system was lost, causing the feed pur ps to run back.

A fuse in steam flow channel "A" was found loose in its holder, apparently causing a loss of the steam flow signal.

The fuse was inserted securely. Fuses in other steam flow instruments were checked on both units.' Personnel

. working in the area were cautioned about bumping panels containing steam ,

flow instrumentation. Permanent signs are being made to place on the panels cautioning personnel of the problems which can occur when they are bumped.

Overtime was worked.

I 2 3 4 F: Forced Reason: Method: Exlubis C . Instruenons S: Scheduled A Eituipment Faiture(Explain) 141anual for Picparaison of Dana

-3 B Maintenance or Test .

241anual Scram. Ents> Sheets for Liecosee 2 C Refueling 3 Automatic Scram. Event Repuri (LERI file INUREG-W D Regularory Restriction 4 Other (Explain) 01611 E Operator Training 1 License Examination N F Administrative 5 m G-Operational Ersor (Explain) Esinbii 1 - Same Source w 08/77) Il Other (Explain)

1 of 2 I

DO ET f

UNIT'SilulDOWNS AND POWElt REDUCTIONS c #1 DATE November 19Z9 COMPLEl ED 11Y Eulls A. Willis REPORT MONTil OCTOllER 1979 TELErilONE (919) 457-9521 i

e.

._ E g

, $E S ~ E ~4 Liecnsce [

'r, D. Cause 1 Corrective -

No. Date .i 58 $ , -: ~$ Evens Fy go3 Aciion Io I- jI E a~ g ;S: lleporg a nu o o Prevent itecurrence O

020 791019 F 140.5 A 3 N/A CG VAINiiX Reactor SCRAM on main steam line high

- radiation signal Channels A & B. The radiation source was identified as an increase in Nitrogen-16 carryover from the reactor water, caused by an injec-tlon.of filter demineralizer rpsin inii the reactor vessel during the return of the Reactor Water Cleanup (RWCU)

System to service following mainte-nance. NRC concerns required Atlanta

, meeting, which delayed the startup from 1600 on 10/21/79 to 0407 on 10/24/79.

The following corrective actions have been taken:

(1) Procedure Modification to OP-14 "RWCU" operating procedure, precaution, i 2 3 4 F: ForecJ Reason: Method: Exinttii G - Inst niaions S: Scheduled A t quipment Failure (Explain) l M.mual for Preparaimo of Daia y D.M.iintenance of Test .

2 Manu I Seram. Enir> Sheets for 1.ieensee

.s C-Refueling 3 Automalie scram. Eveni Repon (LERI File INUREG-

~

D Rerulatory Restriction 4 Other (Explain) 01611

• E-Operator Training 1 License Examination F Admini>irative 5 U G. Operational lirror (Explain) E.shibn I Same Source C gnj77} lt.Othe r ( E.splain)

C r"

2 of 2 DOCKET NO. 050-0325 UNITSIIUll)0WNS AND POWER REDUCTIONS UNIT NAME Ilrunswick #1 D.t l E November 1979 COMPLElED ay Eslis A. Uillis REPO!tT MONTil OCTOliER 1979 TELEPHONE (919) 457-9521

, .$ E S Y4 Licensee E 't . Causc i Corrective .

No. Date R 5g d ji$ Event Fy n3 Acuanto H j5 5 3.e g,=3 lleport s; <2 u gu Prevent itecurrence

. g ;: u 6

and changes to prevent recurrence.

0%0 (cont'd) (2) Temporary modification to GP-1,

" General Startup Procedure", to in-clude holdpoints for equipment and chemistry checks on return to power.

(3) Modifications to El-21 " Main Steam Line liigh Radiation", to,identi-fy possibility of resin intrusion.

(4) llodification of " Red Phone

. Procedure" to set down criteria for NRC notification.

. (5) Wrote and carried out Control Rod Drive Evaluation Program to assure no resin plugging.

(6) Development of a new Emergency Instruction El-47 for actions to be taken in the event of resin intrusion.

(7) Modification of RC&T Procedures 3240 and 1300 to provide better methotL of determining p!!. Overt ime was worket .

I 2 3 4

. F: Forced Itcason: Method: IIxhibit G - Instructions

. S: Seheduled A 1:quipment Failure (Explain) 1 M.niual for Prepasanon of Daia

_7 Il Maintenance of Test .

2 Manual Scrain. liner > Sheets for 1.icensee C Refueling 3 Automatic Scram. Event fleport (LERI Fate (NUREG.

• . " D-Ite;;ulatory Restrienion 4 Other(Explain) 0161)

E-Operator .iainingi License Examination U F Administrative 5 C G Operation.il 1:tror (Explain) Estubit I : Same Souree (9/77) Il Other (Esplain)

APPENDIX -

DOCKET NO: 050-0325 UNIT: Brunswick No.1 DATE: November 1979 COMPLETED BY: Eulis A. Willis OPERATIONS

SUMMARY

BRUNSWICK NO. 1 Brunswick Unit No.1 operated at a 697. capacity factor the :enth of October with two shutdowns preventing higher output: _

October 8 - The reactor scra=med because of low water level.

' "Down Time" was IS hours and 13 minutes.

October 19- Reactor scramned on main steam line high radiation signal. "Down Time" was 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> and 33 minutes.

Monthly availability factor was 78.77.. More detailed information on these outages is provided in the Unit Shutdown and Power Reductions Log (Appendix D), included as a part of this report.

There are 320 BWR spent fuel assemblies and 154 PWR spent fuel assemblies stored in the BSEP #1 spent fuel pool.

,,,9 302