ML20138R686

Monthly Operating Repts for Aug 1985

ML20138R686
Person / Time
Site:	Browns Ferry
Issue date:	08/31/1985
From:	Robert Lewis, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8511180753
Download: ML20138R686 (31)

Text

{{#Wiki_filter:. _ - . -. ~ -{ i l TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT 1 i i MONTHLY OPERATING '.02 TO NRC August 1, 1985 - August 31, 1985 4 i DOCKET NUMBERS 50-259, 50-260, AND 50-296 i 1 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 j j t Submitted by: d#v/4/ Acting Plant Manager f ) t l 0511180753 850031 PDR ADOCK 05000259 1 R PDR l

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LI i i TABLE OF CONTENTS i Operations Summary.................. 1 Refueling Information.................... '. 3 Significant Operational Instructions. 5 Average Daily Unit Power Level................. 8 Operating Data Reports..................... 11 4 Unit Shutdowns and Power Reductions.............. 14 1 Plant Maintenance..... 17 i Modifications (July and August)................ 24 l 4 .i I i 1 I f ir I i Q ( .. -. -. -. - 1

1 Operations Summary August 1985 The following summary describes the significant operation activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report. There were twelve reportable occurrences and no revisions to previous occurrences reported to the NRC during the month of August. Unit 1 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 refueling outage. Unit 2 The unit was in culd shutdown the entire month for the unit's end-of-cycle 5 refueling outage. Unit 3 The unit was in cold shutdown the entire month on an administrative hold to resolve various TVA and NRC concerns. Prepared principally by B. L. Porter. e

e 3 Operations Summary (Continued) August 1985 Refueling Information Unit 1 Unit 1 was in shutdown for its sixth refueling on June 1, 1985 with a scheduled restart date of March 31, 1986. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and environmentally qualify instrumentations. The unit was shut down on March 19, 1985, and remained in cold shutdown until June 1,1985, because of unfinished modifications to meet environmental concerns. There are 504 assemblies in the reactor vessel. The spent fuel storage pool presently contains 260 EOC-6 assemblies, 252 EOC-5 assemblies, 260 EOC-4 assemblies; 232 EOC-3 asse=clics; 156 ECC-2 assemblies; and 168 EOC-1 assemblies. The present fuel pool capacity is 3,471 locations. Unit 2 Unit 2 was shut down for its fifth refueling outage on September 15, 1984 with a scheduled restart date of December 31, 1985. This refueling outage will involve loading additional 8X8R (retrofit) assemblies into the core, finishing torus modification, turbine inspection, piping inspection, THI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection. There are no assemblies in the reactor vessel. At month end, there were 273 new assemblies, 764 EOC-5 assemblies, 248 EOC-4 assemblies, 352 EOC-3 assemblies, 156 EOC-2 assemblies, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 77 locations. All old racks have been removed from the pool and new HDR's are being installed.

1 Operations Summary August 1985 The following summary describes the significant operation activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report. There were twelve reportable occurrences and no revisions to previous occurrences reported to the NRC during the month of August. Unit 1 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 refueling outage. Unit 2 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage. Unit 3 The unit was in cold shutdown the entire month on an administrative hold to resolve various TVA and NRC concerns. Prepared principally by B. L. Porter.

2 Operations Summary (Continued) August 1985 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows: Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629 0.14326 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements. Common System Approximately 1.19E+06 gallons of waste liquids were discharged containing approximately 4.53E-02 curies of activities. C

, ~ _ ._.m < ~ . = 4 3 Operations Summary (Continued) { August 1985 Refueling Information U_ nit 1 Unit 1 was in shutdown for its sixth refueling on June 1, 1985 with I a scheduled restart date of March 31, 1986. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and environmentally qualify instrumentations. The unit was shut down on March 19, 1985, and remained in cold shutdown until June 1,1985, because of unfinished i l modifications to meet environmental concerns. l { There are 504 assemblies in the reactor vessel. The spent fuel storage l pool presently contains 260 EOC-6 assemblies, 252 EOC-5 assemblies, 260 EOC-4 assemblies; 232 E0c-3 assemblies; 156 EOC-2 assemblies; and 168 EOC-1 l assemblies. The present fuel pool capacity is 3,471 locations. Unit 2 l Unit 2 was shut down for its fifth refueling outage on September 15, 1984 1 1 with a scheduled restart date of December 31, 1985. This refueling outage will i ) involve loading additional 8X8R (retrofit) assemblies into the core, finishing I i torus modification, turbine inspection, piping inspection, TMI-2 modifications; l post-accident sampling facility tie-ins, core spray change-out, and feedwater l sparger inspection. There are no assemblies in the reactor vessel. At month end, there were 1 l 273 new assemblies, 764 EOC-5 assemblies, 248 EOC-4 assemblies, 352 E0c-3 i assemblies, 156 EOC-2 assemblies, and 132 EOC-1 assemblies in the spent fuel j storage pool. The present available capacity of the spent fuel pool is 77 ~ locations. All old racks have been removed from the pool and new HDR's are ( j being installed. l 1 -.- -..-. - - -...- -.~.-

4 Operations Summary (Continued) August 1985 Unit 3 Unit 3 is scheduled'for its sixth refueling outage approximately November 30, 1985, with a scheduled restart date of November 10, 1986. This refueling involves loading 8X8R (retrofit) assemblies into the core, and complete reinspection of stainless steel piping. The unit was shutdown on March 9, 1985, and will remain in cold shutdown until November 30, 1985, on an administrative hold to resolve various TVA and NRC concerns. There are 764 assemblies presently in the reactor vessel. There are 248 ' OC-5 assemblies, 280 EOC-4 assemblies,124 EOC-3 assemblies,144 EOC-2 E assemblies, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations. 2 l f O

5 August 1985 Significant Operational Events Unit-1 8/01/85 0001 End of cycle-6 refuel outage continues 8/31/85 2400 End of cycle-6 refuel outage continues 4 4 l e 1 h

6 August 1985 Significant Operational Events Unit-2 8/01/85 0001 End of cycle-5 refuel and modifications outage continues 8/31/85 2400 End of cycle-5 refuel and modifications outage continues i S" l .m m

e 7 t August 1985 Significant Operational Events Unit-3 8 /0 1/85 0001 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved. 8/31/85 2400 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved. 9 s, i I e f 1 1 i

._.,.,_.u..__. 8 AVER \\GE DAILY UNIT PO%fR LEVEL DOCKET NO. 50-259 UNIT Browns Ferry 1 9-1-85 DATE COMPLETED BY T. Then TELEPHONE 205/729-2509 4 MONT13 Aumist l' DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL 3 iMWe Net) iMwe. Net) -10 -10 g7 2 -10 is -10 3 -10 19 -10 4 -10 20 -11 5 -10 21 -10 6 -10 22 -9 7 -10 23 -10 3 -10 24 -10 9 -10 25 -9 -10 10 26 -11 II -10 27 -10 I 12 -10 g -10 13 -10 -10 39 34 -10 30 -11 IS -11 -9 33 16 -11 INSTRUCTIONS On thitforrnst. list the sverage do!> umt p.mc levelin MWe. Net for each day in the reportir.g month. Compute to the nearest whole nwgtwatt. { ("/77 )

a... ._+4 a -__u 9 AVER AGE D LILY UNIT POWER LEVEL 50-260 DOCKET NO. Browns Ferry 2 gj7 DATE 9-1-85 T. n om CO%fPLETED EY ) TELEPHONE 205/729-2509 MONTH August f j DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe Neti IMWe %t) g -3 17 -2 2 -2 is -2 3 -2 -2 9 ~2 4 -2 20 5 -3 -2 -2 6 -3 '2 -3 7 -2 3 s -3 -4 24 9 -2 -6 25 -2 t -6 Io 26 11 -2 27 -6 12 -2 -6 33 ~3 -6 13 29 14 -2 30 -6 15 -3 31 -6 16 -2 4 INSTRUCT 10NS On thi<furmat.1:st th: average dah uni! Pirwer Icvelin Mwe.Nei for eJch aa). in the sepuenn; non:h. Compute to the nearest whole meg 1 wart, i (0/77) i i

^^ l I 10 AVER AGE DAILY UNIT POWER LEVEL DOCKET No. 50-296 UNIT Browns Ferry 3 DATE '9-1-85 T. Thom COMPLETED BY TELEPHONE 205/729-2509 MONTH Austust DAY AVERAGE D AILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL iMWe NetI (MWe. Net) -9 -9 ,7 2 -9 g3 _9 3 -8 g9 _9 -9 4 20 -9 5 -9 3 9 6 -9 3 _9 7 -9 g -9 8' -10 24 -10 9 -9 25 -9 -9 10 26 -9 -9 II -10 27 3: -10 _9 -9 13 -9 39 } 34 -9 30 -10 15 -9 _g y, . 16 -9 INSTRUCTIONS On ihnfarmat. list the aserage J41) unit rinver lese! in MWe. Net for exh day in il e seporting monih. Compute tu the nearest who!c mcpwaii. (9 /77 ) l t.

g =. ~. 11 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 9-1-85 CO\\lPLETED BY T. Th or-TELEPHONE 20s/729-2509 OPERATING STATUS

1. Uma Name:

Browns Ferry One N"8"

2. Reporting Period:

Aunust 1985

3. Licenwd Thermal Power (Mht1:

3293

4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating INet MWe):

1065_

6. Masimum Dependable Capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Rea>ons:

N/A 9 Power Lesel To Which Restricted.lf AnyINet MWe): N/A ~

10. Rea,ons For Restrictions. lf Any:

N/A This Month Yr..to Date Cumulative

11. Ilours in Reporting Period 744 5,831 97,231 j

12. Number Of Ilours Heactor Was Critical 0

1,647.78 59,521.38

13. Reactor Rewrie Shutdow n Ifours 0

512.22 6,997.44

14. Hourt Generator On Line 0

1,626.67 58,267.26

15. Unit Newne Shutdown flour, 0

0 0

16. Grow T!vrmal Energy Generated (MWHI O

4,950,821 168,066,787 ~ 17 Gron Electrical Energy Generated (MWHI O 1 6s2.6sn 55.398.130

18. Net E!ccarical Energy Generated IMbil)

-7.471 1.567.725 _53,781.546

19. Unit Senice Factor 0

27.9 59.9

20. Unit Asailability Factor 0

27.9 59.9

21. Unit Capacity Factor IU>ing MDC Net) 0 25.2 51.9

22. Unit Capacity FactorIUsing DER Net) 0 25.2 51.9

23. Unit Forced Outage Rate 0

55.1 23.6

24. Shutdowns Scheduled Over Nest 6 Months IType. Date,and Duration of Each t:

25. If Shut Dawn At End Of Report Period. Estimated Date of Startup:

9/14/80

26. Units in Tnt Status IPrior to Commercial Operationi:

Forecast Achiesed INITI A L CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPER ATION 19/77)

~- 12 OPERATING DATA REPORT 50-260 DOCKET NO. DATE 9-1-85 COMPLETED BY T. Th on TELEPHONE 205/729-2509 OPERATING STATUS Browns Ferry Two Notes

1. Unit Name:

2. Reporting Period:

Aunust 1985

3. Licensed Thermal Power (MWt1:

3293

4. Nameplate Rating (Gross MWe):

1152 1065

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

1098.4 1065

7. Mnimam Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report.Gise Reawns:

N/A

9. Power Lesel To Which Restricted. If Any (Net MWe):

N/A 3

10. Reasons For Restrictions. If Any: N/A This Month Yr.-to-Dat e Cumulative

11. Hours In Reporting Period 744 5,831 92,118

12. Number Of Hours Resctor Was Critical 0

0 55,860.03

13. Reactor Resene Shutdown Hours 0

0 14.200.44

14. Hours Generator On.Line 0

0 54,338.36

15. Unit Reserve Shutdown flours 0

0 0

16. Gross Therma! Energy Genereted (MWH) 0 0

153,245,167 17 Gross Electrical Energy Generated (MWH) 0 0 50,771,798

18. Net Electrical Energy Generated (MWH)

-2,437 -20,004 49,282,969

19. Unit Service Factor 0

0 59.0

20. Unit Avadability Factor 0

0 59.0 U U

• • 4

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 0 0

50.2

23. Unit Forced Outage Rate 0

0 23.0

24. Shutdowns Scheduled Over Nest 6 Months ! Type. Date.and Duration of Eacht:

25. If Shut 1)own At End Of Report Period. Estimated Date of Startup:

December 24, 1985 l

26. Units in Test Status (Prior Io Commercial Operation):

Forecast Achiesed l ~ l INITIA L CRITICALITY l INITIA L ELECTRICITY CO\\lMERCIAL OPER ATION 1 l l (9/77)

~ ~ 13 OPERATING DATA REPORT j DOCKET NO. 50-296 DATE 9-1-85 U5 /75-2509 EL PHO, OPERATING STATUS

1. Unit Name:

Browns Ferry 3 Notes

2. Reporting Period:

August 1985

3. Licensed Thermal Power (MWt):

3293 1152

4. Nameplate Rating (Gross MWe):

1065

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

in9R.4

7. Maximum Dependable Capacity (Net MWe):

1065

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Re: sons:

N/A

9. Power Level To Which Restricted. If Any (Net MWe):

N/A

10. Reasons For Restrictions. lf Any:

N/A This Month Yr..to.Date Cumulatise

11. Hours In Reporting Period 744 5,831 74,543

12. Number Of Hours Reactor was Critical 0

1,517.65 45,306.08

13. Reactor Resene Shutdown Hours 0

508.05 5,149.55 I4. Hours Generator On.Line 0 1,496.96 44,194.76

15. Unit Reserse Shutdown Hours 0

-0 0

16. Gross Thermal Energy Generated (MWH) 0 4,649,840 131,868,267 i

0 1,572,770 43,473,760

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH).

-6,642 1,492.119 42,157.880

19. Unit Service Factor 0

25.7 59.3-

20. Uni Availability Factor 0

25.7 59.3 "*U 53*1

21. Unit Capacity Factor (Using MDCNet)

22. Unit Capacity Factor (Using DER Net) 0 24.0 53.1

23. Unit Forced Outage Rate 100 74.3 23.6

24. Shutdowns Scheduled Over Nest 6 Months (Type, Date,and Duration of Each):

t

25. If Shut Do4n At End Of Report Period Estimated Date of Startup:

Harch 87

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiewd INITI \\ L CHITICA LITY INITIA L ELECTRICITY COMMERCIA L OPER ATION i (4/77)

tlNITSilUTUOWNS AND POWER REDl!C110NS DOCKET NO. 50-259 UNIT NAME Browns Ferry 1 DATE 9/1/85 REPOR T MONTil Ancust. COMPLETED BY T. Thnm TELEPilONE 205/729-2509 T u. : 5 ). c r. 7 54 l s.cernce C-t, 2e E g3 Cause & Correceive No Dale g 3s 4 j :,,: y lACH3 %7 9-Action lo i $E 5 j 5, llePort "

• E 0 j

Prevent Recurrence C 315 8/1/85 S 744 C 2 End of cycle 6 refuel outage (Cont) continues. E i ( 4 i 5 1 2 3 4 I~: Forced Rew.n: . Method : I:shibii G - Instructi.m S: S(hedt. led A-l.quipment I ailure a l'*l: fred I 41 tnual for Psepar.Hion of D.ita Il-Mainte:cince i.r 'l est .Mianual Scrarn, lintr) Sheets for I.seensee 4 C-Refurinig 3-Autoin. die Scram. I-vent Repoo (1.1 R)l'ite (Nt;RI c. D Reputatus) Resistein.n

4. Oil cr (I.splain )

olog) 4 I:-Operator Iraining & 1xrn.c l samnutson F AJnunnerati.e 5 G Ogeration.:1Iiresa1.xplai.i) 19/77) Il Ort es (1 splains I stubu I - S.iini s. urce i

9 UNIT SilUTDOWNS AND POWER REDUC 1 IONS DOCKET NO. 50-260 UNIT NAh1E Browns Fe ry 2 DATE 9-1-85 REM)RT hf0NTil Aimunt COhlPLETED BY T Timm TELEPflONE _205 /729-2509 C ea 3 :s. O h .2 = 7sx Licensee g r, gg cause A cuirective No. Date g 3g

(

jg5 Event ? ^9 ss 'E Action to 5 2., 3p= Report = <E C 53 ' Present Recurrence v e 6 305 8/1/85 S 744 C 4 EOC-5 refuel outage (Cont) (controlled shutdown) 9/15/84 G 3 f 4 t I 2 3 4 F: Forced Reason : h1cthod: INlubit G Instrucinms S: Schedulnl A. Equipment Failure (Lxplaml I klanual tor Psepar.its.in of Data D. Alaintenance or Test .' hlanual Scram. 1.nts) Sheets for Liccinec i - C Retuchng 3 Automatic St ram. livent Report il i 10 File INUHl.G-D. Regulatory Rest:ittion 4.Oiher ( thplain ) 01011 i l'-Opera to: 'l e.iis on3& l.stenw I samination F Adnunistratr.e i 5 G-Operational I tri:t tI splaial e'#!77) Il-Other 11.spla.n l l'sh.bii 1 Same Source 1 i 3

UNIT 511U1 DOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT NAME Browns Ferry 3 DATE 4-1-Rs REPORT MON ni Aunust COMPT.ETED BY L._Thom TELEPHONE 205/729-2509 = ce E u, N.. Dale E_ hN @J. Cause & Correctise o p =.2 .j 5=% g'0"3 1,2 c Atsion to y d5 j IICP"'I " 'M V j' Prevent Recurrence OO M d 156 8/1/85 F 744 F The unit remains on administrative (Cont hold until various TVA and NRC concerns are resolved. E 2 i 2 1 4 l': l'e n ced Reamn: MethoJ: INlubit G - Intt ructio.is S Sc hed ulett A-L.piipment !!ailuse(larlain) 1 -M in ual foi Piepaiation of Data B Maintenance oi Tes: 2 Manuel Scram. Entr> Sheets f or 1icensee C Refuchng LAutomauc Scram. I%eni 1:epon eI l'Ril'ile iNI!RI G. D Regul:.iosy Hesi icuou 4 Othent!' pt.unt 0101) a i l' Operator hainmg & I ntense I umia s' ion I Adnunist ratr.e 5 G OperJttuual l's tot t I si'lat.il l'sh'hil 1 - SJme Soulie rejil) Il-Ot hes (l~ xplain) 9

E3') G CG] G CTW G Q Q Q Q Q C M QPagb =*a BRO!GS FERRY E4UCLEAR PLANT UNIT 0 BF D1SIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SDP!ARY Appendix B 9/29/82 For the !!onth of August 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude Date Svstem Component Maintenance The Reactor Malfunction Malfunction Recurrence 1985 7/16 Radiation PMP-90-0152A Troubleshoot None Motor winding bad Motor would not run Motor rebuilt at monitoring stack sample stack sample Power Svc Shop pump B1 pump B1 1R 566809 MR 582336 1663 BFN 85-182 8/2 Off gas !!TR-65-0060 Troubleshoot None lleaters burned '! eaters not working - Replaced heaters standby gas and repair out treatment charcoal fir 589769 control heater neaters for filter train C 8/14 EECW FCV-67-0005 Troubleshoot None Bad valve motor Valve would not Replaced valve rrotor EECW strainer to identify operate I backwash dis-oroblem MR 588751 charge valve L l

l M

M E G E G C LD C C3 U ~.L.J 8 C C C Pag BP,0NNS FERRY NUCl. EAR PLANT UNIT 1 BF EMSIL 30 Appendix B CSSC EQUIPME;IT ELECTRICAL MAINTENANCE

SUMMARY

9/29/82 For the Month of August 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1985 6/28 Radwaste LS-77-25C Inspect switch None Missing internal Flood level switch (teplaced superseded RHR pump room for 1 ose and/ parts was not ope,ra t ing level switch model flood level or missing

1. 351 with model #352 switch hardware FACF 1-85-021-77

fR 582415 7/19 Reactor SBM switch on Repair cut wire Several engi-Panel door Fuse FB-6 blew itepaired wire protection battery board on terminal #2 neered safety pinched insula-resulting in loss of 1R 556010 system No. I compart- (normal to features tion when closed RPS MG set B, caus-ment 9 alternate) initiated

& wire shorted ing group 2, 3, 6 & 8 "ER 259/85037 to ground isolations y 8/26 Standby CEN-082-000B SI 4.9.A.1.a None Unknown Idle speed out of teduced idle speed diesel diesel genera-D/G nonthly specification per SI from 470 RPMs to ]- generator tor B, units check 450 RPMs 1 and 2 ",j MR 571826 ~f 2 t I s, a r O e 5

E E C GD C C C C C C C C C C O - C C p BP0! INS FERRY NUCI. EAR Pl. ANT UNIT 3 BF D!SIL 30 CSSC EQUIP:!ENT ELECTRICAL MAINTENANCE SOf fARY ^EE# 9/29/82 For the Month of August 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude Date Systeci Component tra in tenance The Reactor tfalfunction Pfal func t ion Recurrence 1985 8/7 Radiation RE-90-0143 Surveillance None Bad connector Radiation monitor Repaired pins A & E monitoring reactor zone instruction at end of cable not operating on connector plug exhaust radia-4.2.A-10 going to RE tion detector 143 MR 180799 channel B 8/10 Fire XS-39-106EF Surveillance None Bad detector No alarm came in on Replaced detector protection CB, el 593 instruction detector whcn tested battery rm 4.11.C.1 & 5 t!R 572524 zone E smoke detector G 7/18 Contain-Analyzer Investigate None Bad pump on Pump very noisy; Replaced pamp/ motor ment sample. return excessive noise analyzer failure anticipated assembly i inerting pump !!R 571946 k l 9 p l

BROWNS FERRY NUCLEAR PLANT UNIT CSSC EQUIPMENI MECHANICAL MAINTENANCE

SUMMARY

For the Month of' Aimnnr 19 ns EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8/5/85 84 IICV-554 Repair Leak Age and normal 1R 176643 repair use ed valve 8/5/85 84 IICV-555 Repair Leak Age and normal MR 176644 repai use ed leak }8/5/85 84 CKV Repair Leak Age and normal MR 176645 use repaired 31eak I I:$ 9 l l

k BROWNS FERHY NUCLEAR PLANT UNIT I CSSC EQUIPMENT l'ICHANICAL MAINTENANCE

SUMMARY

For the Month of August gg 85 t EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS GF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE None w W e o D

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~ 24 SHUTDOWN UNITS' MONTHLY REPORT MONTHS OF JULY - AUGUST 1985 Unit 1 Status: Shutdown date: March 19, 1985 Turbine: 1 "B" LP turbine disassembly started July 6. The spindle was shipped offsite to the Power Service Shop for rebuild on July 23. Refuel Floor: Fuel pool gates were opened on July 31. Fuel offload started August 15. As of August 30, 267 of 764 bundles were offloaded. Days shutdown as of August 31: 165. Outage Day: 91 Unit 3 Status: Shutdown date: March 9, 1985 As of the first week in August, priority on returning unit 3 to service ceased and was shifted to completing the unit 2 cycle 5 refueling outage. Completed work on unit 3 was identified, as was aborted (until the unit 3 cycle 6 refueling outage) work and unit 3 ongoing work to be carried over to the unit 2, cycle 5 refueling outage schedule. Unit 3 will remain shutdown until its outage starts. It will not require a reload of fresh fuel. Days shutdown as of August 31: 175. Unit 2 Status: Shutdown date: September 15, 198% Return to service: Target - December 24, 1985. Scheduled - February 1, 1986 A. Turbine: The unit 2 turbine building crane is still not in service. Recoupling of turbines remains outstanding. B. Refuel Floor: The core is unloaded and the cavity is flooded. Setting of four Westinghouse fuel bundles in the fuel pool, reload, changeout of LPRMs SRM/IRM dry tube replacement, and assembly remain outstanding. C. Drywell/ Steam Tunnel; remaining major work: Complete work on "B" I/B and both "C" MSIVs. Re - LLRT all valves. Remove valve 69-579, machine it, and reweld it in the process pipe. ~ Reinstall MSRVs. Rebuild MSRV vacuum breakers. Changeout recire. pump shaft seals. Repair weld DSRHR-2-5A. Replace RWCU suction pipe.

a 25 Replace two electrical penetrations for ECN P0324. Replace one drywell airlock penetration. LPRM changeout. Install TIP tubing. Complete ECN P0415; feedwater t,emperature monitors. Walkdown vessel level instrument sensing lines. Complete ECN P0284; MSRV accoustic monitors charge converters. Reinstall SRMs & IRMs which were defective and removed. Drywell coolers maintenance. Remove vessel head spray piping. Inspect jet pump instrument line nozzle drywell penetrations. Replace interferences removed for ISHI. Replace valve 73-45. Analyze and modify MSRV air sensing lines (ECN P0612). Install high level radiation monitors (ECN P0324). Complete replacement of valves 3-98 & 3-99. ILRT & RPV hydro preps. Replace insulation removed for IHSI. Hanger Inspections / Repairs. D. Torus Fill Preps: Remaining identified major work. Install wide-range level sensing lines (ECN P0323). Minor work associated with ECN P0093. Rework narrow-range level sensing lines. Stroke single-isolation valves from the torus below normal water line for operability. Install seismic shims. Install torus snubbers (operability). Painting touchup. W ,e-- -m

~. 2 26 E. Unit 2 modification by type, by ECN. MECHANICAL L1970 EECW Piping o% P0083 RHR Seal HX 80% i P0093 ' Remaining Torus work 90% P0126 Mech. Supp't for Elec. Mods 0% P0271 Rem. packing bleed-offs 0% P0323 - Torus level instr. 0% P0354 Stack monitoring - piping 0% P0361 Attached piping supports 75% P0392 CRD - Syst. Mods 70% l P0555 Torus Painting, heateure 90% i P0569 RPV - Vent valves 70% P0598 Security Mods 99% P0611 MSRV - Fig. machining 95% P0625 Misc. Vent / Drain Supports 0% P0652 Replace 71-40 Os P0666 1" RHR by-pass 60% ~ _P0669 Sprinkler system Mods Os j t i P0671 Sprinkler system Mods 0% P0684 Torus Vac. Brkr. - Mods 40% P0697 HVAC Mods - Control Bay 60% P0651 Replace 73-45 Os P0724 Rem. RHR HD Spray 0% ) P2085 Attach Piping Document 04

P3002, Replace 43-13 Os y

P3043 " Modify 64-9/10/40/41/42/43 0% 1 P3046 Modify 64-139/140/141 0% P3069 Modify 75-57/58 Os P3130 Modify 32-62/63 0% P3134 Modify 64-31/34 Os P3135 Replace valves on PNL 0% P3140 Replace 64-31/34 0% P3148 H7AC Mods 0% 1 P5316 Rem. Snubber Lugs 50% P5049

• Install Rad Monitor 0%

PS213 Modify 73-24 and 71-32 0% r ECNs COMPLETED 4 P0157 Cap and Rem. 1" EECW piping j P0612 MSIV - Mods P0613 MSIV - Mods P0614 MSIV - Mods P0646 DSL Generator Mods, U/1-2 P0688 Modify 76 and 84 series valves P0720 JPI Nozzle I i w i i -n n, -n..,

v s 3 27 ( ELECTRICAL ECM DESCRIPTION PERCENT COMPLETE Ll791 Modify control of SJAE 15 P0085 Upgrade drywell temp 70 P0112 Instl Thermal PWR monitor 0 P0126 Analog trip system 60 P0203 Rewire internals of PNL 25-31 100 P0272 Reroute wire for IRME 100 P0284 Upgrade acoustic monitoring sys O P0322 Upgrade containment press. sys 80 P0323 Upgrude torus level 80 P0324 Upgrade containment radiation monitor sys 40 P0354 Upgrade off gas monitoring sys 30 P0392 Qualify switches of scram discharge sys 70 P0399 Resolve I&C bus problems 30 PO415 RPV feedwater nozrle temp instr 45 PO417 Remove internal wire in control cab 100 PO418 Replace CRO S/D air heacer P. S. O PO422 RPS circuit protector 0 P0511 Relocate RB emergency light transformer 0 P0532 Replace T/D relay 0 P0533 Upgrade torus temperature sys 90 P0567 Replace diodes 0 { P0598 Upgrade control bay doors 100 P0600 Remove clips from recirc MG sets 0 iP00)1 Move RHRSU inline detectors 0 P0672 Remove wire from panels 25-5A & 6A 100 P0697 Upgrade HVAC system 0 P0706 Replace pwr supplies for ECCS 0 P0707 Replace pwr supplies for RPS 0 P0712 Replace unit preferred transformer 50 P0724 Rem head spray pipe O P0737 Replace elect penetration to D. W. O P0738 Upgrade access control 99 P0752 Remove static press limiters O P0753 HPCI cable separation 0 P0820 Change MCC internal wiring 99 P0828 Add fuses for recire MG sets O P0831 Revise 120/240 VAC emergency tie O P0834 Adjust magnet setting of load brkr 0 P0837 Add / replace brkr/ckt of cables O P3006 Replace press switches 96 P3019 Replace press switches 96 P3022 Replace press switches O P3023 Replace press switches 96 P3025 Replace press switches 96 P3026 Replace press switches 0 P3028 Replace press switches 96 ]

~ 4 28 Electrical ECN DESCRIPTION PERCENT COMPLETE P3040 Replace flow solenoid valves 96 P3051 Replace switches ,0 P3053 Replace switches O P3058 Replace switches O P3061 Replace switches O P3064 Relocate pwr supplies O P3084 Replace switches 96 P3085 Replace switches 96 P3087 Replace switches 96 P3092 Repl, ace switches 96 P3098 Replace switches O P3104 Replace switches 96 P3106 Replace switches 96 P3112 Replace valve components O P3113 Replace valve components O P3114 Replace valve components O P3115 Replace valve components 0 P3116 Replace valve co.?ponents O P3117 Replace valve components O P3118 Replace valve components O P3138 Replace RHR pmp room cooler 100 P3139 Replace C3 pmp room cooler 100 P3142 Add pressure indicators O ( P3145 Previde conduit scalc 0 P3148 Qualify SD bd room cooling 0 ' P5141 Remove instruments used during D. W. leak rate tests 100 P5192 Replace annunciator window in C. R. 100 P5209 Replace annunciator window in C. R. 100 PS210 Replace annunciator window in C. R. 100 h J t

b TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 SEP 171935 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen: Enclosed is the August 1985 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3. Very truly yours, TENNESSEE VALLEY AUTHORITY [6%dB Robert L. Lewis Acting Plant Manager Enclosures cc: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, GA 30303 (1 copy) Atlanta, GA 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D. C. 20555 (10 copies) Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 l l /l I l l An Equal Opportunity Employer L}}