ML18024A767

Monthly Operating Rept for Mar 1979

ML18024A767
Person / Time
Site:	Browns Ferry
Issue date:	04/09/1979
From:	Dewease J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A765	List: ML18024A764 ML18024A767
References
NUDOCS 7904130181
Download: ML18024A767 (30)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT

.MONTHLY OPERATING REPORT March 1, 1979

March 31, 1979 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted By:

ant Superintendent

TABLE OF CONTENTS Operations Summary

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Refueling Enformation Significant Operational Events

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Average Daily Unit Power Level Operating Data Reports

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Unit Shutdowns and Power Reductions.

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Plant Maintenance

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erations Summa The following summary describes the significant operational activities during the reporting period.

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

There were three reportable occurrences reported to the NRC during the month of March.

Two supplemental reports and one revision were also made.

Unit 1 The unit scrammed three times during the month.

The unit was manually scrammed on March 12 to repair a leak on "B" feedpump discharge piping.

On March 28, the reactor scrammed due to false high pressure and low water level signals generated when concrete dislodged during a floor drilling operation struck a local panel.

The reactor scrammed on March 29 due to stop valve closure,

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caused by moisture separator high level and turbine trip.

Unit 2 The unit scrammed twice during the month.

The unit scrammed on March 18 and 25 from APRM high flux caused by a malfunction of the "A" pressure regulator in the EHC system resulting in a pressure transient and high flux.

Unit 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 Shell at water line Feedwater nozzle Closure studs

.00401

.18415

.17244

= Unit 2

.00268

.11750

.10007 Unit 3 0.00243 0.09513 0.07339 Note:

This accumulated monthly information tion section 6.6.A.17.b(3) reporting satisfies technical specifica-requirements.

Common S stems Approximately 4.61E+5 gallons of waste liquid were discharged containing 4.06E-1 curies of activity.

Cooling Towers 2, 3, 4, and 5 (until Mi rch 19) were operational this month for two lift pump operations.

Work on Towers 1, 6, and 5 (beginning March 19) was continued.

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' (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel.

Unit 1 (Cnntdnned)

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 840 assemblies.

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

Unit 2 Unit 2 is scheduled for its second refueling beginning on April 27, 1979, with a 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 sub-mitted 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 267 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 spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Unit '3 Unit 3 is scheduled for its next refuel outage beginning on August 30, 1979, with a scheduled restart date of December 8, 1979.

This refueling will

Unit 3 (Continued) 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 erational Events Unit 1 Date Time Event 3/1/79 0001 1130 Reactor thermal power at 85%, sequence "A" with PCIOMR in progress Reactor thermal power at 98%, rod limited 3/2 2310 Reduced thermal power from 98% to 80% for turbine CV tests and SI's 3/3 0050 0700 Turbine CV tests and SI's completed, commenced po~er ascension Reactor thermal power at 99%, rod limited 3/9 1240 2000 2100 Reduced thermal power from 99X to 90% for removal of "C" string high pressure FV heaters from service for maintenance (leakage problems)

'"C" string high pressure heaters returned to service, commenced power ascension Commenced PCIOMR from 95% thermal power 3/10

- 0835 3/11 0330 0735 0800 2300 Reactor thermal power at 99X, steady state Reduced thermal power from 99% to 65% for CV tests and SI s CV tests and SI's completed, commenced power ascension Commenced PCIOMR from 85% thermal power Reactor thermal power at 99%, steady state 3/12 1933 2211 Commenced reducing thermal power from 99% to shutdown.

to repair leak in piping on discharge of "B" reactor feedpump Reactor scram no.

107 (manual) from 35%,thermal power to accommodate FV piping maintenance 3/17 0040 0105 1228 1248 Commenced rod withdrawal Reactor critical no.

123 Roll'ed T/G Synchronized generator, commenced power ascension in control rod sequence "A"

3/18 3/19 3/24 0930 1430 2215 2250 Commenced PCIOMR from 75X thermal power Reactor thermal power at 98%, steady state Reduced thermal power from 98% to 90% for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced PCIOMR

Si nificant erational Events Unit 1 Date Time Event 3/25 3/27 a5ao 1221 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 90% for removal of "A" string high pressure heaters from service for maintenance

('lange leakage) 3/28

. 0535 0605 0930 1852 Maintenance to "A" string high pressure heaters completed and heaters placed in service Commenced power ascension from 90% thermal power Reactor thermal power at 99% steady state

'eactor scram@~

no.

108 due to false low reactor water level and high reactor pressure signals 3/29 3/3O 3/31 0445 1020'400

. 1714 1920 2020 2238 2000 2123 2400 Commenced rod withdrawal Reactor critical no.

124 Synchronized generator commenced power ascension Reactor scram<

~ no. 109'rom 60% thermal power due to stop valve closure Commenced rod withdrawal Reactor critical no. 125 Synchronized generator, commenced power ascension Commenced PCIOIR from 40% thermal power sequence "B"

Reactor thermal power at 66%, holding for control rod pattern adjustment Reactor thermal power at 66% holding for control rod pattern adjustment

7 Si nificant Operational Events Unit 2 Date Time Event 3/1/79.

0001 3/2 2310 Reactor thermal power at 97%, rod limited Reduced thermal power from 97% to 85X for turbine CV

tests, SI's and condensate demineralizer backwash and precoat (reduction due to a bad valve on "F" deminera1.izer) 3/3 0020 0700 Turbine CV tests, SI's and condensate demineralizer backwash and precoat completed, commenced power ascens"on Reactor thermal power at 97%, rod limited 3/5 2346'educed thermal power from 97% to 85% for condensate demineralizer backwash and precoat 3/6 0200 0225 Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal powex't 96%, xod limited 3/7 0010 0215 0240 Reduced thermaI power from 96X to 85% fox condensate demineralizers backwash and pxecoat Condensate demineralizers backwash and precoat completed, commenced power ascension Reactor thermal power at 95X, rod limited 3/11 3/12 0001 0336'415 06aa.

113Q 2300.

Reduced thermal power fxom 95% to 70% for turbine CV tests and SI's Turbine CV tests and SZ"s completed, commenced power ascension'eactor thermal power at 90X, holding for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 95%, rod limited Reactor thermal power at 94%, rod limited 3/15 3/16 0001 0125 0415 2045 Reduced thermal power from 94% to 85X for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 93%,,rod limited Reduced thermal power from 93% to 75% for turbine CV tests and SI's

Si nificant Operational Events Date Time Unit 2 Event 3/17 0030 0115 1620 1720 Turbine CV tests and SI's completed, reduced thermal power from 75% to 44% for control rod sequence ex-c'hange from "A" to "B" Control rod sequence exchange established holding at 44X thermal power for both recirculation pumps MG set brush replacement Both xecirculation pumps MG set brush replacement, completed, commenced power ascension Commenced PCIOMR from 55% thermal power 3/18 3/19'033' 1400; 1900 2230.

2258 1430'eactor scram no.

74 from 65% thermal power on APRM high flux (pressure regulator problem)

Commenced rod withdrawal Reactor critical no.

86'olled T/G Synchronized generator, commenced power ascension Reduced thermal power from'65% to.51% for control rod pattern adjustment Control rod pattern established, commenced PCIOMR from 51%. thermal power 3/20 221Q'educed thermal power'rom 88% to 55X for control xod

'pattern ad/ustment 3/22, 233Q:

\\

3/21" 0030'ontxol xod pattern adjustment completed, commenced "

power ascension'eactor thermal power at 97%, rod limited 3/24 3/25 003Q-0130'336 1635 005Q 0450.

0815'140 1201 Reduced thermal power from 97X'o 80% fox turbine CV tests and SI'~s Turbine CV tests. and SI~s completed, commenced power ascension'ommenced'CIOMR from. 95X'hermal power Reactor thermal power at 98%', rod limited Reactor scram no. 75'rom 98% thermal power on APRM high flux due to failure of the "A" pressure regulator (pressure spike}.

Commenced rod withdrawal Reactor critical no.

87 Rolled T/G Synchronize generator, commenced power ascension

Si nificant erational Events Unit 2 Date Time Event 3/26 0700 2230 Commenced PCIOKt from 82% thermal power Reactor thermal power at 98%, rod limited 3/30 2200 2250 2300 Reduced thermal power from 98% to 82% to achieve all rods out Qf/D last 8 peripheral rods full out)

All-control rods fullywithdrawn, commenced power ascension Commenced PCIO~iK from 88% thermal power 3/31 2400 Reactor thermal power at 96%,

PCIOHR in progress

10 Si nificant Operational Events Date Time Unit 3 Event 3/1/79 0001 3/2 2310 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 90% for turbine CV tests and SI's 3/3 0130 0700 Turbine CV tests and SI's completed, commenced power ascension Reactor. thermal power at 99%, steady state 3/5 0205 0535 1637 1930 2230

'coop tube on both recirculation pumps locked reducing thermal power from 99X to 82%

Both recirculation pumps scoop tube reset, commenced power ascension Reduced thermal power from 99X to 96%,

CPR limited Commenced PCIOMR from 96% thermal power Reactor thermal power at 99%, steady state 3/9.

. 1905 2110 Reduced thermal power from 99% to 50% for turbine CV

tests, SI's and control rod sequence exchange from "B" to "A"

'urbine CV tests,and SI's completed, holding for control rod sequence exchange 3/10 0130 1230 Control rod sequence exchange completed, commenced power ascension Commenced PCIOMR from 70% thermal power 3/12 1500 Reactor thermal power at 99X, steady state 3/16 3/18 0215

'602 0645 1050 1335 1915 2030 0630 Reduced thermal power from 99% to 70% for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension

. Commenced PCIOMR from 95X thermal power Reactor thermal power at 99%, 'steady state Reduced thermal power from 99% to 65% for maintenance to'MSIV (FCV-1-52) solenoid (replaced coil)

Maintenance to MSIV (FCV-1-52) completed, commenced power ascension Commenced PCIOMR from 75% thermal power Reactor thermal power at 99%, steady state

Si nificant Operational Events Uait 3 Date Time Event 3/21 1100 Reduced thermal power from 99X to 75% due to both recirculation pumps run back (ground in control loop in Auxiliary Instrument Room) 3/22 0305 1245 Commenced power ascension Reduced thermal power from 97% to 75% for removal of "C" reactor feedpump for maintenance (controls problem) 3/23 1312 2245'aintenance to "C" reactor feedpump completed and placed in service, commenced power ascension Reduced thermal power from 94% to 64% for control rod pattern adjustment and turbine CV tests and SI's 3/24 0126 023Q Control rod pattern established, turbine CV tests and SI's completed, commenced power ascension Commenced PCIOMR from 75X thermal power 3/25 0.732 Reactor thermal power at 99%, steady state.

3/30 1955 240Q.

2200 2300

--- -3/312005--" -

Reduced thermal power from"'99X'o 70% for STI 162 goad following test Phase I}

Commenced power ascension.

Reactor thermal power at 99?;, steady state Reduced thermal power from 99X to 70X for STI 162 goad following)

Reactor thermal power at,70/', holding Maintenance error.

a)

Equipment malfunction (2$

12 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

UNIT DATE COMPLETED BY T ~ Tholn TELEpHONF 205-729-6846 "MONTH March 1979 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

DAY AVERAGE DAILYPOWER LEVEL (MWe.Net)

'50.

9 10 12 13 14 15 16 1056 1069 1068 1067 1077 1079 1039 1067 950

-12

-12 18 19 20 21 22 23 24 25 26 27 28 29 30 31 795 10143 1063 1069 1068 1070 1066 1068 1071 1023 807 619 721 INSTRUCTIONS On this format, list the average daily unit power level in Mme.Net for each day in the reporting tnonth. Compute to the nearest whole megawatt.

h

. (9/77 )

13 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

Browns Ferry II DATE 4

2 79 COMPLETED SY TELEPHONE 205-729-6846 "MONTH March 1979 DAY AVERAGEDAlLYPOWER LEVEL (MWe Net) 1055 DAY AVERAGE DAILYPOWER LEVEL (MWe.Net) 492 17 10

]2 13 14 15 16 1046 1036 1027 1025 1033 1031 1023 980 1019 1015 1001 1000 1021 19 o0 24 25 26 27 28 29 30 31 784 709 949 1064 1044 320 937 1070 1072 1073 1060 981 INSTRUCTIONS On this format. list the average daily unit power level in Mme Net for each day in the reporting month. Compute ro the nearest whole megawatt.

(<)/77 1

14 AVERAGE,DAILYUNITPOWER LEVEL'OCKET NO.

DATE 4/2/79 COMPLETED BY, TELEPHONE 205-729-6846

'MONTH DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

'I 1071 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 910 17 4

5 Ig 6

10 12 13 14 IS 16 1065 1075 1C62 1070 1059.

070 IS 19 20 21 22

'73 25 26 27 28 29 30 31 1064 1071 1071 943

. 895 899 911 1065 1065 1072 1073 1068 1012 965 INSTRUCTIONS

/

On this format, list the average daily unit power level in hliiVe-Valet for each day in the reporting month. Compute to the nearest whole megawatt.

(9/771

15 OPERATING DATAREPORT OPERATiNG STATUS DOCKET NO.

DATE 4

E TB COMFLETED BY MO~~ren TELEPHONE ~(~~6846 Notes

l. Unit Name Browns F

2. Reporti'ng Period:

Ha<eh 1979

3. L'icensed Thermal Power (MWt):

4. Namephte Rating (Gross LIIWe):

1152

5. Design Electrical Rating (Net MWe):

10 5

6. Maximum Dependable Capacity (Gross MWe):

i um De endable Ca acit Net hIWe:

3.098. 4 1065 7 4Iaxm p

p y(

)

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

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

10. Reasons For Restrictions, IfAny N A N/A

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvaihbilityFactor

21. Unit Capacity Factor (Using MDC iVet)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months This hlonth Yr.-to.Date 744 2160 1593.33 626.53 142.84 117.

7 608.85 1507.07 0

0 e

4,149,051 1,833,996 621 650 1 383 780 69.8 81.8 76.4 58.5 58.5 76.4 10.7 18.2 (Type, Date. and Duration of Each):

Cumulative 40'98 21 824.92 4541.97 21198.41 0

54 921 723 18 201 780 1..8

~

40.5 40.5

38. 7

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

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

Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION

(~l77)

16 I

OPERATING STATUS OPERATING DATAREPORT DOCKET NO.

D~TE ~a~

>9 COMPLETED BY MQILZzXRStl ELEPHONE ~~o-6846 Notes

1. Unit Name:

2. Reportfng Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Deoendable Capacity (Gross MWe):

We 1098.4 1065

7. Maximum Dependable Capacity (Net M

).

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. IfAny:

v

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 hlonths (Type, A ril 27'979 744 728.13 15.87 707,700 689,831 96.8 96.8 87.1 87.1 3.2 2160 2134.85 25.15 212

.18 0

6,322,154 2,169,730 2,115 297 98.3 98.3 92.0 92.0 1.7 Date.and Duration of Each):

This Month Yr.-to-Date Cumulative 35'809 18 853.14

~

11,501.86 0

49,773,942 16 483 518 16 005 461 5'0. 8 50..8 42.0 1,

~

~

a

~

P

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 (9/77)

~>

17 OPERATIiVG DATAREPORT DOCKET NO.

DATE

~~

COilIPLETED BY Znn $XRBD.

TELEPHONE ZQ-Lg9=6846 OPERATING STATUS Unit Name.

Browns Fer TXI

p od.

March 1979.

3. I.icensed Thermal Power (ilIWt):

4. iVameplate Rating (Gross ibIWe):

5. Design Electrical Rating (Net MWe):.

1065

6. Maximum Dependable Capacity (Gross MWe)'.

Maximum Dependable Capacity (Net MWe):

1098.4 1065 Notes

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

v

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

10. Reasons For Restrictions. IfAny:

4 ~

N/A N/A This illonth

'I 744 Yr.-to-Date 2 160

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Lme

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months 2146. 15 13.85 744 0

2138.37 744 0

0 6 630 345 2 351 609 224 220" 2 170 302 756 292 99.0 00 99.0 100 94.3 5,4 94.3 95.4 (Type, Date. and Duration of Each):

Cumulative 18,264 15,23 1119.26, 14868.35

~ 0 42,781,727 13 991 720 13 575,490

'81.4 81.4 69.8 9 ~

8.3

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

26. Units In Test Status IPrior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COMilIERCIALOPERATION (o/77)

UNITSIIUTDOlYNSANDPOKER REDUCTIONS REPOR T MONflI >farch DOCKET NO.

UNITNAhlE DAfE COhlPLETED IIY TELEI'IlONE 50-259 C

Browns Ferr I 4

2 79 Don Green 205-2 -6 N(I.

Dale Q

aK A~

P A

J

~

f(

o=~

U <

~ I/I Liccnscc Event Report sr

~J O

Q O

2 ~

O

'I Cause A Corrective Action to Prevent Rc<<urrcn<<e 70 71 72 73 790311 790312 790328 790329 110. 62 19.13 5.40 A

2 H

3 A

3 Derated for turbine control valve test and SI's Leak in piping on discharge of "B" reactor feed um False low reactor water level si nal Moisture separator high water level caused a turbine sto valve closure I

F: Forced S: Schcduicd

(>>/>>)

Reason:

A.EI)uipment Failure (Explain)

B h(aintcnance or Test C-Rcfueliog

,D Regulatory Restriction E Operator Training', Liccosc Examination F Administrative G Operational Error (Explain)

I I Other (Explain) 3 hkethod:

I -hla>>ual 2.hla>>IIal Sera>>i.

3-Aulootatic Sera>>I.

4.Other (Lxplain) 4 Exhibit G - lnstroclions for Preparation of Data LollyShccts lof I.I<<c>>scc Event Rcport (I.L'R) File (NURL'G-OI6I) 5 Exhibit I - Sante Source

l UNITSIIUTDO'lUNS AND POWER REDUCTIONS DOCKET NO.

50 260 COhIPLETEI) IIY ~~ea No.

Date rr 5

~

IA 1J gr<

g J J

Q

~ C/l Licensee Event Report 4 C ~

Q El

~0 cn'Cr

~J~

()

4J Q

Zl C ~

O Cause & Curler.tive Action lo Prevent Recurrence 80 81 82 83 84 790311 790317 790318 790320 790325 12.42 11.18 B

H H

A Derated for turbine 'control valve test and SI's Derated for control rod sequdnce exchan e from "A" to "B" APRM high flux due to pressure re ulator roblems Derated for control rod pattern im'rovement APRH high flux due to pressure re 'ulator roblems F: Forced S: Scheduled I>I77)

Reason:

A-Equipment Failure (Explain)

I).hiaintenance or Test C.Rel'ueling D-Regulatory Restriction E.Operator Training k. Uccnsc Examination F.Administrative G.Operational Lrror (Explain)

I I.Other (Explain) 3 hlethod:

I -hlanual 2-hlanual Scram.

3.Automatic Sera>n.

4-Other (Explain)

Exlribit G - Instructions fol I rcpafalloll of Data Entry Sheets I'or I.iccnsee L'vent Repor<nc Source

UNITSIIUTDQ'LVNS AND POhlFR REDUCTIONS REPORT IIIONTII~laxch DOC)'ET No.

UNITNAhIE COhIPLETED IIY NII.

Dale I I 5

Vl

~lJ tO, u

U< a

~ M Licenscc Event Report ¹ 4l Cla w'r O

C Cause A. Corrective Action lo Prevent I<ccurrcocc 81 790309 82 790316 82 790316 83 790321

)I'4 790330 85 790331 B

B B

H Derated for turbine control valve test and SI's and control rod se uence exchan e from'"B" to "A" Dere ted for turbine control valve test and SI's Derated for maintenance to MSIV (FCV-1-52 solenoid Derated due to runback of both

'recirc um s Derated 'for STI 162 (load followin Derated for STI 162 (load followin )

F: Forced S: Scheduled

(')/77)

Reason:

A-Equipment Failure (Explain)

II-Maintenance or Test C.Refueling D.Ri!guiatory Restriction E.Operator Trainiog 8; Ucensc Examination F-Administrative G-Operational Error (Explain) ll Other (Explain)

Method:

I -htaoual 2-hIannal Scraln.

3-Automatic Scram.

4-Other (Explain}

Exhibit G - instructions fof Prcprlrsl lion ol Data Entry Sheets I'or l.iccoscc Event ltiport (I.III<}File (NURI!G.

OI6 I I Exhibit I - Salnc Source

CSSC E UIPMENT RROHHE PERRY HUOLEAR PLAHT UHLT MECILQlICAL MAINTENANCE SU>MARX For.the Month of March 19 79 3/24 SYSTEM Fuel Pool Cooling COMPONENT FPC Pumps A&B NATURE OF MAINTENANCE Packing Leaks EFFECT ON SAFE OPERATION OF 1llE REACTOR None CAUSE OF MALFUNCTION Operation RESULTS OF MALFUNCTION None I

ACTION TAKEN TO PRECLUDE RECURRENCE Ad)usted packing 3/15 CRD CRD accumu-lator 50-11 Bad accumula tor t

None Operation None Replaced accumulato>

CSSC E UIPHENT MOWNS FERRY NUCLEAR PLANT UNIT 2

MEQIANXCALMAINTENANCE SUS&KRY For the Month of March 19 79

~ j DATE 3/13 SYSTEM HPCI COMPONENT 73-16 Valve Packing leak None EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION Operation RESULTS OF MALFUNCTION None ACTION TAKEN TO PRECLUDE RECURRENCE Tightened packing gland 3/23 CRD Discharge Dirty filter filter "A" None Operation None Replaced dirty filte

BRGNNB'PERRY NUCLEAR PLANT UNXT B

MECHANICAL tfAINTENANCE SUtfMARY For,the Month of March 1979 DATE SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE

. 3/2 "B" CRD dis-charge filter Dirty filter None Operation None Replaced filter

. 3/11 RHR gCV 3-74-552C Leak at bush-ing None Operation None Tightened Pushin 3/13 CRD CRD pump suction filte Dirty filter

, None Operation None Replaced filters 3/4 Fuel Pool Cooling "A" FPC pump Packing leak None Operation None Ad)usted packing

CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT Common MECHANICAL hfAINTENANCE

SUMMARY

I For the Booth of tterch 19~

DATE SYSTElf COMPONENT NATURE OP MAINTENANCE EFPECT ON SAPE OPERATION OP

-THE REACTOR CAUSE OP hfALPUNCTION RESULTS OF hfALPUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 3/19 RHRSW RHRSW pumps A-l, C-3, D-,3 Packing gland leak None Operation None Ad5usted packing

CSSC E UIPMENT BROlUlR PERRY ilUCLEiU'LARYUllLY~

ELECTRICAL HAINTENANCE SlRMARY Por the Honth of Harch 19~

Date System Component Nature of Haintenance ect on a e Operation of The Reactor Cau e of Halfunction Results of Halfunction Action Taken To=Preclude Recurrence 3/2 High Pres-sure Pire Protection 1-25-315 heat detector pnl.

alarm light Alarm'nopera-tive N/A Loose connection Alarm would not on plug/supply light up to panel lights Tightened connection and tested alarm Light ok.

TR 111515 3/2 High Pres-sure Fire Protection 1-25-303 pre-action sprin-kler system; first out indicating lights for

,zone "X" Indicating light will not light N/A Interlock contac on zone "W" not making up (found during SI per-formance)

Indicating light would not light Replaced zone "W"

'elay and tested zone "X'First out" light o.k.

TR 111519 3/13 Ventilatin lA battery room exhaust fan damper motor Damper inoper-able N/A Control circuit contactors not making up Inoperable damper Adjusted connector and tested ok.

TR".118205 3/26 Pire Pro-tection Smoke and hea detectors SI 4.11.C.1

.5 N/A Four defective detectors found; 1)one with loose connection, 2) one would not

clear,

3) one with short in mounting base,

4) one detector indicating light inoperable

1) Inoperable detec-tor

2) Inoperable detec-tor 3),.Alarm wo'uld not clear 4)

No local alarm indication on detector Replaced four det tors tested ok.

TR 106159

ERONNE FERRY NUCLEAA'LANTUNYT 2

ELECTRICAL MAINTENANCE SEÃhRY For the Honth of March 19 79 D"te System Component Nature of Haintenance ect on a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 3/15 Fuel Pool Cooling Damin.

2LS 78-2A/2B Calibrate fuel pool hi - lo level alarms per EHI 48 N/A Hi level switch out of ad)ust>>

ment Alarms not coming in at proper point Ad)usted hi level switch per EHI 48 Tested and checked ok TR 18593 3/27 Ventilatio 2A-1 drywell Breaker will blower.

480V not close breaker N/A Contacts burned on 52X relay Blower inoperable Cleaned contacts.

Tested operation ok TR 118249

RROliWS PERRT EUOLEAll PLAEIT UtlZT 3

ELECTRXCAL HAXNTENANCE SIMfARY For the Month of March 19 79 Date System Component Nature of Maintenance

~

ect on a c Operation of The Reactor Cause of Malfunction Results of AMalfunction Action Taken To Preclude Recurrence 3/16 Main Steam Outboard MSIV 1-52 "D" line DC coil Coil open and alarm "Battery board breaker tripout" in on battery board 3

N/A Coil burned out and coil wires shorted against conduit nipple when replacing coil on TR 111571 Coil open and alarm in'eplaced coil and tested ok.

TR 111571, 18596 3/30 RBCCM 3A RBCCM pump motor bear-ings Noisy rear bearings N/A Bad bearings Running rough and noisy Replaced rear bear-

.ings Checked ok TR 122744

BRO!AS FERRY NUCLEAR PLANT UNITS 1, 2

& 3 INSTRUMENT HAINTENANCE SUk NARY For the Month of March 19 79 Date Unit 2 System Component Nature of Haintenance t on S

~

ec a

e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 3-2-79 I

Neutron APRH's A,B,C, Monitoring D,E,F Calibration None Peaking (R)'ac-.:

Scram setting at tor ad5.

115% instead of 120K None 24 7-.9 R-adiation Rlf-90-250 Honitorin Unit 2 Calibration None Iodine Channel Drift Low source check res onse None

$-1-79 CRD 3-1-79 EEL 79 Radiation Monitor-- 79 Neutron onitorin 79 eutron fonitorin Unit 3 3-4-79 Radwaste 3"8-79 CIC 3-19-79 1RSW Pds-85-63 PIS-67-1 1-90-140 IRM E 4PRM flow bias Q-.77-69 16 T-71-1A, lB S-23-4 Replace Calibrate Replace Repair Calibrate Calibrate Calibrate Calibrate None None None

one, one one one one Needed compound gage Indicates zero DP when actually a vacuum Meek detector Blown fuse Zero drift Periodically spiked causing refuel floor isolation No.indication Disagreement in in-dicated core flow Zero shift Indicated flow with um s off Instrument drift Redundant indicators did not a ree Instrument drift Did not alarm with low header ressure Instrument drift Low pressure'ndica-tion None None None None None None None None 3-28-79 od block onitor RH/RBM re-order Repair one Faulty amplifier No:.indication None