ML18024A800

Monthly Operating Rept for Apr 1979

ML18024A800
Person / Time
Site:	Browns Ferry
Issue date:	04/30/1979
From:	Dewease J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A799	List: ML18024A798 ML18024A800
References
MOR-790430, NUDOCS 7905150352
Download: ML18024A800 (36)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT April 1, 1979 - April 30, 1979 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By:

Plant Superintendent

TABLE OF CONTENTS Operations Summary .

Refueling Information Significant Operational Events ~ ~ 5 Average Daily Unit Power Level ~ ~ 13 Operating Data Reports ~ ~ 16 Unit Shutdowns and Power Reductions. ~ ~ 19 Plant Maintenance ~ ~ 22 Outage Section Monthly Report. "

34

0 erations Summar The following summary describes the sign ificant c o p erational activities during the reporting period. Xn support o f this summary a chronological logo f i s gn ificant events is included in this report.

There were three reportable occurrenceses rep re orted to the NRC during the month of April.

Unit 1 The unit i scramme d tw ce d ur ing the month. The unit scramm ed on AP ril 2 due to stop valve closure from a turb ine ne trip..

tr The turbine trip occurred as a result of a false mo isture t e separator s high level signal apparently generated by vibration o fa loose oose sensing line on C2 moisture separator.

The unit scrammed on Apr il 29 due to stop valve closure from a turbine trip. Th e tur bine trip occurred as a resultt of a false reactor high water level signal generateed due ue to a breaker opening and resultant loss of power.

Unit 2 The unit scrammed once i d ur ng thee month.

m The unit was manually scrammed on Apr il 27 to accomodate the scheduled refueling outage.

Unic 3 The unit did not scram during the month.

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 0.00407'.00270 0.00243 Feedwater nozzle 0.18684 0.11861 0.09515 Closure studs 0.17378 0.10335 0.07339 Note: This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.

Common S stems Approximately 2.56E+05 gallons of waste liquid were discharge containing 1.55E-Ol curies of activity.

Cooling towers 1, 2, 3, and 6 were operational. Repair work on Tower 4 began on April 10, and is to be completed by May 8. Repair work on Tower 5 was completed on April 30. Installation of new fillmaterial on Tower 5 continues.

Refuelin Information Unit 1 Unit 1 is scheduled for its third refueling beginning on or about December 15, 1979, with a restart date of January 25, 1980. This refueling will load additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel.

Unit 1 (Continued)

There are 764 fuel assemblies in the core. The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies and two 8 x 8 R fuel assemblies. Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 520 assemblies.

pith present capacity, Unit 1 does not have full core discharge capability in the pool.

Unit 2 Unit 2 began its second refueling beginning on April 27, 1979, with a'cheduled restart date of June 7, 1979. 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 was submitted to the NRC in February. This refueling will involve replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.

There are 764 fuel assemblies in the core. At the end of the month there were 132 discharged cycle 1 (7 x 7) fuel assemblies in the spent fuel storage pool. There are presently 268 new 8 x 8 fuel assemblies in the spent fuel storage pool. The present storage capacity of the spent fuel pool is 1080 assemblies. Present planning is to increase that capacity to 3471 assemblies. With present capacity, the 1979 refueling would be the last refueling that could be discharged to the'pent fuel pool without exceeding tha't capacity and maintaining full core discharge capability in the pool.

Unit 3 Unit 3 is scheduled for its next refuel outage beginning on September 1, 1979, with a scheduled restart date of November 20, 1979. This refueling will involve loading additional 8 x 8 R (retrofit) assemblies into the core, torus integrity modifications, core spray piping modifications, EECW

~ .piping changes, feedwater sparger modifications, and LPCI modifications.

Resumption of operation following refueling will require changes in technical specifications pertaining to the core thermal limits. Licensing information in support of these changes will be submitted before the refueling.

There are 764 fuel assemblies presently in the core. There are 208 fuel assemblies in the spent fuel storage pool. The present licensed storage capacity of the spent fuel pool is 1132 assemblies.

Si nificant 0 erational Events Unit 1 Date Time Event 4/1/79 0001 Reactor thermal power at 66%, sequence "B", holding for control rod pattern adjustment 0030 Control rod pattern established, commenced PCIOMR from 66% thermal power 2230 Reactor thermal power at 97%, rod limited 4/2 1440 Reactor scram no. 110 (1) from 97% thermal power due to turbine trip and stop valve closure 1635 Commenced rod withdrawal 1840 Reactor critical no. 126 2000 Rolled T/G 2015 Synchronized generator, commenced power ascension in sequence "B" 4/3 0250 Commenced PCIOMR from 60% thermal power 4/5 '710 Reactor thermal power at 96%,. rod limited 4/6 2145 Reduced thermal power from 96% to 70% for turbine C.V. tests and SI's 4/7 0115 Turbine C.V. tests and SI's completed, commenced power ascension 0300 Commenced PCIOMR from 75% thermal power 4/8 2105 Reactor thermal power at 98%,.steady state 4/13 2330 Reduced thermal power from 98% to 85% for turbine C.V.

tests and SI's 4/14 0105 Turbine C.V. tests and SI's completed, reduced thermal power further to 75% for removal of "B" condensate booste pump from service for maintenance 0400 "B" condensate booster pump maintenance completed, placed pump in service, commenced power ascension 0450 Commenced PCIOMR from 90% thermal power 4/15 1500 Reactor thermal power at 98%, steady state 4/16 0217 Reduced thermal power from 98% to 75% for removal of "A" reactor feedwater pump for maintenance 0420 "A" reactor feedwater pump maintenance completed, pump returned to service, commenced power ascension 0445 Commenced PCIOMR from 90% thermal power 1630 Reactor thermal power at 98% steady state

Si nificant 0 erational Events Unit 1 Date TfRe Event 4/21 1915 Reduced thermal power from 98% to 90% due to "C" string low pressure feedwater heaters isolation (broken air line) 2312 Reduced thermal power from 90% to 85% for turbine C.V. tests and SI's 4/22 0100 Turbine C.V. tests and SI's completed, commenced power ascension 0120 Commenced PCIOMR from 90% thermal power 0700 Reactor thermal power at 99%, steady state 4/25 0805 Reduced thermal power from 99% to 85% due to both recirculation pumps run back during SI (feedwater controls malfunction) 0810 Commenced power ascension 1200 Reactor thermal power at 99%, steady state 4/26 1500 Reactor thermal power at 99%, steady state.

4/27 2300 Reduced thermal power from 99% to 75% for turbine C.V. tests and SI's 4/28 0025 Increased thermal power to 90%, holding for control rod drive exercise 0200 Commenced PCIOMR from 90% thermal power 0730 Reactor thermal power at 99%, steady state 4/29 1922 Reactor scram no. 111 from 99% thermal power on turbine trip and stop valve closure due to loss of 120 volt preferred power ("C" shutdown board) causing feedwater control problems 4/30 0140 Commenced rod withdrawal for startup 0355 Reactor critical no. 127 0410 Reactor made subcritical, holding for changing out main transformer 1600 Resumed rod withdrawal for startup 1605 Reactor critical no. 128 2250 Rolled T/0 2308 Synchronized generator 2400 Reactor thermal power at 20%, with power ascension in progress (1) Equipment malfunction (2) Cause unknown

Si nificant 0 erational Events Unit 2 Date Time Event 4/1/79 0001 Reactor thermal power at 96%, sequence "B", PCIOMR in progress 0700 Reactor thermal power at 99%, steady state 4/3 1500 Reactor thermal power at 99%, steady state 4/5 0015 Reduced thermal power from 99% to 85X for condensate demineralizer backwash and precoat 0112 Condensate demineralizer backwash and precoat completed, commenced power ascension 0200 Commenced PCIOMR from 95% thermal power 0700 Reactor thermal power at 99%

4/6 2155 Reduced thermal power from 99% to 90% for turbine C.V. tests and SI's 2345 Turbine C.V. tests and SI's completed, commenced power ascension 4/7 0010 Commenced PCIOMR from 95X thermal power 0400 Reactor thermal, power at 99%

2200 Reduced thermal power from 99% to 88% for condensate demineralizer backwash and precoat 4/8 0235 Condensate demineralizer Sackwash and precoat completed, commenced power ascension 0300 Commenced PCIOMR from 95% thermal power 0700 Reactor thermal power at 99%

4/12 0125 Reduced thermal power from 99% to 85X for condensate demineralizer backwash and precoat 0230 Condensate demineralizer backwash and precoat completed, commenced power ascension 0700 Reactor thermal power at 97X, rod limited 4/13 2325 Reduced thermal power from 97% to 85% for turbine C.V.

tests and SI's 2340 Commenced condensate demineralizer backwash and precoat 4/14 0025 Turbine C.V. tests and SI's completed,.holding for condensate demineralizer backwash and precoat 0110 Condensate demineralizer backwash and precoat completed, commenced power ascension 0300 Commenced PCIOMR from 90% thermal power 0700 Reactor thermal power at 96%, rods limited

Si nificant 0 erational Events Unit 2 Date Time Event 4/15 0930 Reduced thermal power from 96% to 90% for removal of "A" string high pressure feedwater heaters from service for maintenance (leakage) 1706 "A" string high pressure feedwater heaters maintenance completed and placed in service, commenced power ascension 1900 Commenced PCIOHR from 93% thermal power 4/16 0015 Reduced thermal power from 95% to 85X for condensate demineralizer backwash and precoat 0210 Condensate demineralizer backwash and precoat completed, commenced power ascension 0330 Commenced PCIOMR from 95% thermal power 0700 Reactor thermal power at 96%, rods limited 4/20 0125 Reduced thermal power from 96% to 85% for condensate demineralizer backwash and precoat 0223 Condensate demineralizer backwash and precoat completed, commenced power ascension 0700 Reactor thermal power at 95%, rods limited.

4/21 0440 Reduced thermal power from 95X to 85% for condensate demineralizer backwash and precoat 0545 Condensate dermineralizer backwash and precoat completed, commenced power ascension 0815 Reactor thermal power at 95%, rods limited 4/22 0020 Reduced thermal power from 95X to 85% for condensate demineralizer backwash and precoat 0130 Condensate demineralizer backwash and precoat completed, commenced power ascension 0515 Reactor thermal power at 94%, rods limited 4/25 0140 Reduced thermal power from 94% to 85% for condensate demineralizer backwash and precoat 0300 Condensate demineralizer backwash and precoat completed, commenced power ascension 0330 Reactor thermal power at 94%, rods limited 4/26 2200 Reduced thermal power from 94% to 70X for scram timing control rods

Si nificant Operational Events Unit 2 Date Time Event 4/27 0250 Control rod scram timing completed, commenced power ascension 0345 Reactor thermal power at 93%, rods limited 1954 Commenced reducing thermal power for shutdown (scheduled refueling outage, cycle 3) 2213 Reactor scram no. 76 manual from 35% thermal power 4/30 2400 Reactor at cold shutdown with cycle 3 refueling outage in progress e t I

~ ~ ~

~ ','D

10 Si nificant Operational Events Unit 3 Date Time Event 4/1/79 0001 Reactor thermal power at 70%, sequence "B", holding for STI 162 (load following) 0321 Commenced power ascension 0700 Commenced PCIOMR from 96% thermal power 1530 Reactor thermal power at 99%, steady state 2315 Reduced thermal power from 99X to 68% for maintenance to EHC (leakage) 4/2 0400 Maintenance to EHC completed, commenced power ascension 0700 Reactor thermal power at 99%, steady state 4/6 0243 Reduced thermal power from 99% to 90% for condensate demineralizer backwash and precoat 0542 Condensate demineralizer backwash and precoat completed, commenced power ascension 4/7 '008 Reduced thermal power from 97X to 70% for turbine and SI's C.V.'ests 0120 Turbine C.V. tests and SI's completed, reduced thermal power from 70% to 50% for STI 162 (load following test-Phase 2) 0755 Commenced power ascension, part of STI 162 0940 Reduced thermal po~er from 90% to 80% for control rod pattern adjustment 1400 Control rod pattern adjustment completed, commenced power ascension 1500 Commenced PCIOMR from 95% thermal power 2120 . Reduced thermal power from 99% to 50% for STI 162 (load following test) 4/8 0428 Commenced power ascension, part of STI 162 1155 Commenced PCIOMR from 90X thermal power 1800 'Reduced thermal power from 99% to 50% for STI 162 (load following test) 2303 Commenced power ascension, part of STI 162 4/9 0405 Commenced PCIOMR from 90% thermal power 0810 Reduced thermal power from 95% to 85% for control rod pattern adjustment 1100 Control rod pattern ad)ustment completed, commenced PCIOMR from 85% thermal power 1830 Reactor thermal power at 99%, steady state

11 Si nificant 0 erational Events Unit 3 Date Time Event 4/12 2100 Reduced thermal power from 99% to 72% for control rod pattern ad/ustment 2215 Control rod pattern adjustment completed, commenced power ascension 2230 Commenced PCIOMR from 90% thermal power 4/13 1355 Reactor thermal power at 99%, steady state 1910 Reduced thermal power from 99% to 85% for condensate demineralizer backwash and precoat 2145 Condensate demineralizer backwash and precoat completed, commenced power ascension 2300 Commenced PCIOMR from 88% thermal power 4/14 0140 Reactor thermal power at 90%, holding for turbine C.V.

tests and SI's 0355 Turbine C.V. tests and SI's completed, resumed PCIOMR 0700 Reactor thermal power at 99%, steady state 4/20 2200 Reduced thermal power from 99% to 40% for control rod sequence exchange from "g" to "3" 4/21 0330 Control rod sequence exchange from "A" to "B" completed, commenced power ascension 0700 Commenced PCIOMR from 70%

4/22 1330 Reactor thermal power at 99%, steady state 4/24 0152 Reduced thermal power from 99% to 85% for condensate demineralizer backwash and precoat 0500 Condensate demineralizer backwash and precoat completed, commenced PCIOMR from 85% thermal power 1500 Reactor thermal power at 99%, steady state 2155 thermal power from 99% to 65% for control rod

'educed pattern adjustment 4/25 0010 Control rod pattern ad)ustment completed, commenced power ascension 1200 Commenced PCIOMR from 88% thermal power 4/26 1500 Reactor thermal power at 99%, steady state 4/28 0048 Reduced thermal power from 99% to 80% for removal of "C" reactor feedwater pump from service for maintenance due to high vibration 0230 Commenced turbine C.V. tests and SI's-0400 Turbine C.V. tests and SI's completed, holding at 80%

thermal power for "C" reactor feedwater pump maintenance

12 Si nificant Operational Events Unit 3 Date Time Event 4/30 1244 "C" reactor feedwater pump maintenance completed and pump placed in service 1335 Commenced power ascension from 80% thermal power 1400 Commenced PCIOMR from 90% thermal power 1550 Reduced thermal power from 91% to 80% for removal of "C" reactor feedwater pump from service due to high vibration 2400 Reactor thermal power at 80%, holding for vibration checks on "C" reactor feedwater pump

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

DATE COMPI ETED 8Y Ted Thorn TELEPHONE 205/729-6846 MONTH DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net)

I 44 17 18 19 950 20 1041 21 1021 1052 855 1061 7 23 989 1064 24 1058 25 1056 1056 1048 10 26 1062 27 12 1059 1051 28 1062 848 13 29 985 14 30 15 1060 31 1020

~

16 INSTRUCTIONS .

On this format, list the average daily unit power level in Mme Net for each day in the reporting ntonth. Compute to the nearest whole megawatt.

(t)(77)

~ ~

0 AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

UNIT Bro~s Ferry 2 DATE

'~"'ELEPHONE 205/729-6846 MONTH A ril 1979 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEI.

(MWe-Net) (MWe-Net) 17 03 1076 IS 1033 1077 19 1027 1077 1019 20 1067 1015 21 1069 ~

22 1013 1057 23 1013

, S 24 1009

'

1067 25 1001 1058 979 10 26 0 27 866 12 1050 28

-15 13 29 14 1040 30 IS 1022 31 16 1033 INSTRUCTIONS

'n this format, list the average daily unit power level in hIEVe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(~)/77)

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

Browns Fer 3 DATE 5/2/7 COMPLETED BY TELEPHONE 205/729-6846 MONTH A ril 197 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net) 1006 17 1066 992 18 1069 1065 1061 19 1067 1033 20 1073 21 759 1028 1042 6 22 811 1066 793 1017 24 946 917 10 1057 26 1006 1064 27 1088 12 28 842 13 1033 29 864 1060 866 14 30 1067 IS 31 16 1069 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

16 OPERATING DATA REPORT DOCKET NO.

DATE 5~

~9 COMPLETED BY ~ZORIL TELEPHONE 2QSLZ~46 OPERATING STATUS Bro~s Ferr Notes Unit Name:

1.

2. Reporting Period: A ril 1979

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions, If Any:

This Month Yr:to-Date Cumulative

12. Number Of Hours Reactor Was Critical

-219

'4 ~ 53 2 287.86 22 519.45

13. Reactor Reserve Shutdown Hours 167.31 4566.44

14. Hours Generator On-Line 2193. 21885.0 "

15. Unit Reserve Shutdown Hours 0 0

16. Gross Thermal Energy Generated (MWH) 2~ 145 926 6 294 977 57 067 649

17. Gross Electrical Energy Generated (MWH) 2,100,300 18,918,300

18. Net Electrical Energy Generated (MWH) 2 044 386 18 356 606

19. Unit Service Factor 95.5 76.2 52.6

20. Unit Availability Factor 76.2 52. 6

21. Unit Capacity Factor (Using MDC Net) 66.7 41.4

22. Unit Capacity Factor (Using DER Net) 66.7 41.4

23. Unit Forced Outage Rate 4.5 8.8 38.0

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

25. IfShut Down At End Of Report Period. Estimated Date of Startup:

26. Units ln Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCJA L OP ERATION (o/77)

17 OPERATING DATA REPORT DOCKET NO.

DATE 5 2 79 COMPLETED BY Don Green TELEPHONE ~L229-6846 OPERATING STATUS Notes I. Unit Name:

2. Reporting Period:

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross AIWe): 1152

5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Gross MWe):

1098.4

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

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

10. Reasons For Restrictions. If Any:

This Month Yr.-to-Date Cumulative 365'28

12. Number Of Hours Reactor Was Critical 646 22 2781.07 19499.36

13. Reactor Reserve Shutdown Hours 25.15 . 11501.86

14. Hours Generator On. Line 646.22 2770.40 '18838.26" '

15. Unit Reserve Shutdown Hours 0 0

16. Gross Thermal Energy Generated (MWH) 8 386,684 51,838 472

17. Gross Electrical Energy Generated (MWH) 687,850 2,857,580 17,171,368

18. Net Electrical Energy Generated (MWH) 669,399 2,784,696 16,674,860

19. Unit Service Factor 89.9 96.2 51.6

20. Unit Availability Factor 96.2 51.6

21. Unit Capacity Factor (Using MDC Net) 90.8 42.9

22. Unit Capacity Factor (Using DER Net) 87.4 90.8 42.9

23. Unit Forced Outage Rate 41.

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

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY COMMERCIALOPERATION

18 OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED BY TELEPHONE 2QQ;~846 OPERATING STATUS Browns Per 3 Notes

1. Unit Name:

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross ilIWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): 1 9 7 Maximum De p endable Ca p acit y(Net MWe: )

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

9. Power Level To Which Restricted, IfAny (Net MWe): N A

10. Reasons For Restrictions, If Any:

This Month Yr:to.Date Cumulative

'4

12. Number Of Hours Reactor Was Critical 719 2 865.15 15 956.35

13. Reactor Reserve Shutdown Hours 0 13.85 1119.26

14. Hours Generator On-Line 2,857.37 ~

15,

15. Unit Reserve Shutdown floors 0 0 0

16. Gross Thermal Energy Generated (MWH) 8,835, I 7. Gross Electrical Energy Generated (MWH) 734 410 2 958 630 '14 726,130

18. Net Electrical Energy Generated (MWH) 716 288 . ' 886 590 14 291,778

19. Unit Service Factor 82.1

20. Unit Availability Factor 2.1

21. Unit Capacity Factor (Using MDC Net) ~ 1 70.7

22. Unit Capacity Factor (Using DER Net) 94.1 70.7

23. Unit Forced Outage Rate 0 .8 8.0

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

ta e Se tember 1 1979

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COMMERCIALOPERATION (o/77)

DOCKET NO.

UNIT SIIUTDOWNS AND POiUER REDUCTIONS

~ I COMPLETED BY REPORT MONTII I

rl C CO V Licensee Q~

~m C Cause Ec Corrective o 4 0 O Nir. Date m 5cc Event Action to PJ

~V CA C Report 0 O Prevent Recurrence CJ CI 74 79 04 02 F 5.58 Moisture separator fH level caused sto valve closure 75 79 04 06 Derated for turbine C.V. tests 76 79 04 14 Derated for "B" condensate booster um maintenance 77 79 04 16 Derated for "A" reactor feedwater um maintenance 78 79 04 28 Derated for turbine C.V. tests 79 04 29 26.77 Turbine sto valve closure OI6I)

F: Forced Reason: hiethod: Exhibit G - Instructions S: Scheduled A.Equipment Failure (Explain) I -hlanual for Preparation of Data B.hlaintenance or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-

- D-Regulatory Restrictiun 4.Other (Explain)

E-Operator Training & License Examination F-Administrative 5 G-Operalloltal Error (Explain) Exhibit I - Same Source Il Other (Explain)

DOCKET NO. 50-260 UNITSHUTDOWNS AND POWER REDUCTIONS Browns Ferr 2 UNIT NAhIE DATE COhIPLETED BY Don Green

'ELEPHONE f4 ~ c ~

~Vl~

~ = 5 Licensee oCQ0 o Cause Ec Corrective No. Date ~ fY  ; Event Action to hK u~ C Report 4 wG E Q

~ Prevent Recurrence

~ Ch CI . ~

85 79 04 26 Derated for scram timin control rods 86 79 04 27 ,72. 78 Refuelin I

F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) I.hlanual for Preparation oi'ata B.hiaintenancc or Test 2.hlanual Scram. Entry Sheets for l.ic<<nsee C.Refueling 3.Automatic Scram. Event Report (LER) File INUREG.

~

D Regulatory Restriction . 4-Other (Explain) OI6 I )

E.Operator Training'iccnsc Examination F-Adminis t ra t ive G.Operat tonal Lrror (Explam) Exhibit I - Satnc Source I I Other (Explain)

DOCKET NO 50-296 VNlTSl(UTDOlVNS AND POWER REDUCTIONS COMPLETED BY C ~

r>

P Licensee C<4J Cause &, Corrective N<i. Date EA

Event

~0n D

~

O U Q Action to u

Report 0 cn G E Q

~ Prevent Recurrence 86 79 04 01 Derated for EHC maintenance (leaks e) 87 79 04 07 Derated for turbine C.V. tests 88 79 04 07 Derated for STI 162 (Load Following Test) 89 79 04 08 Debated for STI 162 (Load Following Test 90 79 04 12 Derated for control rod pattern ad ustment 91 79 04 20 Derated for control rod sequence exchan e from "B" to "A" 92 79 04 24 Derated for control rod pattern ad ustment 93 79 04 28 Derated due to high vibration on "C" Rx feed um 3 4 F: Furced Reason: Method: Exlubtt C - lnstructtons S: Scheduled A-Equipmcnt Failure (Explain) I -hlanual . for Preparation of Data B-hlaintenance or Test 2 hlanual Scram. Entry Sheets for Licensee C-Refueling 3.Autotnatic Scram. Event Report (LER) File(NUREG-D.Regulatory Restriction 4 Other (Explain) OI6I )

E.Operator Training & Liccnsc Examination F-Administrative 5 G-Operational Error Exhibit l ~ Same Source (Explain)'i-Other (Explain)

BROWNS FERRY NUCLEAR PLANT UNIT Common CSSC E UIPMENT MECllANICAL MAINTEKKNCE

SUMMARY

For the Month of APril 19 79 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4/5 Ventilatio Board and Dirty Filter None Operation None Replaced filters Spreading Room Supply Fans 4/17 Rx. Bldg. Discharge Valves in None Unknown None Turned valves and Closed check valve backward replaced Cooling from equip.

Water drain sump pump 4/27 RllRSW A-1 RHRSW Packing leak None Operation None Tightened packing pump 4/27 RllRSW C-3 RHRSW Packing leak None Operation None Tightened packing pump 4/27 RHRSW D-3 RHRSW Packing leak None Operation None Tightened packing pump

BRONNB FERRY NUCLEAR PLANT UNIT 1 CSSC E UIPMENT MECHANICAL MAINTENANCE SUGARY 19 79 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR IfALFUNCTION MALFUNCTION RECURRENCE 4/1 HPCI FCV.73-35 Shaf t bent an bearings bad None Operation None Replaced shifter shaf and bearings 4/1 1-PCV-25-2 Valve dirty Non'e Normal wear None Disassembled an and regulator cleaned valve, set not set pro- regulator perly 4/9 CRD 85-50-19 Valve leaking None Operation None Lengthened stem and through stopped leak

BROWNS FERRY NUCLEAR PIANT UNIT 2 CSSC E UIPMENT MECHANICAL MAINTENANCE

SUMMARY

EFFECT ON SAFE ACTION TAKEN DATE SYSTElf COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4/3 Ventila- '2A. Reactor Loose belts None Operation None Tightened belts tion bldg. exhaust fans 4/10 HPCI U-2 HPCI Leaking Unto None Operation None Tightened union Booster Pump

BROWNS FERRY NUCLEAR PLANT UNIT 3 CSSC E UIPMENT MECHANICAL MAINTENANCE

SUMMARY

EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4/l "A" CRD Dirty Filter discharge None Operation None Changed filter filter 4/4 RHR - SM 'Pac4ng leak. None Operation None Ad)usted packin pump D-3 4/4 RHR SM Packing Leak None Operation None Ad5usted packing Pump C-3

BROlPilS PERRY BUCLEAP, PL62IT M)ZT CSSC E UIBfENT ELECTRICAL MAINTENANCE SDBfARY For the tfonth of Page 1 of 3 E ect on a e Action Taken System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction. Malfunction Recurrence 3>>30-79 HPCI HPCI drain Scheduled N/A LS73-5 corroded Level not control- Replaced switches.

level maintenance ling properly Checked OK.

switches TR 112088 LS 73-5 4-3-79 Fire pro- Class "A" Scheduled N/A (1). Panel 9-2, Alarm would not Replaced relay in tection supervised maintenance A spreader rm. come in panel 25-323 to detector (R-3, R-6 zone light annunciator in alarm cir- A heat) would panel 9-2. Tested cuits and (2) Above would OK. LER 259/797 circuits from not light from TR 130004 panel to con- pnl 25-323 trol room 4-12-79 tandby uD'( diesel Relay operat- N/A Bad relay Improper operation Replaced relay and iesel gen- generator- e ting spurious- (discovered while times in accordance erator sys. time delay ly performing EMI 3) with EfI 15 and relay (SFD2) SZ 4.9.A.l.d.

Tested OK. TR 13 6 4-17-79 ir con- "B" control Chiller trip- N/A Dirty oil filter Chiller not operat- Replaced oil filter, itioning bay chiller ping on low ing properly checked oil pressure oil pressure normal. Tested OK.

TR 129544

ERONNE PERRY 'NUCLEAR PLANT UUZT 1 ELECTRICAL MAINTENANCE SV11MARY Page 2 of 3 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 4-18-79 entilation Diesel genera (1 ) IIAII N/A (1) "A" exhaust (1) and (2) dampers (1) Replaced motor.

tor building exhaust fan fan damper motor locked in open posi-exhaust fans damper in "A" defective dampers room will not (1) A and close

{2) B (2) IIBII (2) "C" room (2) Replaced acx exhaust fan damper had iary contact.

damper in "C" faulty auxil- Tested OK. TR 117926 room will not iary contact close 4-22-79 Emergency "D" EECW pump Circuit break- N/A Faulty circuit Strainer motor will Replaced circuit.

equipment discharge er faulty breaker not run Breaker tested OK.

cooling strainer TR 128083 water motor - cir-cuit breaker 4-24-79 Battery U-1 250-V mai SI 4.9.A.2.C N/A Biannual surveil- Found humming in Removed metal shaving boards battery lance ACl relay due to from ACl relay. SI metal shaving . completed. TR ll 4-26-79 Air condi- 1-B, control Tripping on N/A Reservoir and Chiller tripping on Cleaned reservoir and tioning bay chiller low oil oil p'ump jet low oil pressure oil pump )et, pressure dirty changed oil'ilter and freon filter.

Tested OK. TR 127109

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ERONNS PERRY NUCLEAR PLRNY UNYY 2 CSSC E UIPMENT ELECTRICAL MAINTENANCE SALARY

~ 5 Page 2 of 2 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 4-23-79 Ventilat- U-'2, 250-V Motor trips N/A Overload set at Tripping out at Reset overload to ing battery room out 100% full load 115(.. Tested OK.'R supply fan 2A 126913 motor 4-29-79 Neutron "E" IRMP Defective .:=. N/A Bad.cable IRM will not operat Installed new cable monitor- cable cable and connector per ing EMI 5. Checked OK.

TR's 115425 and 105406

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EROVRE FERRY RUCLEAR PLARY URLY ELECTRICAL MAINTENANCE S CHARY For the Month of April . 19 79 Page 2 of 2 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 4-20-79 Air condi 4160-V shut- "Air condition N/A Freon charge low Alarm will not Added freon.

tioning down bd. er abnormal" clear Operation room chiller alarm tested'ormal.

TR 128846 (alarm clear) 4-24-79 Raw ser- 3A raw ser- .". Motor trip- N/A Motor leads Motor trip Replaced leads, vice vice water ping out burned meggered motor.

water pump motor Checked OK.

TR 128830

BRONNR PRRRY NUCLEAR PLRNT UNIT I & 3 INSTRUMENT MAINTENANCE SUQfARY For the Month of April 19 79 CSSC Equipment ect on Sa e Action Taken Date System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence Unit I Primary PdT-64-138 Calibration None Zero drift Redundant indicators New design trans-Contain-'ent do not agree mitters to be installed Unit 3 4-23 Radwaste Fq-77-16 Calibrate Nqne Zero drift Indi:cated"'%low with None pump off 4-23 Contain- H2H-76-38 Replace None Sensor failure Indicated 5% H2, lab New system to be ent sample was aero installed nerting

34 OUTAGE SECTION MONTHLY REPORT Much of April was spent toward planning and work preparations for the Unit 2, Cycle 3 outage which began with shutdown at 2213 hours on April 27, 1979. The outage is scheduled for 42 days.

Since no significant invessel work or ma)or modifications requiring critical path time are scheduled for the Unit 2, Cycle 3 outage, it should be the shortest scheduled refueling outage to date.

Training in preparation for the refueling outage and all the mandatory prefab work was completed in April for gobs scheduled,:during the outage.

Some major efforts were expended on non-outage work such as security and cooling tower modifications.

In conjunction with the Unit 2 effort, the planning and prefabrication work for the upcoming outages such as the torus and LPCI modifications were underway.

To date, the Unit 2, Cycle 3 outage is progressing very well, and at this time it is slightly ahead of schedule.