ML20210F184

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Monthly Operating Repts for Dec 1985
ML20210F184
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/31/1985
From: Robert Lewis, Porter B, Thom T
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
0058B, 58B, NUDOCS 8604020060
Download: ML20210F184 (27)
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{{#Wiki_filter:- 1-Operations Summary DECEMBER 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 six reportable occurrences and two revisions to previous occurrences reported to NRC during the month of December. 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 for the unit's end-of-cycle 6 refueling outage. This was prepared principally by B. L. Porter. 860402CK)60 851EKl1 PDR R ' ADOCK 05000259 PDR 0058B fh ,1 - i

em 2 i Operations Summary (Continued) DECEMBER'1985 L Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows: Location Usage Factor Unit 1-Unit 2 Unit 3 -5 _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. 1 4 Common' System 1 Approximately 8.14E+05 gallon's of-waste liquids were discharged containing approximately 7.22E-02 curios of activities f 0058B

3 Refueling Information DECEMBER 1985 Unit 1 Unit I was in shutdown for its sixth refueling on June 1, 1985 with a scheduled restart date of March 1989. 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 instrumentation. The unit was shut down on :tarch 19. 1985, and remained in cold shutdown until June 1, 1985, because of unfinished modifications to meet environmental concerns. There are 0 assemblies in the reactor vessel. The spent fuel storage pool presently contains 764 EOC-6 assemblies. 252 EOC-5 assemblies. 260 EOC-4 assemblies. 232 EOC-3 assemblies, 156 EOC-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 June 1, 1986. This refueling outage will involve loading additional 818R (retrofit) assemblies into the core, finishing torus modification, turbine inspection, piping inspection, TMI-2 modifications; postaccident sampling f acility tie-ins, core spray change-out, and feedwater sparger inspection. 0058B

4 Refueling Information DECEMBER 1985' There are no assemblies in the reactor vessel..At month end, there were 277.new assemblies, 764 EOC-5 assemblies, 248 EOC-4'assemb11es, 352 EOC-3 assemblies 156 EOC-2 assemblies, and 132.EOC-1 aswemblies 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 HDRs are ~ being installed. Unit 3 Unit 3 started its sixth' refueling outage November 30, 1985, with a scheduled restart date of March 1987. '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 remained in cold shutdown until November 3'0, 1985, on an administrative hold to resolve various TVA and NRC concerns. There are 764 assemblies presently in the reactor vessel, there are 248' EOC-5 assemblies, 280 EOC-4 assemblies, 124 EOC-3_ assemblies,-144 EOC-2 assemblies,.and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations. 0058B

= 'S-Slanificant Operational Events DECEMBER ~1985 Unit 1 12/01 OC01 End-of-cycle 6. Refuel outage continues 12/31 2400 End-of-cycle 6 refuel outage continues 0058B

a 6 'Significant Operational Events DECEMBER 1985 Unit 2 -12/01 0001 End-of-cycle 5 Refuel and modifications outage continues 12/31 2400 End-of-cycle 5 Refuel and modifications outage continues 0058B

7 Significant Operational Events DECEMBER 1985 Uni'c 3 12/01 0001 End of cycle 6 refuel outage begins (unit has been shut down since March 8, 1985, due to various TVA and NRC concerns. 12/31 2400 End of cycle 6 refuel outage continus. 0058B

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9 AVI.R A(,f-In fl.) l' Nil POWER LEVEL DOCl:E T NO. _50-260 h'o UNIT DATE 1/1/86 C0\\lPI ETTD BY _T. Thom 1 E LEPilONE._205.DJ9-2509 .nf0Snt . De c.pmbe r D 4Y AVER AGE D AILY POWER 1 EVI.I iny Avi:R.u;E IMH.Y I OM ER LEVI'L - I'IVe Sct) istwe Net) 1 -7 -7 ,7 -8" 2 - 27. I.s 3 -Z__.__..__._. 19 8 4 -8 'O 8 -8 -8 s .-8 22 ~7 -8 -8 'g -8 _- 8 y. -7 -8 9 'S -7 -8 10 ,. t,

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~1 4 10 WLR \\GE la slLi l'NII I On f R 11VIi dot Kl'T NO..5.Q-19 ti IltWT Three DATE 1/1/86__ COMFI ETED BY T Tl"* It t t.!'I'ONE. --205/729-2509 ~ 3937,g Decembe r - IMY '.VERACE D41t Y POWER LEt LL D sY I M h r:.%t i Wl R gGE D til.Y FOh ER LEVLt. IMWe Nc4 9_, g 9 83 -5 3 _9 -5 39 9 4 -5 20 9 .I -5 .a 9 h.

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I 11 OPERATING DATA REPORT l'OCRF i NO 30-259 It\\ f t. 1/1/66 CO.\\tPLEll D BY .T. _Thom Il.LI Pil0NE M /7_29_3509 OrLRATING STATUS Notes

1. Unit Name:

Ilrowns Ferry One December 1985

2. Reporting Period:
3. Licenwd Thermal Power (\\1hti:

3293 1152

4. Nan: p! ate Rating IGrow N1hcP
5. Design Electrical Rating (Net SIWE):

1065 1098.4

6. 5!nimum Dependable Capacity (Grow atWe):

1065

7. 31nimum Ds pendab!c Capacity (Net StWe):
5. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since i.ast Report. Gise Rtavms:

N/A N/A

9. Power Lesel To Which Restricted. lf AnyINet31Wel:

N/ A liL Reasons for Restrietions,if Any-Ils \\lonth Yr..to Date Cumul.u ne iI fleurs in Reporting Period _.___.1114 8d60 100,160

12. Number of Ilot.rs Reictor was (. itical 0.___.

1'647.78_._ _ __ -59,521.38.- _ r 13 Reactor Hewne Shutdown flouri

14. Il<.ms Generator On I.me 0

1+626.67 58,267.26 7 0 15 Unit Resene Shutdow n floon 0 0 ( ow Thermal Energy Genuated (91w10 0 4,950,821 168,066,787 l t, n 17 Giow l!<ctrical l nergy Gencr.ited i\\lblit .. Net Ilettrical 1:ncrp Generated 15th II) -1,58l 1,5 4)..F86_. _53._757 009.. __. is 0 18.6 58 2 19 L.mt seniec Factor 2t> tmit Tsailabihty I' actor ._18,6 58.2 21 ITmt rapxity F actor (U ing \\tDC Net) 0 . 16.5 50.4 ?? l'mt Capacity I actor (Liing ill R Net) 0 16.5 50.4 0 55.1 2TE 2.1. L. it I.orerd Outare Rate n 2/. Shutdowns % hiduled Oser Nest 6 \\lonths I13 pc. Date and liaration of I aehl 25 If Shnt liown At Lnd Of Report Period. Estimated llate of Suetop. 9/14/86 26 L mis in ie.t St.nus iPsios Io Connreri al Oper.itioni I orecast Tthir m i INill \\ L ( RillCAlll Y INI flAl. I l.1 C l Rit 11 Y ( O\\l\\ll RCl \\1 Ol'l R \\IlON (9/77)

12 l OPERATING DATA REPORI DOCKl:T NO. 50-260 DA1E l.[IM.6_ COMPI 1:1ED fly.In Thom l ELrrilONE _.2031.7? & 2509 OPI' RATING STATUS

1. Unit Name:

B rmm s Fe r ry Two _ ecember 1985 D 2.. Herotting Period: 3293

3. Licensed Thermal Power (5tht):

1152

4. Nameplate Rating (Gross MWe).

1065

5. Design Electrical Rating (Net MWe):

1098.4

6. Masimum Dependable Capaesty (Gross MWe):

106.5

7. Masimum Dependable Capacity (Net MWei.
s. If Changes Occur in Capacity Ratings fliems Number J lhrough 7)Since f.nt Report.6i c Re.cun,-

N/A N/A

9. Power Leic! To hhich Restricted. lf AnvhA Net Mher 10 Reasons for Restrictions. If Any-

~ t his 31ont h Yr.-to Date Cumulatise 744 8,760 95,047

11. llourt in Reporting Period O
12. Number Of flours Resetor Was Critical 55,860.03
13. Reactor Resene Shutdown llours 14,200.44
14. Ilours Generator On.Line 0

0 54,318.36

15. Unit Resene Shutdown lloun 0

0 ~T 16 Gross Thermal Energy Generated (Mbil) U U 153,245.167 0 0 50, 7'i I, 79 8

17. Gron Electric.d Energy Generated IM%il) lb. Net Electrical Energy Generated IMhill p.W I)/,609 49,26S,164

~~~~~~ U 57.2

19. Unit Senice Factor

-U 5 / 2 U

20. Unit Asailability Factor 0

0-~ 4d /

21. Unit Capacity Faefor (Using MDC Netp 2.'

Umt Capacity I actor IUsing Di R Net) 0 0 48.7 )

23. Unit I onced Outage Rate.

0 0 21.0

24. Shutdowns Stheduled Oscr Nest 6 Months f ly pe. Date,and linration of 1:ath) 25, if Shi. IJown \\t Fnd Of Report Piriod. Estimated Date of St.,rtup: __ I.!RI.Ll986
26. Unies in lest Status (Psior to Commersial OperationL i once.nt A t luc si d lNlil \\ l. CRlllCAll! Y

_... _... ~. INIIITI. I 1.101 RR 11 Y CO\\lMI RCl \\ L Ori R.\\ IlON 6"j!/) 4.

s 13 OPERATING DATA REPORT DOCKETNo.' 50-2 E__ DATE 1/1/R6 CO'.!PLE1ED 11Y r Th . ILI.f ril0NE 2a5/779-2509 Ol'E RATING STA TUS - I. Unit Name: Browns F rry Three b"

2. Reporting Period:

De. ember 1985 3293

3. Licensed Thermal Pow.r (Mbt):

1152

4. Nameplate Rating (Cron MWe):
5. Desi;n Electrical.ating(Net MWe):

106s

o. Masimum Dependable Capacity (Grow MWe):

1098.4

7. Masimum Dependable Capacity (Net MWe):

1065 4

b. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since I.ast Report. Give Reasons:

N/A.

9. Power Lesel To which Restricted. If Any (Net MWel:

N/A n . 10. Reasons For Restrictions.lf Any: N/A This Month Yr. to-Date Cumulatise I II. Ilours in Reporting Period 744 8.760 77.472 0 1.517.65 45,306.08 12.. Number Of flours Reactor Was Critical 508.05 5,149.55

13. Reactor I!cwne Shutdown flours

. 14. llours Generator On Line 0 1,496.96 44Jg.J6

15. Unit l'e>ene Shutdown flour, 0

0 0 I. lo.. Gross Thermal Energy Generated IMhil) O 4,649,840 131,868,2 R.. U 1,572,770 43,473,760

17. Grov. Llectrical Energy Generstrd lMhil)
15. Net Elcetrical Energy Generated IMWil)

-4,603 1,468,012 42,133,773 0 17.1 57.0

19. Un:t Service Factor j
20. Unit Asailability Factor 0

17.1 57.0 0 l

21. Unit Capacity Factor (Using MDC Net) 15.7 51.1
22. Unit l'apacity Factor (Using DrR Net) 0 15.7 51.1 0

81.3 26.4

23. Unit Forced Outage Rate
24. Shutdowns Scheduled Oser Nest 6 Months (T)pc.Date.and Duration of Fath).

4 25 If Shut Down At l'nd Of Report Period. Estimated Date of Startup: - Flarch 1987

26. Units in Test Status IPrior Io Con.mercial Operation);

Iorecast At hiesed 3 INITI A1. ClllllCA1.1 f Y r INITIAL El.l filt! CITY ( OMMI itCITI. OPI R A IlON eJ/77)

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o - 50-260 UNII Sil!JI!>OhN5 ANI) POhl R REDUL110NS IWKEI NO-UNIT N AME _Tm DATE 1/1/86 COMPI.ETED BY L Th n I!LPORI MOVIII Nench e TELLPilONE ons n90 95no .2 5 1 "; J. E -; Leo nsce =" F :, Cauw A Curre, tare N-tbh i 5i jss Lvent u7 6.? Atiion to 55 U. 5f3 Report : EL 5' Picsent Recurrente e i 305 12/1/85 S-744 C 4 EOC-5 Refuel Outage (Cont) (Controlled Shutdown 9/15/84) vi I I t i i t I I l i 2 3 4 F: Forced Re25)n : Methed: Exhibit G -Instructiois S Sched u'c ! A Equipment F2 dure s Lspain) 14tanual fer Preparan.m ot' Data B-Emre.,2.u.. l es* ' Manaa! Sera:n. Entr> Sheets for L:;emce C-R: iud:,c 1 Automatic Scram. Ese:0 Rer n (L'.R t Fi:e i V FEG-D-Reputati n Ronisnoe. 4-Other i Explain i 0:6!1 1 -Opera:ov Tra:nmg & I.e.c e laannannn i AJ:".;nm rv r.e 5 G-Oper.itiona; 11 r er I I. s plata l E siuht: I - Same Soure.- l'C 7 ) if Other iEspt:m6

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~ '* ~ .a.. P. W:;5 : U,i.Y JCLi.AR i1.A ;I L6.Y v BF CtSII 30 CSSC D)UIPMENT ELECTRICAL !!AINTENANCE SDetARY 9/29/82 For the Month of December 19 85 I Effect on Safe Action Taken h Nature of Operation of Cause.of Results of To Preclude d Da2e Systen Component Maintenance The Reactor Malfunction Malfunction Recurrence 1985 L 773 4kV common BKR-203-A/03 Routine transfer None Bad SBM switch Breaker 'took about Replaced SBM switcl e board alternate (52 STA) located 5 seconds tb close breaker 1118 in bkr compt MR 591355 12/16 Standby BKR-211-B/004 Pe rforming None Bad SBM switch D/B "B" failed to Replaced SBM switcl diesel tie breaker to SI 4.9.A.l.a (52 STA) located fast start during o generator D/G "B" (1822) D/G monthly in bkr compt SI. Declared inopera-85 -311 operability ble 1 1 12/19 Control bayCHR-31-13 1A Troubleshoot None Sticking pressure Chiller tripped on Reset pressure swit heat, vent control bay chiller switch low refrigerant & AC chiller pressure & would not MR 645046 reset 12/28 Diesel 125VECAB-254-C Replace alarm None Broken contact on Bell alarm defcetive Replace alarm bell DC alarm bell, 1C bell bell alarm asscobly diesel engine control cabinet MR 569323 C f j I i g.

.' ?. -m. ,,..-s --\\.~_(_.. c.s"" %, .s '9_' l* r .u,,' m oGUW:.6 t r.iikt ;.oLQ.A.s PLA.w t;A i f 1 g CSSC EQUIPMENT ELECTRICAL !!AINTENANCE SDD!ARY ^PE"" 9/29/82 For the Month of December 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude .tte System Co.mponent Maintenance The Reactor Malfunction Malfunction Recurrence 15 d5 Fire Fire protec-Performing None Unknown Cell #11 found bad Replaced. cell (til protection tion battery D11-4-B MR 571865 No. 1 /9 Condensate ifrR-2-14 Remove motor None Open winding Motor taken out of Removed motor condensate and send to service for repairs hotwell pump Power Service PR 578257 - motor 1C Shop Sent to PSS e e

.u b.OliNS liwi M Cs.r.A!; Pl.ANr CNii o _ g' 33 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SCIMARY 9/29/82 For the ?!anth c.f December 19 85 Effect on Safe Action Taken._ Nature of Operation of Cause.of Results of To Proclude Date System Component }!aintenance The Reactor Malfunction Malfunction Recurrence l 1985 4/8 Condensate MTR-2-14 Remove motor & None Open winding on Motor taken out of Removed motor system condensate hot-send to Power motor service for* repairs MR 578254 - 11 pump motor Service Shop j w pg3 11/5 Fire pro-Fire protection Performing D1I-None Unknown Cell #6 found bad Replaced cell 116 tection battery No. 2 4-B !!R 571864 .12/5 Control Annunciation Troubleshoot None Bad card Panel would not test Replaced card room panel 9-3 and repair annunc ia- !!R 643392 G tien 1 12/10 Core spray MV0P-75-2 Troubleshoot None Closing circuit Valve failed low leak Set close torque cooling CS pump A valve torqua switch rate test switch up to nax i suction valve setting too low setting 3 MR 637675 12/11 Fire XS-39-92NB Replace smoke None Unknown Smoke detector not Replcced smoke protection smoke detector detector operable detector Rx b1dg - 593 MR 569325 12/17 Crancs & Refuel platforr Repair or None Connector was Grapple latched Cleaned & tightene. hoists main hoist replcce loose and dirty light was intermitten t arp henol connecto~ amphenol before reaching the MR 639309 connector full up position I f

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MECHANICAL MAINTE MNCE

SUMMARY

CSsc EOUIP ENT For the Month of December 19 85 ACTION TAKEN EFFECT ON SAFE 'DATE SYSTD1 COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINFENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 52/4 26 Emergency Fire Fabricate cesh None New fabrication None Fabricated mesh scr< Fire Pump 'C' screens for ' :' as requested ( -Screens fire pump mot ar 3 84 Relief valve Bench test None Defective gage Potentially Removed and tested inaccurate relief valve at 142 PSIG 0-84-507 relief valve used on previou: t CAD tank "A" 0-84-507 at bench test setting 140 PSI +3% 2 l l l i l t

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/.. TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 JAN 151986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, D.C. 20555 Gentlemen: Enclosed is the December 1985 Nonthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3. Very truly yours, TENNESSEE VALLEY AUTHORITY / obert L. Lew Plant Manager Enclosure ec: Director, Region-II INPO Records Center Nuclear Regulatory Comunission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, Georgia 30303 (1 copy) Atlanta, Georgia 30389 Director. Office of Inspection and Enforcement Nuclear Regulatory Comunission Washington, D.C. 20555 (10 copies) Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 'I s ( An Equal Opportunity Employer

m: Fi TENNESSEE VALLEY AUTHORITY POWER & ENGINEERING (NUCLEAR) ^ BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC DECEMBER 1, 1985 - DECEMBER 30, 1985 DOCKET NUMBERS 50-259, 50-260. AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by: / Plant Mahag(r O L .,,y

TABLE OF CONTENTS Operations Summary. 1 Refueling Information........... 3 Significant Operational Events...................... 5 Average Daily Unit Power Level......... 8 Operating Data Reports......................... 11 i Unit Shutdowns and Power Reductions................... 14 Plant Maintenance............................ 17 i 1 ,1 e 0058B ,}}

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