ML20113G716

Monthly Operating Repts for Nov 1984

ML20113G716
Person / Time
Site:	Browns Ferry
Issue date:	11/30/1984
From:	Jones G TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8501240483
Download: ML20113G716 (26)

Text

.

l TENNESSEE VALLEY AU1NORITY i

DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT i

MONTHLY OPERATING REPORT TO NRC Nov mber 1, 1984 - November 30, 1984 DOCKET NUMERS 50-259, 50-260, AND 50-296 LICENSE NU M ERS DPR-33, DPR-52, AND DPR-68 Submitted by:

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TABLE OF CONTENTS Operations Stanary......................

1 Refueling Information....................

3 Significant Operational Instructions.............

5 Average Daily Unit Power Level................

11 Operating Data Reports....................

14 Unit Shutdowns and Power Reductions.............

17 Plant Maintenance......................

20 Outage Maintenance & Major Modification...........

25

s 1

Ooerations S - ry November 1984 l

The following sumary describes the significant operation activities d,uring the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

l There was one reportable occurrence and no revisions to previous l

reportable occurrences reported to the NRC during the month of Novmber.

Unit 1 There were no scrams on the unit during the month.

Unit 2 l

l The unit was in cold shutdown the entire month for the unit's end-of-cycle l

5 refueling outage.

Unit '4 There was one scram on the unit on Novmber 20, 1984, due to low reactor water level.

The end-of-cycle refuel outage was completed on November 28, 1984, when the unit was brought on-line briefly to check turbine vibration.

The unit was in a maintenance outage November 28 to l

November 30, 1984.

l l

Prepared principally by B. L. Porter.

I 9

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Operations m ry (Continued)

. November.1984' Fatinu f r.n=e Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location flanae Factor Unit 1 Unit 2 Unit '4 Shell at water line 0.00611 0.00492 0.00418 Feedwater nozzle 0.29403 0.21319 0.15675 Closure studs 0.23744 0.17629 0.14093 NOTE:

This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements.

C-

-> System Approximately 1.40E+06 gallons of waste liquids were discharged containing approximately 6.10E-01 curies of activities.

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Ooerations S - rv (Continued)

November 1984-4 l.

Refbelina Information l

Unit 1 Unit 1 is scheduled for its sixth refueling approximately March 22, 1985 with a scheduled restart date of October 8, 1985. This refueling will' involve 1

loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and envirornnentally qualify instrumentations.

l There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-j-

age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel j

assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-4 1 fuel assemblies. The present fuel pool capacity is 3,471 locations, t

Unit 2 4

Unit 2 was shut down for its fifth refueling outage on September 15, 1984 i

l with a scheduled restart date of January 31, 1985. This refueling outage will i

involve loading additional 8X8R (retrofit) fuel assemblies into the core, l

finishing torus modification, turbine inspection, piping inspection, 'IMI-2 j

modifications; post-accident sampling facility tie-ins, core spray change-out,

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and feedwater sparger inspection.

j There are no fuel assemblies in the reactor vessel. At mcnth end, there were 56 new fuel assemblies, 764 EOC-5 fuel assemblics, 248 EOC-4 fuel i

assemblies, 352 E0C-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 132 E0C-

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1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 350 locations. All old racks have been removed from the pool and new HDR's are being installed.-

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4 Ooerations Si-ary (Continued)

November 1984 Unit ~4 Unit 3 is scheduled for its sixth refueling outage approximately December 6,1985, with a scheduled restart date of March 6,1986. This refueling involves loading 8X8R (retrofit) assemblies into the core,.and

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complete reinspection of stainless steel piping.

There are 764 fuel assemblies presently in the reactor vessel. There are 248 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies,144 EOC-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the i

spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations.

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'Sinnificant Operational Events Date

- Ti==

Event Unit 1.

~ 11/01

' 0001 Reactor thennal power at 100-percent (5), maximum flow, rod limited.

11/03

.0030 Comenced reducing thermal power for SI 4.3.A.2 (Control Rod Drive Exercise).

0035 Reactor thennal power at 955 for SI 4.3.A.2.

0150 SI 4.3.A.2= complete; commenced power ascension.

0230-Reactor thermal' power _ at 1005, maximum flow, rod limited.

11/10 0200 Commenced reducing thennal power for SI 4.3.A.2 (Control Rod Drive Exercise).

0215 Reactor thennal-power. at 955 for SI 4 3. A.2.

0338 SI 4.3.A.2 complete; commenced power ascension.

0800 Reactor thennal power at 1005, maximum flow, rod limited.

1300 Reactor thermal power at 995, maximia flow, rod limited.

1325 Increased thennal' power to 1005, maximum flow, rod limited.

11/16 2210 Commenced reducing thennal power for turbine control valve test, sis, and removal of "C" reactor feedwater pump from service for' maintenance.

11/17 0200 Reactor thennal pwoer at 735 for turbine control valve test, sis, and "C" Reactor Feed Water Pump (RFWP) maintenance.

0225 Turbine control valve test and sis complete, holding at 735 for "C" RFWP.

0440 "C" RFWP back in service, commenced power ascension.

0500 Reactor thennal power at 755, commenced reducing power for. control rod pattern adjustment.

0600 Reactor power at 74% for control rod pattern adjustment.

0700 Consnenced PCIOMR from 745 thennal power.

0910 Stopped PCIOMR due to computer problems, reactor power at 765.

1035 Computer back in service, increased thermal power to 785.

1140 Commenced reducing thermal power due to Xenon transient.

1200 Reactor power at 775 due to Xenon transient.

1400 Reactor thennal power at 785 due to Xenon transient.

1530 Conmenced PCIOMR from 785 thermal power.

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Significant Ooerational Events Date Tima Event Unit 1 (Continued) 11/18 1730 Reactor thermal power at 1005, maximum flow, rod limited.

2300 Reduced thermal power to 995 due to a bad computer point on "A" feedwater line.

11/19 0030 Computer point deleted from computer input, increasing thermal power with PCIOMR.

0300 Reactor themal power at 1005, maximm flow, rod limited.

0700 Reactor thermal power at 995, maximum flow, rod limited.

11/20 0020 Commenced PCIOMR from 995 thermal power.

0500 Reactor thermal power at 1005, maximum flow, rod limited.

1500 Reactor thermal power at 995, maximum flow, rod limited.

11/21 2355 Increasing themal power from 995.

2400 Reactor thermal power at 1005, maximum flow, rod limited.

11/22 2008 Commenced reducing themal power for removal of "C" RFWP from service for maintenance (vibration problem).

2120 "C" R W P out-of-service to tighten base plate, reactor themal power at 725.

2235 "C" RFWP back in service after maintenance on baseplate.

2317 Commenced power ascension from 725 themal power.

11/23 0005 Commenced PCIOMR from 965 themal power.

0400 Reactor themal power at 1005, maxima flow, rod limited.

1335 Commenced reducing thermal power for removal of "C" RFWP from service for maintenance.

1430 "C" RFWP out-of-service, decreasing themal power.

1800 Reactor thermal power at 715 for maintenance on "C" RFWP.

2200 Reactor themal power at 725 for maintenance on "C" RFWP.

11/24 0200 Reactor themal power at 735 for "C" RFWP maintenance.

0230 "C" RFWP in service, commenced power ascension.

0830 Comenced PCIOMR from 955 themal power.

1330 Reactor themal power at 1005, maximum flow, rod limited.

7 Sinnificant Ooerational Events Date Tim Event Unit 1 (Continued) i 11/25 0800 Reactor thermal power at 995, maximum flow, rod limited.

0830 commenced power ascension from 995.

8 0900 Reactor thennal power at 1005, maximum flow, rod limited.

2200 Reactor thermal power at 995, maximum flow, rod limited.

2210 Conmenced power ascension from 995.

2300 Reactor thermal power at 1005, maximum flow, rod limited.

11/27 1300 Reactor thennal power at 995, maximum ficw, rod limited.

1430 Increased thermal power to 1005, maximum flow, rod limited.

1900 Reactor thennal power at 995, maximum flow, rod limited.

11/28 0030 Increased thermal power to 1005, maximum flow, rod limited.

11/29 0100 Reactor thermal power at 995, maximum flow, rod limited.

11/30 2205 commenced reducing thennal power for control rtxt sequence exchange.

2400 Reactor thermal power at 585 for control rod sequence exchange.

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8 Sinnificant Ooerational Events Date Tima Event Unit 2 11/01 0001-End-of-cycle 5 refuel outage continues.

11/30 2400 End-of-cycle 5 refuel outage continues.

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9 Sinnificant Operational Events Date Tima Event Unit 3 11/01 0001 Unit remains offline due to NRC concerns.

11/19 2200 Commenced rod withdrawal for startup.

2349 Reactor critical No. 127 11/20 1152 Reactor Manual Scram No.113 from 4% thermal power due to low reactor water level.

11/21 0030 Reactor in cold shutdown.

11/22 1632 Commenced rod withdrawal for startup.

1800 Reactor Critical No.128.

2130 During High Pressure Coolant Injection (HPCI) alignment, FCV-73-3 was found to be broken. Stopped heat-up of reactor vessel.

11/ 23 1420 Unit controlled shutdown in progress.

1615 All rods inserted, control shutdown complete.

Reactor in Hot Shutdown.

11/24 1458 Commenced rod withdrawal for startup.

1610 Reactor Critical No. 129.

2150 Stopped heat-up at 250 psig, holding for startup sis and inspections.

Reactor thermal power at 70%.

11/27 0359 Commenced rod withdrawal to rated pressure and temperature.

0630 Stopped rod withdrawal, reactor at rated pressure and temperature, holding for drywell inspection.

Reactor power at 75.

1020 Drywell inspection complete.

1150 Commenced rod withdrawal.

1300 Stopped withdrawing control rods, holding for startup sis, reactor thermal power at 10%.

1830 started inerting drywell.

2230 Drywell/ torus inerted.

11/28 1215 Commenced rod withdrawal for startup.

1305 Stopped rod withdrawal, reactor power at 145, holding for turbine overspeed trip test.

2030 Rolled main turbine to medium speed.

2035 Turbine 100 rpm trip and inspection complete.

2030 Resumed rolling main turbine.

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.f 10 Sinnificant Operational Events Date Time Event Unit 3 (Continued) 11/28 2110 Main turbine at 1800 rpm; No. 8 bearing has high (Cont.)

vibration.

2206 Synchronized generator, commenced power ascension from 14% thenmal power.

2257 commenced reducing load from 21% to take turbine offline due to excessive vibration on ho. 8 bearing.

2310 Main turbine offline, reactor power at 215.

11/29 0007 Commenced reducing thermal power for two bypass valves.

0125 Reactor thermal power at 105, holding for balance of mein turbine.

0300 Reactor thermal power at 95, holding for balance of main turbine.

1210 Commenced rod withdrawal for startup.

1320 Rolling main turbine.

1350 Main turbine at 1800 rpm, oil trip test complete.

1355 Synchronized generator, commenced power ascension from 15% thermal power.

1410 Unit taken offline due to excessive vibration on main turbine, reactor power at 15%.

1530 Commenced reducing thermal power for 1-1/2 bypass valves.

1700 Reactor thermal power at 125, holding for balancing of main turbine.

1900 Reactor thermal power at 95, holding for balancing of main turbine.

11/30 0355 Commenced inserting control rods for Hot Standby mode.

0420 Rdactor sub-critical, holding for balance of main turbine.

1640 Commenced rod withdrawal for startup.

1805 Reactor Critical No. 130, 2147 Reactor in Run mode.

2300 Reactor power at 135, holding for startup.

2400 Reactor power at 135, holding for startup.

t 11 AVERAGE DAILY UNIT POWER LEVEL 50-259 DOCKET NO.

WIT Browns Ferry-1 DATE I?/1/RA COMPLETED BY Tad Thnm 205'/729-3834 TELEPHONE MONTH DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net I (MWe-Net) 1047 801 g7 2

in70 18 1009 3

1058 19 1050 4

1069 20 1057 1066 1048 5

3 6

inso 22 1039 1064 921 7

,3 8

inAR 2.g 978 9

1076 1063 25 1054 1069 10 3

1071 1065 1067 1065 12 28 g3 1065 1062 y,

1079

4 30 15 1064 3

16 1048 INSTRUCTIONS On this format,hst the aserage ijail.s unit p.mer leselin %twe.Nel for each day in the reporting month. Compute to the nearest whole nwgawatt.

e (9/77) e

j 12 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT Browns Ferry-2 DATE 12/1/84 Ted Thom COMPLETED BY TELEPHONE 205/729-3834 MONTH November DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(Mwe. Net) 1

-8

-3 37

-8 2 is

-3 3

-7 39

-5

-3 4

20

-4

-3 3

-4

-3 6

22

~4

-3 7

33 8

-3 24

-3 9

-4 25

-3

~4 10 26

-3

-3

~4 II 27

-3

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12 33 13

-3 y,

_3

-3 14 30

-3 15

-1 3

16

-1 INSTRUCTIONS On this fortnat.!nt the acrage dails unit p.mee lesel m MWe Nei for each day in the reportinginonth. Compute to the nearest whole nwgawatt.

19/771 i

13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

~

UNIT Browns Ferry-3 12/1/84 DATE Ted Thom COMPLETED BY 4

TELEPHONE 205/729-3834 s'

MONTH November DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

I

-II 17

-12 2

-12 IE

-13

-12 3

19

-14

-12

-14 4

20

-12 5

21

-13

-II 6

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-12

_g4 7

-11

-15 3

24

-11 9

25

-13

-12

-14 10 26

-II

-14 II p

12

-12 28

-8 0

13 '

-12

-14 29

-II

-14 14

.40 "I2 15 41 16

-12 INSTRUCTIONS On this format. list the average dash unit ii.e t u.i n, sim..N'et f or each dJ - H IIic reporting inonth. Compute to i

the nearest whole negawait.

(9/77)

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Ol'ERATING DATA RLi'ORI DOCALT No 50-259 m

Dil1: 121.llE4 CO\\1PLE1 ED liY Ied Thom.

I 1:1.1 PIION t' 205/J29-383'4 OPER A TING S'IXI US 1.,11ni Name:

Browns Ferry ~l November 1984 I

2. iterotting Period:

' 3.- Lietnsed Thennal Power 6tht):

3293-

' f.' Nameg late llating (Grow S1We r 1152

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5. Design Elcetrical Raticg (Net 31Weg 1065

)

6. 51axiinum Dependable Capacity (Grow ilWep. __.1098.1 j

1

'- 7. Sinimmu Dependabl Capacity' fNet 51Wep 1065 S. If Cluages occur in Cupacity Itatings litems Number 3 Ihrough 7: Since I.ast Itepott Gi.e Reason, N/A N/A

9. Power Letel To hhich !!cs'ricted. If Any (Net \\lwer

10. Reasons l'or itestridinns. If Any.

N/A 4

l T hi> 51ont h Yr..to Daie rumulatise 720 8,040 90,656 iI J llours in Reporting Period

12. Number Of flours Reactor has Critical 720 7.323.48.-

57,-129.6

13. Reactor' Reserve S:.utdown linurs 0

__700.20 6,485.22 1,4. flours Generator On-Line

. J20

_7(178.95

_518_96.,5T ~

15. Unit Resene Shutdown llour, 0

-0 0

15. Gnm1hermal Energy Generated OlW!h 2.335J0.6

_2.2.J1J1,802 160.874,4_81 17 Grow Eketrical Energv Generated (.\\lhil) 769.980 3 345,670 52,991,290.

18. Net Electrical Energy Generated iMbII, 751,122 7,153,020 51,478,347

-19. Unit Senice Factor 100 89.3 61.7 20; L'mt Asailabil'ity Factor 100 89.3-61.7

21. Llait Lapacity Factor tusing.\\1DC Neti 98.0 83.5 53.3 2.'. L nit Capacity Fa, tor ilhimt Di R Net)-

98.0 83.5 53.3

23 - t nit I orced Out. ige Rate 0

10.4

'22.3'

24. -Shutdowns Sihsluln: ther Not 6 \\fonthi,i1 pe. Date, and Unration of I'achi 3

.- w

25. If Shut Down L\\t End Of R$ port Period. Estimated Date 6f Startup;

26. Units !n fest Statuit Prior to Conunercial Operation):

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i 15 OPERATING DATA REI' ORT 50-260 DOCKET NO DATE 12/_l'/84-_.

COMPLETED BY Tad Thnm 1ELEPflONE 205/,729 3834 OPERATING STATUS

1. Unit Name.

Browns Ferry 2

2. Reporting Period: Novomher 1984 g

3. Licensed Thermal Power (MWt):

3293 1

4. Nameplate Rating (Gross MWe):

1152 3

5. Design Electrical Rating (Net MWe):

1065 l

6. Masimu'n Denendable Capacity (Gross MWe): inon A l

7. Masimmn Dependable Capacity INet MWe):

1nn

8. If Changes Occur in Capacity Ratings tItems Nmul,er 31hrough 7i Since I.ast Report. Give Reasons:

M/A

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

N/A

10. Reasom l'or Restrictions,if Any:

N/A This Month Yr..to Date t umulathe I1. flours In Reporting Period 720

.8.040

_8_5_, 5 4_3

12. Number Of flours Reactor Was Critical 0

5,895.85 55,860.03

13. Resetor I!cwne Shutdown flours 3nn nn 14,700.44_ _._

n

14. Ifours Generator On.I.iae n

_1.&45.52 14.338_,36 ___

15. Unit Rewne Shntdown llours O

~_.0_

0

16. Grow Thermal Fnergy Generated 1MWil) n l't100;1??

153.2/1.M L_

1 17 Grow Electrical Energy Generated IMhill

0.. _ __..

_4.J74.510

_5_L 771,798 IN Net Electrical Energy Generated (MWH) 0 4.044.370 49,302,973 I". Unit Senice I actor 0

72.7 63.5

20. Unit Asailability factor 0

_72.7 63.5

21. Unit Capacity Factor (Using MDC Net) 0 47.2 54.1 2.'

Unit Capacia) Fat-tor (Using DER Net) 0 47.2 54.1 23.' Uni Forced Ontage Rate 0

4.1 23.0

24. Shutdowns Stheduled Oser Nest 6 Months t I) pr. Date,and Duration of I ash e.

25. If Shut Down -\\t End Of Report Period, titimated Date of Startnp: _Ap_ril 13_,_l,9.85 2h. Unin in Test Stains t Prior to tommercial Operation):

I m eras

.hhiesed INil l A l. ( Hli tCAI.ll Y INi ll AI. FI l C I RiflI Y

COM\\ll'Rrl \\1 OPI R A IlON

16 OPERATING DATA REPOR1 DOCKLTNO 50-296 _

DATt 12L1L8_4,_

( 03]Pl.LTED liY Ied..Thom.

ll-1.IP!IONi-205/729.-3834 OPERAT!NG S1 ATUS-r-

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1. Unit Name: _ Browns Ferry 3

2. ileporting l'*eriod.

November 1984

3. Liccawd Ihennal Power 13tht1:

3293 1152

4. Nameplate Rating (Gnm 3DVeI:

1065-

5. D.: sign E!cctrical Rating (Net MWe).

.f ti. Slasinunn Denendable Capasity tGnm \\tWe):

10 % 4 7 Masianum th pendable Capacity (Net 31Wel:

..106_5 M. If Chango Occur in Capacity Ratings litems Nmnl.cr 3 Ihrom:h 'l since I ast Repmt 4.i e Reason.

N/A

9. Powc i.esel 19 hho h Restritted. lf Any INet \\lhet N/A t

10. Itca4ons I or 16 trictions, if Ans.

N/A

. _. ~ -

______a_

Ihis Ntonth Yr to la ie Cumulaths a

!I. linurs In Reporting Period

_720 8,040 67,968

12. Nu:nber Of flours Rc,ctor W.is Critical

._l]2J8 172.38 43.260.18 v

13. Reactor Resene Shutdnwn flours 547.62 547.62

-4,425.75

11. It'ours Generator on.1 ine 1.'32 1.32 42,195.03

15. Unit Resene Shutilown llours

_D

_D 0

16. Grow Ihenna: Energy Generatesi(\\1Wl')

• n

__ Q 41,591 R 0 17 Gnm E!cetrical I.ncrgy Generated CIWill

_150

_L5p 41.597,7/0 Ik-Net Westrical Ercrgy Genuated (MWill 0-0 40,375,256 _

19. Unit Senice Factor

._0 2

0.02 62.1

20. Unit Asailabili:3 I actor 0.2 0.02 62.I

.0 O

55.8 21 Unit Capacits Factor (Using \\tDC Net) 0 0.

55.8 2.'

Unit Capacity Factor (Using Di R Net 1 99.8 99.8 17.7

23. Unit Forced Outage itate 24 Shutdowns Schedu!cd Iher Nest 6 \\lonths (T pc. Date.and Duration of I achl-

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'25. If Mmt Down At End O! Report Period,l.stimated Dale of Staitup.

'12/1/84' 2n. Units in 'iest Stains tPrior to Conunercial Operationi l'orecast' A'chiesed INil lT I. CRi llCAl.Il Y 1

INIIl \\I. I ! I CIRICII Y TO\\1\\1l RCI \\1. OPI-R A IION

• No measurable. core. exposure or MBTU.

cof? l 6

i-50-?.59

' UNIT S!!UTDOWNS AND POWER REDUCl;0NS DOCKET NO.

UNIT N AME Browns _ Ferry-1 DATE _1_2/1/84 REPORT MONTil.

November COMPLETED BY Ted Thom TELEPHONE

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Present Recu:re isc i

299 11/16/84 F

B Derated-for CV Tests, SI's and-

"C" RWP Maintenance

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300 11/22/84 F

B Derated for "C" RFWP Maintenance

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y x-301 11/23/84 F.-

B Derated for "C" RFWP maintenance.

302 11/30/84 S

H:

Derated for Control Rod. Sequence Exchange I

2 1

4 F: Forced.

Reason:

Method:

Exhibit G. incenctio.n S. Schedu!cJ

. A Equipment Failurc (E.splain) l-Manual for Preparation of Data B Maintenance of Test. -

2 Manual Seram.

Entry Sheets ti>r 1.:censee C Refueline

~

.t Automatic Str.rm.

Esent Reposi iLi Rt File t' t R16 D RegulatJr> Restriceion.

4-Other s t Aplain t 01611 l -Operator Trainm & I nten'e I samination F Administrati.e 4

G Operational 1:iro Il.splaiai ITinbit 1 Same Soatee to/77)

' II.Other ll% plain i 4 -

UNIT SifUTDOWNS AND POWER REDUCT10NS DOCKET NO.

50-260 UNIT NAME Brot.m n Ferrv-2

~"

.DATE' 19/1/5tA

~

November

COMPLETED BY Ted Thom REPORT MON.fil Ai TELEPHONE 205/729-1R1/c 1

4 4

c1 15?

i 4$p Licensec

8t U":, l '

Cause & Currectne h

Date

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.Z EE3 Esent 7?

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Present Recurrense A tion to 5=

2j-Report :

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.305 11/1/84 S

720 C

4 EOC-5 Refuel Outage j

(Controlled Shutdown 9/15/84) t

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Methm!:

Exhibit G Instrua :.

s A Equipment failure (Eshlaini l

}

l 2-Manual Scram.l 5: Sched uled --

l Manual,

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thr Preparation'or' Da:a j

B-Maintenance of Test Entrs Sheet 5 for 1.:.emec I

i t

4-Autisinatic Scram.

Esent Report ii i R e F ne i',t Ri t -

C Refueling D Regulatory Restriction 4-Other ( Explain )

01611 12 Operator Training & Inense I umination 1

F-Adnunist rati.e 5

G4hwrational Enor (lispland I statut i 4 Same 5.. :.e,

et/77)

Il-Ot her I E splaud

y UNIT SliUlDOWNS AND POWER REDUCTIONS DOCKET NO.

50-296 UNIT NAME Browns Ferry-3 DATE. 12/1/84 COMPLETED BY hA Thn=

REPORT MONTH November TELEPHONE 9 m /79o_3n3r.

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Report :

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Present Recurrerne f.

141 11/1/84 F

467.87 D

Start-up on hold due to NRC concerns.l 142 11/20/84 F

57.63 H

2 Reactor manual scram due to reactor low water level.

Scram was caused by procedural inadequacy.

l

-143 11/22/84 F

48.33 A

1 During HPCI alignment FCV-73-3 was found to be broken.

G 1

144 11/24/84 S-96.27 H

Holding for start-up SI's and inspections.

d 145 11/28/84 F

14.75

.B Excessive vibration on No. 8 bearing i of main turbine (turbine offline for balancing) 146 11/29/84 F

~33.83 B

Excessive vibration on main turbine.

(Turbine offline for balancine) 1 2

3 4

F: Forced.

Reason:

Method:

EshiN G - Inst r us tioo s S: Scheduled

' A Equipment Failuie I.splain 1-Manual for Picparation of Data B-Maintenance of Test 2-Manua! Seram.

Entrs Sheets l'or I.icensee C-Refueling 3-Automatic Scram.

laent Report al.1 R il iL t Nt RI b-D Regulatory Restriction 4 Other (Esplaini 0161i E-Operator Trainmg & I hen e I u::unation F-Administrati.e G-Operational Es toi II: splain i 1.shibit I Same.v.use P7/77)

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' BRO NS FERRY EUCLEAR PLANT. UNIT 0

Page ;4-BF p,,b,L 30.

' CSSC EQt'IP.Mf N T ELECTRICAL MAINTENANCE SUM)f.\\RY Appendig B

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. 9/29/32-

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For the Month of November ~ 19 84'.

e.

1 Effect on Safe 4; Aetion.Taken

,Re c.' :+ e i _

'To'Prb lude.

L; :re of

-Operation of

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se.4 : e,J.

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'*iin ena.c6 The Reactor-Ma l f un c t ia".

' Mal f t:ne t idn '

Recurrence

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0-CMP-82-6680 Replaced pres-None Bad pressure-Air compressor will Replaced pressure".

3.' Standby diesel.'

D/G D. ac/de-sure switch switch not start on;1ow s' witch - ' '

air l compressor ogenerator pressure HR 190679 4

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BF r.:fSIL 30 G ' ' L ' ' I *'.'C N r ELECTRICAL }L\\I +TENA.';Cr. SC>StARY Ap:vendix B l

9/29/82 For the Mant5 of November 19 84 _ _

I:f:ect ea $aie, Aetion laden L:ure of Operation et Ouse.if Rer.: l t s cf Ta Preclude 4.

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Flin o

.e The Re t.: o r Li f un c t ion

talfunction i

Rect rrenci-i 4

l 5

TIP

[ Shear valves Replaced defect <- None Squibs defective N/A

, Replaced defective j

A,B,C,D,E ive explosive aper Cencral squibs.

l actuation

! Electric

' cartridges HR 252093 (squibs) in TIP shear valves j

l 480v jl-RLY-268-273 )Replacedrelay None lBadrelay Contacts will not feplaced relay, g

reactor undervoltare t

MOVboards+relayboardID,j g close when relay coil l l

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is deenergized MR 320105

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3RO'4NS FERRY NUCLEAR PLANT Di1T 2

MF FJSIL 20 MIP !iN T C &:.

ELECTRICAL }L\\lNTEN.\\NCE SO' MARY 9/29/32 For the."anth of November 19 84.

Et'fect on Safe,

,c. ion i gen

'.. :... r -

Operatton of l Cause,2f R.su; ef To pr.Jelude i

3 S

c.-

nt

_..M.

The Reactor I

St.11 f unc t ion i

Malfunction i Recurre.ce 1

i 2 iS0v reacto;r 2-RLY-268

. Replaced relay (Jone Bad relay Contacts will not Replaced relay MOV boards ; undervoltage close on loss of

} relay board 2D voltage MR 320104

, compt 4A 3 Reactor 2-FCO-64-0013 Adjusted damper None Switch out of Damper showing both Adjusted position b1dg

' reactor zone

position switch adjustment red and green position switch.

ventilation air sup outbd lights when in open jisolationvalvyl position MR 312554 3 Reactor 2-FCO-64-0014 ; Adjusted damper None iSwitch out of

Damper would not i Adjusted position',

b;dg gReactor zone

' switch l adjustment lclosefromcontrol switch ventilation air sup outbd l l room handswitch iMR 312553

' isolation valve j

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. Fire prg-2-XS-39-26A Replace smoke None

, Bad detector lPetectoralarming l detector Replaced smoke

action

, control pal detector g internittently with i

9-3A smoke i

i no indication of

} detector t

i smoke iMR 312211 t

I l

i 19' Residual

' 2-BKR-74-075 lReplacedcon-lNone Contacts pitted i N/A. Detected duringiReplaced contacts.

' heat

' RHR sys II tacts I

due to extensive lscheduled maintenance !

removal entmt spray l

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lMR 320145 use

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j inbd valve 27jResidual

,2-MV0P-74-048 IInstalled new None Worn out

RHR shutdown f auxiliary con-contacts jMotor controller not jReplaced auxiliary theat re-operating properly l contacts.

maval cooling itacts in motor l

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inboard starter l

6 iMR 320147 valve i

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BP.%~NS FERRY MUCLEAR PLAST IN17 3

"d N 3 HF EMSIL 30 CIC "

U" nis i ELECTRICAL MAINTENA.CE. SD0!ARY 9/29/82 For the Mynth of.___ November tg 84 Effect ca Safe.

action iaken Opera: ion of Cause.af R e 3 u ' t.. ;:

i Te Preclude

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The P.ractar L I f t.nc t i.,a

!!a l f un 'r in i Recurrence e

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'_iquid rad-3-LS-77-25A CS Replaced level None Bad level switch Invalid alarm Replaced switch

. acte

& RCIC pump rm switch l'

flood level MR 321635 switch e

t

5

:ntrol bag 3-CHR-31-1943 iReplaced motor Ncne Open circuit in Water chiller would Replaced protector P.e a t in g,

. shutdown bd rm! protector motor protector not operate i

ichiller3A i

MR 320184 l

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,3-TS-84-031 jChanged wiring None

. Temperature switch Invalid alarm Changed wiring tN2 temperaturet lwiredwrong according to draw-lto suppression l l

ing.

chambe.

MR 255054, 310830, l

304144; DR84-033G i

i m

o

.:re splay 3-HS-75-37A Replaced push- ' None Moisture in con-Handswitch malfunc-

' Replaced switches

aling system II mini button switches l trol box tioning f

mum flow g(Open-Close-iMR 171914

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Iisolation

'Stop) ivalve i

e i

i 2: Fesidual 3-TA-74-80

, Replaced card None IBad card l Invalid alarm l Replaced card n=2t re-

RHR cooling l

val water heat-i lMR 171936 exchanger tempi l

Hi I

i l

l

3 Eizh pres j 3-MV0P- ;-03

. Replaced cable lNont IP en circuit in i Valve inoperable l Replaced cable s re cool-i HPCI steam j

i

,caole j

att injec I line outboard i

,MR 320064

-ion (HPCI)! isolation l

i. valve l

4 j

i

titut,.ic.in F.AuchhtosoGr..wevatu cr<( i3:,1 l'* WNT 1984 For the Month of : wembe r _,19 I

EFFECT ON SAFE ACIION AKEN 1\\TE ' SYSTEM COMPONENT NATUP.E OF OFERATION OF CAUSE OF RESULIS OF TO PRECLUCE MAINTENANCE Tile REACTOR MALFUNCTION

!G LFCI;CTION RECURRE!. E So cajor non-routine itt ms l

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25 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT November 1984 I.

Unit 1:

Summary of Major Activities The unit 1 cycle 6 outage schedule is being developed. Preliminary sequencing of major maintenance, recirculation piping replacement, and selected modifications is currently underway.

II. Unit 2:

Summary of Major Activities A.

Refuel Floor 1.

Invessel flushes were discontinued on November 7,1984, due to inability to significantly reduce drywell radiation levels.

2.

Fuel sipping started November 18, 1984, and was postponed on November 22, 1984, due to new fuel delivery. Sipping will resume in January 1985. Eight bundles were sipped; one leaker was identified.

3.

Fuel receipts started on November 25, 1984.

B.

Turbine 1.

Disc inspection of low-pressure "C" rotor was completed.

2.

Number 3 and 4 bearings and 8th stage diaphragms were returned from PSS on November 14, 1984.

3.

The new (low-pressure "A") rotor is at Muscle shoals, ready for shipment to Browns Ferry.

C.

Drywell Control Rod Drive changeout started November 1,1984, and was finished November 19, 1984. Forty CRDs were changed out.

D.

Balance-of-Plant 1.

"B" string feedwater heaters are tagged for maintenance.

2.

"A" and "C" string feedwater heaters were probologged.

3.

Residual Heat Removal (RHR) heat exchanger "B" was probologged but not plugged from the bottom.

RHR heat exchanger "D" was probologged and plugged.

RHR heat exchanger "A" was probologged and is currently open.

E.

In-service Inspection of Primary Piping System Welds 1.

MINAC has not been successfully run; started on November 25, 1984.

2.

172 of 204 UT inspections are completed; 158 acceptable, 12 under evaluation, 2 rejected (KR-2-37 and KRWC-2-4).

~. ' '

26 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGENENT NOVEMBER 1984 II. -Unit 2:

Sunmary of_ Major Activities (Continued)

F.

Mechanical Maintenance 1.

HPCI turbine maintenance is complete.

B.

"B" CCW pump pit and "B" fire pump maintenance are conplete.

"A" CCW pump pit is drained.

-"Gr Electrical ~ Maintenance- "~-- ~ ~ ~ ~ " ~ ~ ~ ~ ~ ~ ~ ~ ~~

~~~

1.

Units 1 and 2 "B" diesel outage for annual surveillance testing was completed.

~

2.

Routine Electrical Maintenance Instructions are in progress.

H.

Instrument Maintenance 1.

Reactor Protection _ Isolation System probes for changeout Control

~~ Rod Drives ~were' replaced. ~

~ ~'~~

- ~ "

2.

Routine System Instrument Maintenance Instructions are in progress.

I.

Mechanical Modifications 1.

Torus drain started November 1,1984 and is still in progress.

2.

Valve work:

74-67

- -Complete 74-68,71-580, 73-603 In Progress-

"C" and "B" I/B Main Steam Isolation Valve in progress.

I 3.

Main Steam Relief Valves were removed and boxed.

4.

Main steam drain vacuum breakers were removed.

~J.

Electrical / Instrument Modifications 1.

Recirculation pump motor maintenance is in progress on "A" and "B" motors.

2.

Recirculation motor / generator (MG) set maintenance continues on "A" and "B" MG sets.

3 Torus /IHSI power supplies are being rerouted from U-3 to U-2.

K.

Security Modifications Eighty-eight days remain for completion of physical security plan modifications.

L.

Other 1.

Inspections of structural steel by 0.E. started on November 15, 1984, and are in progress.

2.

Standard Practice BF 8.3 should be approved by PORC soon to allow l

. ork plans for. unit 2 modifications to progress.

w

._._ _.. 3._..Limitorque_ inspections _are_in. progress to.. verify._ nameplate: data.-

l on prospective IEB 79-01B valves.

^

27 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGENENT NOVEMBER 1984 III. Unit 9:

Summary of Major Activities The unit 3 cycle 5 outage work activities were closed out during the October report period and startup was begun October 28, 1984. However, a question concerning a procedural interpretation caused the startup* to be placed on hold pending resolution.

Permission was granted by PORC to resume the unit 3 startup on November 17, 1984. Delays due to problems with dew point analyzer equipment in the offgas system and reactor water cleanup solenoid valve repairs prevented rod pulls until November 19, 1984. Criticality was achieved at 2349 hours0.0272 days <br />0.653 hours <br />0.00388 weeks <br />8.937945e-4 months <br /> on this date, but the startup/ test sequence had to be interrupted November 20, 1984 due to low reactor water level indication problems.

Following calibration checks on the reactor water level instrumentation and some miscellaneous valve and flange leak repair, unit 3 startup was again resumed. The generator was tied on line at 2206 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.39383e-4 months <br /> November 28, 1984, ending the refueling outage duration at 450 days. Additional testing is still being performed in preparation for full power operation.

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4 TENNESSEE VALLEY AUTHORITY Brwns Ferry Nuclear Plant P. O. Box 2000 Decatur,-Alabama 35602 DEC 141984 Nuclear. Regulatory CommJssion Office of Management Infor1 nation and Program Control Washington, DC 20555 Gentlemen:

Enclosed is_the November 1984 Monthly Operating Report to NRC for Brw ns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AUTHORITY 4

$}MO G. T Jones Plan 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-

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