ML18024B233

Forwards Monthly Operating Repts for Dec 1979

ML18024B233
Person / Time
Site:	Browns Ferry
Issue date:	01/09/1980
From:	Abercrombie H TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
Shared Package
ML18024B234	List: ML18024B233 ML18024B236
References
NUDOCS 8001150488
Download: ML18024B233 (32)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT December 1, 1979 December 31, 1979 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By

fi ~c P ant S erintendent

TABLE OF CONTENTS Operations Summary .

Refueling Information Significant Operational Events Average Daily Unit Power Level lo Operating Data Reports 13 Unit Shutdowns and Power Reductions. 16 Plant Maintenance 19 Outage Summary ~ 1 ~ ~ ~ ~ ~ ~ 26

0 erations Summar The following summary describes the significant operational activities during the reporting period. Tn support of this summary, a chronological log of significant events is included in this report.

There were fourteen reportable occurrences reported to the NRC during the month of December.

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

Unit 2 There were three scrams on the unit during the month. On December 2, the reactor scrammed due to abrupt movement of the turbine control valves apparently caused by EHC pressure control problems. The turbine control valves abruptly opened, then started closing, leading to a high neutron flux scram. The reactor was manually scrammed on December 13 to investigate vibration on the 2A recirculation motor, pump, and associated piping. On December 17, the reactor was manually scrammed for implementation of modifica-tions of certain PCIS valves and the installation of acoustic monitoring instrumentation on the MSRV's.

Unit 3

0 erations Summa (Continued)

Unit 3 Unit startup (BOC-3) following a refuel outage began on December 6.

The unit scrammed once during the month. On December 30, the reactor was manually scrammed to install overhead cables from the cooling tower switch gear to the bus tie boards.

Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00421 0. 00317 0.00283 Feedwater nozzle 0.20264 0. 13592 0.10480 Closure studs 0.17644 0.11572 0.08561 Note: This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.

Common S stems Approximately 1.13E+06 gallons of waste liquid were discharged containing 2.75E+00 curies of activity.

Refuelin Information Unit 2 Unit 1 is scheduled for its third refueling beginning on or about January 3, 1980, with a restart date of February 19, 1980. This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel, LPCI modifications, installing acoustical monitors on KSRV's, and containment isolation modifications.

There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies, two 8 x 8 R fuel assemblies, and 252 new fuel assemblies. Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 720 assemblies. With present capacity, Unit 1 does not have full core discharge capability in the pool.

Unit 2

'I Unit 2 is scheduled for its third refueling beginning on September 1, 1980, with a scheduled restart date of October 7, 1980. Resumption of operation on that date will require a change in technical specifications pertaining to the core thermal limits. Licensing information in support of these changes will be submitted to the NRC before the outage. This refueling involves replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.

There are 764 fuel assemblies in the reactor vessel. At the end of the month, there were 132 discharged cycle 1 fuel assemblies and 268 discharged cycle 2 fuel assemblies in the spent fuel storage pool. The present storage capacity of the spent fuel pool is 1080 assemblies. With present capacity, the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Refuelin Information (Continued)

Unit 3 Unit 3 resumed power operation December 8, 1979, after its second refuel outage which began August 24, 1979. Unit 3 is scheduled for its third refueling beginning on September 6, 1980, with a scheduled restart date of October ll, 1980. This EOC-3 refueli'ng involves loading additional 8 x 8 R (retrofit) assemblies into the core.

There are 764 fuel assemblies presently in the reactor vessel. There are 144 discharged cycle 2 fuel assemblies and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool. The present storage capacity of the spent fuel pool is 1528 assemblies. With present capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Si nificant Operational Events Unit 1 Date Time Event 12/01/79 0001 Reactor thermal power at 92%, core limited 0020 Reduced thermal power from 92% to 80% for turbine C.V. tests and SI's 0150 Turbine C.V. tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 91%, core limited 12/03/79 1500 Reactor thermal power at 90%, core limited 12/05/79 0700 Reactor thermal power at 89%, core limited 12/07/79 2115 Reduced thermal power from 89% to 75% for turbine C.V. tests and SI's a 2143 Turbine C.V. tests and SI's completed, commenced power ascension 2310 Commenced PCIOMR from 82% thermal power 12/08/79 1500 Reactor thermal power at 89%, core limited 12/10/79 0700 Reactor thermal power at 88%, core limited 1500 Reactor thermal power at 88%, core limited 12/12/79 1500 Reactor thermal power at 87%, core limited 12/14/79 2300 Reactor thermal power at 86%, core limited 12/17/79 1500 Reactor thermal power at 85%, core limited 12/21/79 1500 Reactor thermal power at 84%, core limited 12/30/79 0930 Peduced thermal power from 84% to 73% for control rod scram testing 1620 Control rod scram testing completed, commenced power ascension 1730 Reactor thermal power at 84%, core limited 12/31/79 2400 Reactor thermal power at 84%, core limited

Si nificant 0 erational Events

'Unit 2 Date Time Event 12/Ol/79 0001 Reactor thermal power at 65%, sequence "B" with power ascension in progress 1200 Commenced FCIOM from 80% thermal power 12/02/79 0555 Reactor scram no. 89 (1) from 100% thermal power (suspected EHC pressure regulator printed circuit board problems caused the turb control valves to open excessively and then abruptly began closing) 0755 Commenced rod withdrawal 1202 Reactor critical no. 100 1417 Rolled T/G 1439 Synchronized generatory, commenced power ascension 12/03/79 0020 , Reduced thermal power from 70% to 65% for control rod pattern adjustment 0755 Control. rod pattern adjustment completed, commenced power ascension 1500 Reactor thermal power at 70%, holding for "A" reactor feedpump vibration checks 12/05/79 0040 Commenced power ascension from 70% thermal power 0400 Reduced thermal power from 90% to 70% for removal of "A" reactor feedoump from service for maintenance 12/08/79 0030 Connnenced turbine C.V. tests and SI's 0220 Completed turbine C.V. tests and ST.'s, commenced power ascension from 70% thermal power 0730 Reactor thermal power at 75%, holding for "A" 'reactor feedpump maintenance 12/09/79 2200 "A" reactor feedpump maintenance completed, connnenced power ascension 12/10/79 0130 Commenced PCXOHR frcm 80% thermal power 2348 Reactor thermal power at 96%, holding due to excessive vibration on "A" recirculation pump 12/10/79 0700 Reduced thermal power from 96% to 94% due to excessive vibration on "A" recirculation oump 12/13/79 2000 Commenced reducing thermal power to shutdown for "A" recirculation pump maintenance 2204 Reactor scram no. 90 manual from 40% thermal power to acconnnodate maintenance to "A" recirculation pump 12/14/79 2005 Maintenance completed on 2A recirculation pump, holding for maintenance on FCV-1-55 valve

1 Si nificant 0 erational Events Unit 2 Date Tfrae Event 12/15/79 1821 IMntenance completed on FCV-1-55 valve, commenced rod withdrawal for startup 1930 Reactor critical no. 101 2347 Rolled T/G - could not reach rated spped, EHC problems (electronic card) 12/16/79 0118 Turbine tripped 0125 Rolled T/G 0330 Synchronized generator, commenced power ascension 2300 Commenced PCIOHR from 78% thermal power 12/17/79 0035 Reactor thermal power at 85%, holding for turbine C.V. tests and SI's 0245 Turbine C.V. tests and SI's completed, commenced PCIONR from 85% thermal power 2122 Commenced reducing thermal power from 90% for shutdown for modifications 2220 Reactor scram no. 91 manual from 35%'hermal power to accommodate PCIS post modification 12/18/79 0910 Reactor at cold shutdown 12/22/79 2300 PCIS 'post modification tests completed, commenced rod withdrawal 2345 Reactor critical no. 102 12/23/79 1535 Rolled T/G 1611 Synchronized generator, commenced power ascension 12/24/79 0135 Commenced PCIOMR from 50% thermal power 12/25/79 1500 Reactor thermal power at 85%, flow limited 12/28/79 2325 Reduced thermal power from 85% to 50% for control rod scram testing 12/29/79 0200 Control rod scram testing completed, commenced power ascension 0500 Commenced PCIOHR from 65% thermal power 12/30/79 1500 Reactor thermal power at 98%, flow limited 12/31/79 2400 Reactor thermal power at 98%, flow limited

Si nificant 0 erational Events Unit 3 Date TMe Event 12/01/79 0001 Reactor shutdown for EOC 2, with BOC 3 fuel loaded in vessel 1245 Commenced pressurizing reactor vessel for hydrostatic test 1325 Reactor vessel pressure at 1005 PSI, holding for hydro-static test 1450 Commenced reducing reactor pressure to 570 PSI, holding for drywell leak checks 2045 Reduced reactor pressure to zero 12/06/79 0400 Commenced rod withdrawal for startup 0645 Reactor critical no. 88 12/08/79 1441 Rolled T/G 1615 Synchronized generator, commenced power ascension as conditions allow 12/15/79 2330 Reduced thermal power from 80% to 66% for RTI's 23A, 22 and 32A 12/17/79 2000 RTI's completed, commenced power ascension 12/18/79 1145 Reactor thermal power at 79%, flow limited 12/20/79 0830 Reduced thermal power from 79% to 60% for control rod pattern adjustment 2005 Commenced power ascension 12/21/79 0300 Commenced PCIOMR from 64% thermal power 12/23/79 0706 Reduced thermal power from 98% to 70% due to "A" and "B" string high pressure heaters isolation 0745 High pressure heaters "A" and "B" returned to service, commenced power ascension 1100 Commenced PCIONR from 88% thermal power 2200 Reactor thermal power at 97%, flow limited 12/24/79 1926 Reduced thermal power from 97% to 57% for control rod sequence exchange from "A" to "B" 2114 Control rod sequence exchange completed, commenced power ascension 2300 Commenced PCIOtlR from 67% thermal power

Si nificant 0 erational Events Unit 3 Date Tame Event 12/26/79 0850 Reduced thermal power from 92% to 86% for condensate demineralizer backwash and precoat 1145 Condensate demineralizer backwash and precoat completed, commenced PCIONR from 86% thermal power 12/27/79 0600 Reactor thermal power at 98%, flow limited 1800 Reduced thermal power from 98% to 80% for condensate demineralizers "A" and "3" backwash and precoat 1930 "A" and "B" condensate demineralizer placed in service, holding for "C" and "H" condensate demineralizer backwash and precoat 2245 "C" and "H" condensate demineralizer placed in service, commenced po~er ascension 12/28/79 0300 Commenced PCIOMR from 90% thermal power 0700 Reactor thermal power at 98%, flow limited 1257 Reduced thermal power from 98% to 85% for condensate demineralizer maintenance 12/29/79 2002 Condensate demineralizer maintenance completed, commenced power ascension 12/30/79 0700 Reactor thermal power at 98%, flow limited 2000 Commenced reducing thermal power for shutdown to install overhead cables from cooling tower switchgear to bus tie boards 2230 Reactor scram no. 79 manual from 35% thermal power to accommodate maintenance 12/31/79 2400 Unit at cold shutdown (1) Equipment malfunction

10 AVERAGE DAILYUNIT POWER LEVEL DOCKET >NO.

UNIT DATE MONTH December 197.9 DAY . AVERAGE DAlLYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe Net) (MWe.Net) 964 915 l7 IS 910 3 19 908 20 905 953 895-2,1 953 22 910 933 895 23 934 897 952 '>5 890 IO 938 26 892 943 870.

27 l2 929 2S 916 926 '>9 844 I3 926 838 14 30 915 877 IS 3l l6 920 INSTRUCTIONS On this format.!ist the average daily unit power level in MWe.Net for each day >n the rep<>rtine >n>>nti>. Ci>mpute tu the nearest whole megawat t.

~ ~

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

v UNIT DATE 1- 0-80 CO~IPLETED BY TELEPHONE iE(ON TH December 1979 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-iVet) 17 18 -12 3 676 19

-10 20 819 21 805 -10 810 136 7t 23 800 680 807 865 25 965 897 10 26 1031 27 1013 887 12 28 13 916 29 801

-13 1045 l4 30 1062 IS 3I 541 16 INSTRUCTIONS On this format. list the average daily unit pi>wer levei'n l>I'tVe.Net for each day in the repi>rtinu lnontll. Ci>ltlpute to the nearest whole tnega.vat t.

[9l77 s

12 AVERAGE DAlLYUNIT POWER LEVEL

'DOCKET NO. 50 296 T

Browns Ferry 3 DATE ~E!

COMPLETED BY Ted Tham

~

MONTH December 1979

~ r DAY AVERAGE DAlLYP01UER I.EVEL DAY AVERAGE DAILYPOWER LEVEL

(!tIWe-Net) (hI1Ve.Net) ~

I

-10 689

-10 839 l9 837 3

20 633

-10 21 747 959 23 1008 38 24 983 163 TS 808 223 974 IO 26 353 27 1002 477 1049 l2 28 515 871 l3 29 l4 68 30 963 IS 812 31

-12 724 INSTRUCTIONS On this format. !ist the average daily unir power level in Mac Nct for each day in thc reportin!t ntonth. Compute to tNe rtearcst whole megawatt; I')t77)

13 OPERATING DATA REPORT DOCKET NO.

1~5-80 COMpi,ETED BY ~Do Green TELEPHONE ~o U29-6846 OPERATING STATUS Notes

1. Unit Name

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross <II We):

S. Design Electrical Rating (Net M1Ve):

0 8.4

7. Maxuntum Dep e ndabl e Capa city(Ne ti'OWe: 1065

)

8. If Changes Occur in Capacity Ratings (Items Numoer 3 Through 7) Since Last Report, Give Reasons:

N A

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

10. Reasons For Restrictions, lf Any: N/A This Mon t h Yr.-to. Date Cumulative 744 47',498

12. Number Of Hours Reactor Was Critical 28,277.28

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 744 IS. Unit Reserve Shutdown Hours 0 0 0

'. 16. Gross Thermal Energy Generated (MWH) 74 136 493

17. Gross Electrical Energy Generated (MWH) 7,700,460 24,518,460 Ih. Net Electrical Energy Generated (M}VH) 7,495,748 23,801,968

19. Unit Service Factor, 100 100 90.4 90.4 58 '

58.1 20; Unit Availability Factor - ~

21. Unit Capacity Factor (Using ilIDC Net) 80.3 47.1

22. Unit Capacity Factor (Using DER Net) 47.1

23. Uiiit Forced Outage Rate 0 4.4 33.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duratinn of Each}:

Refuel January 1980

25. IfShut Dnwn At End Of Rcport Period. Estimated Date of Startup:

'26. Uiiits in Test Status iPri<<r to Coinmercial Operation}: Forecast Achieved INITIALCRlTICALITY INITIALELECTRlCITY COi'it'llERCIA L OPERATION io/77)

a ~ I OPERATING DATA REPORT DOCKET NO 5 1-260 BETE 1~5-BO C05tPLETED BY ~&Green TELEPHONE ~~o-6846 OPERATING STATUS

,5 Notes

1. Unit Name:

2. Reportfng Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Cross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross hIIVe): 1098.4

7. Maximum De p endable Ca p acit y(Net hllVe:

1065

)

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

N/A

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

10. Reasons For Restrictions, If Any:

This Month Yr:to.Date Cumulative I I. Hours In Reporting Period 744' 760 42 409

12. Number Of Hours Reactor Was Critical

~

571. 03 7,766.19 24,484.48

13. Reactor Reserve Shutdown Hours 172.97 298.23 -.11,774.94.

14. Hours Generator On. Line 543.98 ~ 7,596.45 23,664"31

15. Unit Reserve Shutdown Hours 0 5

. 16. Gross Thermal Energy Generated (MWH) 1,458,581 22,703,212 66,155,000

17. Gross Electrical Energy Generated (MWH) 475,610 7,636,280 21,950'b

. 18. Net Electrical Energy Generated (MWH) 461.952 7,441.305 21,3315469 19 Unit Service Factor 73.1 86.7 55.8 20., Unit Availability Factor 73e1 86.7 55.8

21. Unit Capacity Factor (Using hlDC Net) 58.3 79.8 47.2 2'2. Unit Capacity Factor (Using DER Net), 47.2

23. Unit Forced Outage Rate 10.3 2.7 36.8

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration uf Each):

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

26. Units In Test Status (Prior tn Commercial Operation): Forecast Achieved e

INITIALCRl'I'ICALITY INlTlAL ELECTRIC lTY COMht ERC I A L OPER ATlON (o/77)

15 OPERATING DATA REPORT DOCKET NO SQ-296 DATE E-5 ED COMPLETED BY TELEPHONE

~~MD

~~-6846 OPERATING STATUS, Notes

1. Unit Name'.

Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross hIWe):

S. Design Electrical Rating (Net MIVe):

6. ihlaximum Dependable Capacity (Gross MWe):

7. Maxtmum Dependable Capa CI ty (Net h IWe).

8. If Changes Occur in Capacity Ratings (Items Nxmber 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, lf Any (Net >IWe):

10. Reasons For Restrictions, lf Any:

This Month Yr..to.Date Cumulative

11. Hours ln Reporting Period

12. iNumber Of Hours Reactor Was Critical 591.75 5 816.35 18 907.55

13. Reactor Reserve Shutdown Hours 131.50 552.9 1,658.31 .

14. Hours Generator On-Line 534. 25 5,708.30 18438.28 IS. Unit Reserve Shutdown Hours

'6. Gross Thermal Energy Generated (MWH) 1 231 495 16 956 484 53.107 866 1.7. Gross Electrical Energy Generated (MWH) 403,790 5 635,080 17 402,580

18. Net Electrical Energy Generated (MPH) 390,613 5,482,585 16,887,773

19. Unit Service Factor 74. 2

20. Unit Availability Factor 71.8 65.2 74.2

21. Unit Capacity Factor (Using MDC Net) 4 8.8

22. Unit Capacity Factor (Using DFR Net) 49.3 ..-- 58.8 63.8

23. Unit Forced Outage Rate 4.6 8.0 9.0

24. Situ(downs Scheduled Over Next 6 hlonths (T ipe. Date. and Duration of Each):

S. If Shut Down At End Of Report Period. Estirrared Date of Startup:

6. Units ln Test Status (Prior to Commercial Op;mtion): Forecast Achieved liVITIAL CRITICALITY INITIALELECTRICITY COhth(ERCIAL OPERATIC'E

.- UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME rowns erry 1 DATE REPORT h(ONTII COhlPLETED IIV o t:re en TELEPilONE 205 29-68t'r6 t4 Cl

~ II Lieenscc C Cause k. Corrective Nii. nate fl 0 I cc Event Action to Cl CA Report 0' E Q

~ Prevent Recurrence O

I F: Forced S: Scheduled Reason:

0-hiaiotcoaoce or Test C-lfefueling

'(ethod:

A.l'.quipmcot Failure (Explain) I hlaoual 2.hlanual Scram.

3-Automatic Scram.

Exhibit C - Instructions for Preparation ot Data L'otry Sheets (or Licensee Eveot Report (LER>Flic (80REC-D Regulatory Restriction 4 Other (Explain) OI6I)

E"Operator Training k Liccnsc Examination I'.AJ toinist rat ive C.Operational Error (Fxplain) Exlubtl I ~ Saroi Soon.e (st/77) ll Other (I:xplaht)

DOCKET NO. 50-260

-- UNIT SIIUTDOWNS A4D POIVER REDUCTIONS

~

UNIT NAME Browns Ferr 2 COhIPLETED IIY REPORT hlOHTII C r<

<r< c u Licensee 0C<'n0 Cause 8'c Corrective I<o l)ale Cl Event Acttort to C<

¹

~

~ CJ Report < cn G Prcvcnt Recurrence Q ~CA g 109 791202 8.73 A . 3 Suspected EliC pressure regulator printed circuit board problems, caused control valve closure and turbine trip.

110 791213 53.44 Maintenance to "A" recirc pump and

.FCV-1-5.

'll 791217 137.85 Pcs t modifications to the primary containment isolation system.

112 791228 B Derated for control rod scram testin F: Forced Reason: Method: Exltibit G - Instructions S: Scl<eduletl A-Equipment Failure (Explain) I.hlanual for Pret)aratiott of Data I}.hlaintenance or Test 2rManual Scram. Entry Sheets I'or l.icensec C Rcfuclittg 3-Aulomalic Scram. Event Report (I.ER) Fii<s(NOREG-D.Regulatory Restriction 4.0tlter (Lxplain} OI 6 I }

E Operator Training lc License Examination I'dllltntslrall"e G Op<'tattuttal Error (Fxplain} Exhibit I ~ Sante Source

(<I/77) I I Otlt<'r (L<xplattt}

--- VNITSIIVTDOIVNS AND POlVER REDVCTIONS DOCKET NO. 50 296 UNIT NAh!E DATE REPORT hIO")TII COhIPLETED BY Mn~tJ:a V

I I

~ c un Lice<<scc Cause Corrective Ni I, Dull.' Vl tl Ec Event Aetio<< tu u

b AA Rcport ~

Prcvcnt Rccurrcncc 109 791201 S 184.25 Refueling 110 .791220 Derated for control rod pattern adjustment.

791924 H Derated for control rod sequence exchange.

112 791230 P 25.50 Ground in auxiliary power supply cables from cooling towers,to bus tie boards. Installation of over-head cables in progress.

3 F: Forced Reasun: hlethod: Exhibit G - Instructions S: Scheduled A.Equipmenl Failure (Explain) I 'hla<<ual for Preparatiun <<I'Data Il.hl;tintcnance or fest 2-hlanual Sera<<i'. Entry Sheets I'or l.ice<<see C-Rct'<<eliot, 3 Auto<<latic Scram. Event Report (LLR) Flh'WOREG-D.l<cttulatory Reslrictiun 4.Other (Explain) 016I ),

E-Ot>eratur Trainint', k Liccnsc Examination F-A Jlntrlist lative G Opclatil>>lal Lrrur (Explain) Exhibit I - Salnc Source (It/77) II Other ((explain)

BROWNS FERRY NUCLEAR PIANT UNIT 1 CSSC E UIPMENT MECIKHICAL MAINTENANCE SU%MARY ZR EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COi fPOHENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tl1E REACTOR MALFUNCTION MALFUNCTION RECURRENCE 12/9 HPCI FCV 73-16 Bad pinion With NPCI inop- Operation NPCI inoperable Replaced pinion gear gear able it could in valve limitorque force unit shutdown I

12/13 Rx. Bldg. Computer Room Damper closed None Unknown Hone Opened damper and Uent. Exhaust damper hooked linkage bac u 12/13 Fuel Pool "lA" FPC pump Disc pins None Operation None Replaced with r.ew Cooling discharge broken valve check valve 12/22 Fuel Pool Internal part None Operation None Replaced all internal Cooling "lA" FPC worn parts pump

BROWNS FERRY NUCLEAR FIANT UNIT 2 CSSC E UIPMENT MECHANICAL MAINTENANCE SUl&fARY For the Month of EFFECT ON SAFE ACTION TAKEN DATE SYS TEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE 'QlE REACTOR 'ALFUNCTION MALFUNCTION RECURREkacE 12/17 CRD "B" CRD Dirty filter None Operation None Changed filter discharge filter 12/17 Main Steam FCV-1-55 Pressure seal None OPeration None Disassembled, leak cleaned and installed new pressure seal rin~

12/20 Radwaste FCV 2-77-2A Bad solenoid None Operation None Installed new solenoid valve

BROWNS FERRY NUCLEAR PLANT UNIT 3

? KQQQlICAL MAINTENANCE

SUMMARY

For the Month of December 19 79 EFFECT ON SAFE ACTION TAKEN SYS 621 COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE HAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 12/1 Control "3A" Control Bad Valve None Operation None Rebuilt valve Bay Vent Bay Chiller Nater Regu-lating Valve 12/12 Auxiliary HCV 3-12-708 Bad packing None Operation None Boiler glanQ leak 12/19 Rx. fiater FCV 69-60B Packing leak None Operation None Repacked valve Cleanup

BRO',FANS PERRY NUCLEAR PLANT UNIT 1 CSSC E UIPENT ELECTRICAL MAINTENANCE SENARY

~

For the Month of December 19 79 E ect on a e Action Taken Date System Component Nature of -Operation of Cause of Results of To Preclude Maintenance The Reactor . Malfunction Malfunction . Recurrence 12/9/79 HPCI FCV'73-16 HPCI auxilia~ HPCI inoperable Failed limit Auxiliary oil pump Replaced limit HPCI turbine oil pump will at the time of switch will not start switch. Auxiliary steam supply not start failure oil pump now starts valve motor from control as required.

room TR 146244 t

12/10/7 HPCI FCV-1-73-16 Failed limit HPCI- inoperable Failed limit Valve inoperable Replaced torque HPCI turbine switch at the time of switch on FCV switch, ran steam supply failure 73-16 EMI 18. Checked valve motor OK. TR 161333 12/12/79 250V 1A 250V bat- HPCI gland None Motor grounded Motor failed to Replaced motor.

battery tery board seal conden- operate Checked OK.

board ser blower TR 149686 motor ground-

'ed 12/31/79 Common 90-51 neutron Motor that None Bad motor Cam inoperable Replaced bad motor, unit monitoring drives pumps started unit. Checke is locked up, OK. TR 161539 blowing fudes

PROSER PERRY NUCLEAR PLP3lT URYT 2 .

CSSC E UIPMENT ELECTRICAL MAINTENANCE SALARY For the Month of December 19 79 ect on a e Action Taken Date System Component Nature of Operation of 'ause of Results of To Preclude Maintenance The Reactor. Malfunction Malfunction Recurrence 12/14/79 Hain FCV '2-1-55 Green light Not applicable Limit switch False indication Replaced limit switch I

steam steam line and open limit drive frozen drive and gear key drain valve switch not per EMI 16 and 18.

motor working right Checked OK.

TR 134713 12/20/79 Ventila- 8-3 drywell Breaker trips None Motor grounde'd Motor failed to Replaced motor.

tion air blower out when try- operate Checked OK.

motor ing to start TR 122352

EROUMR PERRX NUCLEAR PLY~VX tRlXX 3 ELECTRICAL MAINTENANCE Sl&QSRY Fore Month of December 19 79 ect on a e Action Taken Date System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor. Malfunction Malfunction Recurrence 12/4/79 Diesel D/G .3C failed Hi voltage None U-3C diesel Too high voltage Adjusted air gap.on generator to accept supply generator frequency generator load on frequency gen- pickup to reduce emergency load erator was supplied voltage to acceptance supplying too correct valve.

test high voltage to Checked OK.

SSPl and SSP2 TR 96702 BFRO 50 296/7923 12/5/79 Core spray FCV 75-50 Motor failed None SBM switch Valve would not Replaced SBM switch, (core spray to operate controls HIY operate. functional. Cheeked II test valve) were not ma!'ing OK. TR 146429.

motor Up

BROGANS 1ERRY NUCLEAR PLQ<T UNIT INSTRU? fENT MAINTENANCE SUGARY CSSC E UIPOKNT ~

FOR TI?E MONTH OF December 19 79 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN SYSTHf CO~fPOHENT OF OPERATION OF OF RESULTS OF TO PRECLUDE

? fAINTENANCE THE REACTOR  ? fALFUNCTION  ? fALFUNCTION RECURRENCE Init 1 Flow Indicator 2-10 FI-67-9A Calibr,ate None Instrum nt Drift Pegged Upscs,le None

.2-31 Neutron AERf-A Calibrate None Instrument Drift Rod Block came in None Monitoring with lg LPRM's in-stead of 13 Init, 2

?0?K Init 3 2-13 Standby 3D Air Com- Calibrate None Setpoint Drift Air Compressor shut None Die el pressor. Pres- off 3 PSI low Generator sure Switches 2-26 Standby 3A Diesel Replace None Leaking Gage Diesel Fuel in gage None Diesel Generator Fue1 Generator Pressure Gage 2-26 Radwa ste Lls 77 ll)B Clean None Static on Meter Static Charge Caused Hone Face Indicator to Stick

26 OUTAGE

SUMMARY

December 1979 The Unit 3, cycle 2 refuel outage was completed on Saturday, December 8, 1979, marking the completion of a 107 day modification, maintenance, and refuel outage.

Unit 2 was shutdown on December 17 for modifications to the primary con-tainment isolation system and installation of an accoustic monitoring system for the main steam relief valves. During this outage, approximately 80 percent of the repair items on the Unit 2 short outage list were completed as well as the PCES and accou tic monitoring mods. Unit 2 was returned to service on December 23.

Unit 3 was shutdown on December 30 for a modification to install an alternate power supply from the cooling tower transformers to the Unit 3 shutdown bus tie board. This modification should be completed and the unit returned to service by the middle of January.

Preparations have been underway for the upcoming Unit 1, cycle 3 refueling outage and should be completed by January l. Unit 1 is scheduled for a 48 day refueling outage to begin January 3, 1980.