ML18024A594

Monthly Oper Rept for Nov 1978

ML18024A594
Person / Time
Site:	Browns Ferry
Issue date:	12/02/1978
From:	Dewease J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A593	List: ML18024A592 ML18024A594
References
NUDOCS 7812190162
Download: ML18024A594 (32)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT November 1, 1978 November 30, 1978 DOCKET NUMBERS 50-259, 50>>260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted by ant uperintendent V 818 190 lpga

TABLE OF CONTENTS Operations Summary . ~ ~ ~ l Operational Data . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 Maintenance ~ ~ ~ 3 Refueling Information ~ ~ ~ 3 Significant Operational Events ~ ~ ~

Average Daily Unit Power Level . ~ ~ ~ 9 Operating Data Reports ~ ~ ~ ~ ~ ~ ~ o l2 Unit Shutdowns and Power Reductions. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ l5 Plant Maintenance Summary. o ~ o lg Unit 3 Refueling Outage Summary. . . . . . . . . . . . . . . . 27 Unit l Refueling Outage Summary. . . . . . . . . . . . . . . . 27

Ooerations Summa The following summary describes the significant operational activities during the reporting period. ln support of this summary, a chronological log of significant events is included in this report and begins on page 5.

There were 7 Reportable Occurrences reported to the NRC during the month of November.

Untt 1 Significant operational events for unit 1 are tabulated by date and time beginning on page 5.

The unit scrammed once during the month of November. On November 26, the reactor was manually scrammed to accommodate the scheduled refueling outage.

Power was administratively limited throughout the month by 60K "B" recirculation pump speed, with "A" loop out of service.

A summary of maintenance work is shown on pages 18 through 26.

Unit 2 Significant operational events for Unit 2 are tabulated by date and time beginning on page 6, The unit did not scram during the month.

A summary of maintenance work is shown on pages 18 through 26.

Unit 3 Significant operational events for Unit 3 are tabulated by date and time beginning on page 7.

Unit 3 was shut down for refueling outage and startup testing until November 25.

Fuel loading was completed on November 9, and rod withdrawal for startup commenced on November 22.

erations Summa (Continued)

Unit 3 (Centdnned)

There were five scrams on the unit during the month. On November 23, the reactor scrammed on APRM high flux, caused by cold water being introduced into the vessel in an attempt to maintain reactor water level. The water level problems were caused by feedwater control problems which occurred due to a power switch in the control cabinets not being returned to "ON" before startup. The reactor scrammed on November 24 due to a false reactor low-low water leve3 signal apparently caused by'personnel bumping these switches in the reactor building. The reactor was- manually scrammed on November 24 when control rods began drifting into the core due to low scram pilot header air pressure. Investigations did not reveal the cause of the low pressure. On November 25 the reactor scrammed on low condenser vacuum which was caused by instabilities in the "A" SJAE. On November 29 the reactor was manually scrammed to correct LPHM connections in-the drywell.

Approximately 1.1E+6 gallons of waste liquid were discharged con-taining approximately 1.5EO curies of activity.

Cooling towers 1 and 6 were operational this month for two lift pump operations. Modifications by the tower vendor were continued on Tower 3 and Tower 2. None of the towers had significant operational problems.

The average daily unit power level for units 1, 2 and 3 is shown on pages 9 through 11.

The operating data reports for all three units are shown on pages 12 through 14.

Unit shutdowns and power reductions for all three units are shown on pages 15 through 17'.

erations Summa (Continued)

Maintenance Major electrical, mechanical, and instrument maintenance activities during the month are described on pages 18 through 26. Refueling outage activities for Unit 3 are summarized on page 27 'efueling outage activities for Unit 1 are summarized on page 27.

Refuelinm information Unit 1'nit 1 began its second refueling on November 26, 1978, with a restart date of January 8 , 1978. 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 in August 1978.

This refueling will load additional 8 X 8R (retrofit) fuel assemblies into the core, replacing presently loaded 7X7 fuel and will involve irstalling a new recirculation pump trip (RPT) system.'here are 764 fuel assemblies in the coze. The spent fuel storage pool presently contains 168 spent 7X7 fuel assemblies and 156 new 8 X 8R fuel assemblies. The present storage capacity of the spent fuel pool is 1080 assemblies. Present planning is to increase that capacity to 3471 assemblies.

Pith present capacity, the refueling later in 1978 would be the last refueling that could be discharged to the spent fuel storage pool without exceeding that capacity and maintaining full coze dischazge n

capability in the pool.

Unit 2 Unit 2 is scheduled for its second refueling beg~~ning on April 22, 1979, with a restart date of July 1, 1979. Resumption of operation on that date will require a change in technical specifications pertaining to the coze thermal

4 Refuelin Enf ormat ion (Continued)

Unit 2 (Continued) limits. Present scheduling is to submit licensing information in support of these changes before the refueling. This refueling will involve replacinm some more 7 X 7 fuel assemblies with 8 X 8R (retrofit) assemblies.

There are 764 fuel assemblies in the core. At the end of November there were 132 discharged cycle 1 7 X 7 fuel assemblies in the spent fuel storage pool. There are presently 36 new 8 X 8 fuel assemblies in the spent fuel storage pool. which. were not loaded. into the core during this cycle. The present storage capacity of the spent fuel pool is 1080 assemblies. Present planning is to increase that capacity to 3471 assemblies. Pith 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.

Undt 3 Unit 3 finished its erst refueling outage on November 25, 1978.-

This refueling involved replacing some of the present 8 X 8 fuel assemblies with 8X8R (retrofit) assemblies, modifying the main steam relief valves to increase simmer margin, and installing a new recirculation pump trip (RPT) system. Unit 3 is scheduled for its next refuel outage beginning on August 30, 1979. This refueling will involve loading additional 8Z8R (retrofit) assemblies into the cora.

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 11/1 nooo Reactor thermal power at 59K, holding for single re-circulation loop operation Seauence A 11/3 2250 Reduced thermal power from 59,. to 53".. for turbine CV tests and SI's 11/4 0045 Turbine CV tests and SI's completed commenced power ascension 0110 Reactor thermal power at 59K, steady state, holding for single recirculation loop operation 11/10 230n Reduced thermal power from 59'". to 53/ for turbine CV tests and SI's 11/11 03n5 Turbine CV tests and SI's completed, commenced power ascension 0510 Reactor thermal power at 59/, steady state, holding for single recirculation loop operation 11/17 2325 Reduced thermal power from 597 to 53'. for turbine CV tests and SI's 11/18 0330 Turbine CV tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 597, holding for single re-circulation pump loop operation 11/24 2350 Reduced thermal power from 59K to 53K for turbine CV tests and SI's 11/25 0135 Turbine CV tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 59Ã, holding for single re-circulation pump loop operation 11/26 0340 Reduced thermal power from 5",7 to 5ni, for scram timing control rods 0515 Scram timing control rods completed, commenced power ascension 0700 Reactor thermal power at 59K, holding for single re-circulation pump loop operation

Si nificant 0 erational Events Unit 1 (Continued)

Date Tine Event 11/26 1525 Commenced reducing thermal power'rom 59%%u to shutdown for refueling outage 2053 Reactor scram no. 102 manual from 35%%u thermal power to accommodate refueling outage 11/30 2400 Unit off for reload 2, cycle 3 refueling outage Unit 2 11/1 0000 Reactor. thermal power at 98%%u steady state Sequence A 11/3 2330 Reduced thermal power from 98%%u to 85%%u. for turbine CV test and SI's 11/4 0200 Turbine CV tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 98%%u steady state 11/10 2350 Reduced thermal power from 9R%%u to 7n%%u for turbine CV tests and SI's 11/11 0210 Turbine CV tests and SI's completed, commenced power ascension 2230 Commenced PCIOHR from 90%%u thermal power 11/12 0700 Reactor thermal power at 98%%u, steady state 11/17 2308 Reduced thermal po~er from 98%%u to 70%%u. for turbine CV tests and SI's P

11/18 0345 Turbine CV tests and SI's completed, commenced power ascension 0700 Commenced PCIOMR from 85%%u thermal power 11/19 0400 Reactor thermal power at 98%%u., steady state 11/25 0130 Reduced thermal power from 98%%u to 9n%%u for turbine CV tests and SI's 040n Turbine CV tests and SI's completed commenced PCIOHR 1600 Reactor thermal power at 98I.; steady state 11/30 2400 Reactor thermal power at 98%%u; steady state

Si ificant 0 erational Events Utft 3 Date Time Event 0000 Unit shutdown for refueling with fuel loading operation in progress 11/9 0150 Fuel loading operation complete with all 764 fuel assemblies placed in the reactor vessel 11/22 1158 Commenced rod withdrawal for startup (Sequence "B")

1300 Reactor critical no. 74 11/23 1608 Reactor scram no. 66 (1) from 5?,'hermal power on APRM hi flux due to reactor feed pumps control problems 1719 Commenced rod withdrawal 1840 Reactor critical no. 75 11/24 0950 Reactor scram no. 67 (2) from 10?.'hermal power on false low-low reactor water level signal 1140 Commenced rod withdrawal 1231 Reactor critical no. 76 181'9 Reactor scram no. 68 (manual) from 10?'hermal vower due to low scram pilot air header pressure (control rods drifting) 2150 Reactor critical no.77 11/25 0946 Reactor scram no. 69 (3) from 101 thermal power on low vacuum due to "A" steam jet air ejector instability 1107 Commenced rod withdrawal (Sequence "B")

1205 Reactor critical no. 78 1547 Rolled T/G 1910 Synchronized generator 2218 Turbine trip on overspeed trip test from 5?,'hermal oower 2237 Synchronized generator, commenced power ascension

Si nificant 0 erational Events Unit 3 (Continued)

Date Time Event 11/26 0545 Reactor thermal power at 23/, holding for control rod scram timing (RTI-5) 11/27 1407 Commenced reducing thermal power from 23Ã to 57. for turbine trip to perform recirculation pump trip (RPT) test 1430 Turbine tripped at 5Z thermal power 1440 Recirculation pump trip test complete, commenced rod withdrawal for startup (Sequence "B")

1705 Rolled 1735 T/G'ynchronized generator, commenced power ascension 11/28 0925 Increased thermal power to 4%'for continuing control rod scram timing 11/29 0100 Reactor scram no. 70 (1) (manual) from 4M thermal power for corrections to LPRM connections 11/30 1450 Commenced rod withdrawal (Sequence "B")

2040 Reactor critical no. 79 2400 Reactor critical with startup in progress (1) Maintenance error (2) Cause unknown (3) Equipment malfunction

9 AVERAGE DAILYUNIT POWER'LEVEL DOCKET NO.

12-02-78 COMPLETED BY MONTH November 1978 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net) 17 600 591 602 594 19 608 20 611 88 21 603 22 606 585 607 586 614 602 601 602 515 10 26 580 27

-8 12 599 13 601 29 l4 601 30 IS 606 31 16 576 INSTRUCTIONS On this format, list the average daily unit power level in Mme.Net for each day in the reporting month. Compute to the nearest whole megawat t.

(91771

10 AVERAGE DAILYUNIT POWER LEVEL l

DOCKET NO 50-260 BrotIns Ferry T.Z 12-04-78 DATE COMPLETED BY TELEPHONE MONTH November 1978 DAY AVERAGE DAILYPOWER I.EVEL DAY AVERAGE DAILYPOWER LEVEL (MWe Net) (MWe Net)

I, 1086 17 1062 2 1071 18 909 1072 20 1074 21 1068 1056 22 1070 1069 1063 24 1083 1007 9'0 26 1078 11 999 27 1056 12 1062 1084 13 1064 29 1055 14 1071 30 1074 I5 1081 31 16 1026 INSTRUCTIONS On this format, list the average daily umt power level in Mme Net for each day in the reporting month. Compute to the nearest whole megawatt.

(~)/77)

11 AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 50-296 Browns Ferry III 12-04-78 COMPLETED BY TELEPHONE MONTH November 1978 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe.Net) (MWe-Net) 17 ~7 18 19 20 21

-10 ~

24 -10 25 22 10 26 163 II 27 151 12 28 299 13 29 30 IS 31 16 -6 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reportina month. Compute to the nearest whole megawatt.

(9I771

12 OPERATING DATA REPORT DOCKET NO.

DATE ~2-02-78 COMPLETED By Don Green TELEPHONE ~Z?~-6846 OPERATING STATUS I. Unit Name Browns Ferrv November 1978 l Notes

2. Reporting Period:

3. Licensed Thermal Power (hIWt):

4. Namephte Rating {Gross hIWe):

S. Design Electrical Rating (Net MWe):

6. maximum Dependable Capacity {Gross MWe):

1098.4

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>ny (Net hIWeJ:

10 R~onsForResuictions lEAn amSPe recirculation looP oPeration. "A" recirc. loo'n is out of service due to pump discharge valve 68-3 bein inonerable.

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720 8016 37 994

12. Number Of Hours Reactor Was Critical 20.88 7,251.71 20 231 59

.33 4,3a9.13

, 13. Reactor Reserve Shutdown Hours

".14. Hours Generator On-Linc 620.88 7 045.21 19 691.34

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (MWH) .l., 201, 217 18 399 443 50 772 672

17. Gross Electrical Energy Generated (hIWH) 382 420 5 999 980

18. Net Electrical Energy Generated (MWH) 371,047 ~ 5 817 873 16 306 220 ~ ~ J I

19. Unit Service Factor 86.2 87.9 '51. 8 I

20. Unit Availability Factor 87. 9 51. 8

21. Unit Capacity Factor (Using MDC Net) 48.4 68. 1

"". Unit Capacity Factor (Using DER Net) 48.4 68.1 40 3

23. Unit Forced Outage Rate 0 6.0 ~

40.2

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

25. If Shut Down At End Of Report Periog. Estimated Date of Startup: a a

26. Units ln Test Status {Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COhIMERCIAL OPERATION

<a 177)

13 OPERATING DATA REPORT DoczzT No.50-26n

'DATZ, COMPLETED BY

~n s TELEPHONE ~n -22~-6846 OPERATING STATUS Notes 1.'nit Name:

2. Reporting Period: November'978

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity {Gross MWe) 8 4

7. Maximum Dependable Capacity (Net ilIWe): 1065

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):

10. Reasons For Restrictions. If Any:

This Month Yr. to.Date Cumulative

' 720 32 an5

l. Hours In Reporting Period

'2. Number Of Hours Reactor Was Critical 720 n 15 974.29

'13. Reactor Reserve Shutdown Hours

'4. Hours Generator On4.ine an n 15 323'86

15. Unit Reserve Shutdown Hours "W""i

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

~~Q 4 948 548 4 798 035 13 140 839

.19. Unit Service Factor 66.0 46.6

20. Unit Availability Factor 66.0 46.6 56.2

22. Unit Capacity Factor (Using DER Net) 99.4 56.2 37.5

23. Unit Forced Outage Rate 5.0 47.0

24. Shutdowns Scheduled Over Next 6 Months (Type, Date. and Duratio n of Eachl:

Refue1 Outage Atsril 1979

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMibIERCIAL OPERATION (a/77)

14 OPERATING DATA REPORT DOCKET NO. 50-296 DATE -F2-78 COMPLETED BY TELEPHONE 'rr-729-6846 OPERATING STATUS Notes

1. Unit Name

2. Reporting Period: November 1978

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross iMWe):

~

S. Design Electrical Rating (Net 4%(We):

~

6. Maximum Dependable Capacity (Gross MWe):

1098.4

7. 4Maximum Dependable Capacity (Net MWe): 1065

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 Cumuhtive 720 8016

11. Hours ln Reporting Period

12. Number Of Hours Reactor Was Critical 5,651.53 12 347.20 17.92

13. Reactor Reserve Shutdown Hours

~

14.'ours Generator On-Line 74.43 5 489.77 Unit Reserve Shutdown Hours 0 0 IS.

75 132 15 496 170 34 137 864

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 5,060,980 11 094 850

18. Net Electrical Energy Generated (MWH) 1 282 10,737,802

19. Unit Service Factor, 10. 3 68.5 78. 1 10.3 68.5 78.1

20. Unit Avaihbiiity Factor

21. Unit Capacity Factor (Using MDC Net) 57.4 H.. Unit Capacity Factor (Using DER Net) 1.5 57.4 65.7

23. Unit Forced Outage Rate 38.7 10.1 10.0

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

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATIOiV (9/77)

NO. 0-2 rt UNlT SllUTDOWNS AND POWER REDUCT(ONS UNlT NAhlE 5~>e>>~et'OCKET COMPLETED DY DATE 12-04-7(t REPORT MONTH TELEPHONE 9o-C' O

Lice nscc E~

El El c~

EI o 0O Cause Sc Corrective Dale Eve rit Q Action lo C1 Cl U< c Rcport sr ro 6 E Q Prcvcnt Recurrence

~ tA CJ 781128 S C Refueling 55 99 12 3 4 F: Forced Reason: hlethod: Exhibit G - Instructions S: Schcdoletl A.Equipment Failure (Explain) l -hlanual I'or Preparatitm of Data 8-hlaintcnancc or Test 2.Manual Scram. Entry Slteets I'or Licensee C.Refueling 3.Aulontalic Scram. Event Report (LL'R) File (NUREG-D.Regulatory Rcstriclioo 4 Other (Explain) OI6I )

F. Operator Training A (3ccosc Examination F.Administrative G Operational Error (Explain) Exhibit l ~ Sante Source (9/77) ll Other (Explaio)

DOCKET NO.

UNIT SIIUTDOWNS AND POWER REDUCTIONS Browns Fer T T.

UNIT NAhIF DATE 12-A -78 COMPLETED BY Don freest REPORT MONT)I C ~ rr C:

El

~IIl0 5

C Lice nscc p Cause & Corrective No. Date 0 p.

Cl Ul

<Sec Event ~p Action to BK A~

tJ

~(A g Rcport ¹ C CJ

~ Prevent Recurrcncc F: Furred Reason: hlcthod: Exhibit C ~ Instructions S: Scheduled A.Equipment Failure (Explain) I.hlanual for Preparation oi'ata B.htalntenancc or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D.Regulatory Restriction 4.Other (Explain) OI6I )

E-Operator Training & Liccnsc Examination F-Administrative C.Operational Error (Explain) Exhtbtt I - Satnc Source I I.Other (Explain)

h UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO'.

~ r COh(PI.ETEP By Don r;reen

' REPORT h(ONTII

~ 7 TELEPIIONF 205-729-6846

,il h

fP, t4 IA I Z C Lice nscc Cause 4 Currcclivc Dale tS ~ A Event Q Act lull lu B~ Q Eu

-el 1,

A~ ~Vl g Repurl rr O CJ Prcvcnt Rccuncnce

'Ji~

-'4:

tAI 78 11 01 S 595.17 C

i. I 78 11 25 .32 B No shutdown (turbine over speed test)

J; 66 78 11 27 3.08 B No shutdown (turbine trip for recir-culation pump trip test).

]at'$

, 67 78 ll 29 47.0 A LPRM connections were improperly installed.

'~!'.

a'c,

.~. C

.-f..

,j't vi "P.,

'S~'i T

I 3

.n" F: Forced Reason: Melhod: Exhibit G - Inst rucliuns ~

S: Scheduled A.Equipmcnt Failure (Explain) I -hlanual fur Preparation of Data Q.hiaintenance or Test 2-hlanual Scram. Entry Sheets Iur Liccnsec C.Refueling 3-Autuinatic Scranl. Event Report (LER) File (NUREG.

D Regulatory Restrlcliun 4-Other (Explain) OI6I )

E.Operator Twining Ec License Exartdnatiun F.Adniinislralive 5 G.Operational Error (Explain) Exhibit I - Sante Source

()/77) I I Other (Explain)

BRCNNB BURRY NUCLBRR PIRNT UNIT~

MECllANICAL MAINTENANCE SUGARY For the Month of November 19 78 EFFECT ON SAFE ACTION-TAKEN DATE SYSTEM COMPONENT 't.ONE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE R'iNTHNANCE THE REACTOR MALFUNCTION MALFUNCTIO RECURRENCE ll/1 SLC Valv) 1-63-518 Valve: - ked Packing blown Leak Repacked valve 11/6 RCIC Pedestal slid- MMI ?2 N/A N/A MMI 22 ing foot 11/8 RBCCM Valve XV Installed- Defected annubar Annubar failure Installed annubar 100 annubar.

11/11 RCIC Turbine Inboar .Added ril N/A Excessive oil use Added oil bearing

CROWNS PRRRY NUCLRILR PIANT UNTT~

CSSC E UIPHEHT MECHAHXCAL MAINTENANCE

SUMMARY

For the'Month of November 1978 EFFECT ON SAFE ACTXOH TAKEN SYSTEM COME'ONE NT <

NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENAI:CE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE Various Snub ers Inspection N/A H/A Visual inspection of all snubbers

.1/7 Primary Drywall to tor Oil reple irish N/A Low oil level Filled oil level Cont. ua air comp- ment l

ressor

'1/9 SLC 2B pump Installei new Pump needed Leak Installed new packing R

packing and ,packing and ad)usted

.ad5usted Ll/15 Doors Personnel air Lubricated an Latch and keeper Loss of seal Lubricated;and ad)ui tei lock door ad)usted ~ - ."

misad)ustment lock, keeper and seals 11/16 HPCI'pray nozzle Opened drain Header full of Leak Opened drain valve at HPCI on hig valve water press fog fire prot.

11/21 EECW Valve~.2-67-571 Cleaned. out Stopped up with Ho flow through valv Cleaned out and and flushed mud flushed line line

./

,1l/.23 EECH. . > Valve 67-637 Packing Loose packing'eaking valve Tightened packing gland 11/24 Primary Valve 2-,64- Loosened 1 ack Packing gland Hard to open and Loosened packing Contain- 578 ing gle;.d too tight close gland ment

DROWNS FERRY NUCLEAR PLANT UNIT 3 MECIIANICAL MAINTENANCE SUMIIARY For the Month of November 19 7&

EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINiTENANCE TIIE REACTOR a MALFUNCTION MALFUNCTION RECURRENCE RCIC Inboard tur- Low oil level N/A Low oil level Filled with oil bine bearing RClC RCIC pot. leve Float free Float stuck Stuck switch Freed float SW LS 71-5 11/9 Fuel pool Fuel pool cool Leak s:"op Loose packing Packing leak Ad5usted packing cooling ing pump

~.

-11/13 CPD Stabiliz- Filter Ire- Dirty filters H20 pressure drop Replaced, filter ing tralve placement 11/21 EECW FCV 3-67-83 Valve 'leak Valve leak Valve leak Ad)usted diaphragm stop I spring, 11/22 EECW 3- 7-59li Frozen Rusty valve. Valve inoperative Unstuck and lub'ri-valve cated ll 27 EECW FCP la 3-67-50 Valve leak Valve leak Valve leak i Tightened packing.

stop gland 11 29 3 52 , Valve leak Pipe broke Valve leakI Installed 1 2 S.S.

stop plug 11/30 control Solenoid valve Solenoid Valve not valve Rod--- . CRD 30<<59 Changed'alve not seating seating I

Changed i

I 11/3 CRD 3-26-35 Change'cc Bad accumulator Bad accumulator Changed accumulator I

<miilator I

URClClS PEllRY NUCLEAR PLANT UllIT CSSC E UIEtKNT EIECTRICAL HAINTENAllCE SQSIARY For the Month of November 19 78, ect;on a e Action Taken Date System Component liat~re of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 11/7 Primary XA-6g-16 SGT pressure None Motor bad on Open and lockout Replaced motor. on Cont. 64-8,64-64B limiter open ~ 64-16 alarms would not 64-16, gumpered 64-8 and lockout reset and 64-64B to reset.

alarms will no I Checked ok. Ann.

reset after cleared. TR 105548 SGT rw.

11/6 Diesel. Diesel Gen. Perform SI None None STOL1 relay was bad Replaced bad-relays.

Generator C and D 4.9.A.l.d .on "C" D/G. Ann. Ran SI 4.9.A.l.d relay for circui't Checked ok; malfunction was bad TR 87915 on "D"- D/G.

11/23 Diesel . 480V D/G 480U D/G AUK. None Bad damper moto Improper ventilatip Replaced'ldamper .

Generator Aux. Bd. A Bd. A Room motor. Checked ok ventilati~n TR 107169 supply dr~per id stuck open

.BRIRRIB FERRY RUCLEAR FLARE IRIYY .R ELECTRICAL MAINTENANCE

SUMMARY

por the Month of November 19 78 ection a e Action Taken Date System Component Votre of Operation of Cause of Results of To Preclude Mai-. "nance The Reactor Malfunction Malfunction Recurrence 11/12 Off-Gas CVT relay CVT Relay is None Bad CVT coil Gas dilution fan 2B Replaced CVT coil burnt u'. could not be trans- Checked ok.

ferred TR 109153 A

,BRNlgg FERRY RUCLEAR PLANT UHIY ELECTRICAL MAINTENANCE StJMMARY

~ Page 1 of 3 s For tlie Month of November 19 78 ect on a e Action Taken Date System Component Nature of Operation of Cause of 'esults of To Preclude Hai~".enance The Reactor Halfunction Malfunction Recurrence CRD CRD Modu1e Hi-water level Nona Scram accumula- Hi-water level alar Replaced scram accumu 10-'23 alarm w4;i not tor level would not clear lator level switch.

clear switch bad Performed EMI 50.

Checked ok.

TR 106596 Core Spray PCV'75-11 Seal in on- None Close contacts Seal in contact is Ad5usted seal in tact ig .ot not sealing in. not picking up when contact. Checked ok picking up Seal in contact you go to open with .TR 110098 bent 75-llA; When you release the )and switch the valves g

stops 480V SD. Voltmeter ont Voltmeter not None Meter was bad Voltmeter would not Replaced voltmeter .

BD 3A 480V S;D..Bd working I work Checked ok 3k TR 96668 Air Cond. Control Bay Perform routin None. use Dirty freon filter, Repaired oil'eaks, I Chiller 3A and ma5or main Dirty oil filter, replaced freon filter~,

as required. water regulation oil filter. Charged Repair oil lea valve defective, system with Freon 22.

panel. gauges out of Repaired water regu

~ ~

None'ormal calibration oil leaks on unit

'ating valve and calibrated paneL gsagas.'hackad ck TR 106622 I ll s

2 FCV 74-1 FCV 74-1 will Motor was bad Valve could not be Replaced motor. Ran not operate operated )y motor EMI 18. Checked ok by motor TR 114330

BRIRHIR FERRY HUCLEAR FLAHY UIIYY 3 ELFFCTRICAL MAINTENANCE SUMfARY Page 2 of 3 For the Month of November 1978 I ect;on a e Action Taken System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence ll/2 Diesel Dia hragm on Diaphragm is None AP2 press. sw. Low pressure alarm Replaced AP2 and Generator pressure switc blown on AP2 bad was inoperable I.M. calibrate'd it.

AP2, Alarm cleared TR 110084 I

11/11 Primary Limit switches Limit s:itches None .Limit switches .Air supply inboard Ad)usted limit switch I Cont. on FCO-64-14 need adJusting out of adjust- isolation damper Checked ok.

and FCO-64-13 .

on FCO-64<<14 . ment not working correct TR 110042 and FCO-64-13 ly TR 110043 I

11/14 Neutron IRM select but IRM select but None Relays 7C-K9M, Select buttons'ot Replaced relays Monitoring tons tons will not 7C-K7M, 7C-K7C, giving correct in- 7C-K9M and 7C-K7M indicate full and 7C-K7F had dications and replaced coils in position burned up coils in relays 7C-K7C B-25-14 and 7C-K7F, Checked ok TR 110031 14+5- .CRB HR-RR-A Control swatch None Hand switch is =

Control switch vill Replaced atop plate .

Control switch is broken broken on, not operate on hand switch:

HS-85-48 HS S5-4S, Checked ok TR 114353 11/16 HPCI i HPCI gland HPCI gland ste None LeaH contact cli HPCI gland steam ;Tightened clip to steam exhauste exhauster on breaker was exhauster thermaled breaker finger, thc"ma s out loose on finger out after 2 min. Checked ok.

after 2 min. TR 116306 ll/21 Neutron D-SRM D-SRM hm both None Coil bad in In-out lights both Replaced coil in Monitoring in-'out light relay. 7CK7K are on and SRM vill relay 7CK7K. Checks and wil'ot move ok. TR 116398 'ot move

(BROIOIE FERRY ÃIJCLEAR FLARE UIIYY ELECTRICAL MAINTENANCE

SUMMARY

~ Page 3 of 3

~

ect on a e Action Taken Date System Component Nature of Operation of Cause of Results of To Preclude Main'nance The Reactor Malfunction Malfunction Recurrence 11/21 Primary Relay 16AK68 16M(68 is None Bad relay and Power ann. circuit Replace relay and Cont. chattering and resistor would not operate resistor. Checked arcing properly ok. TR 116801 11/21 Primary Relay 16$ -K23 Burn out-'coil None Bad coil Improper ann. Replaced coil on Cont-. on pnl 9-42 on lnb-K 3 relay. Cl~ecked ok e

TR 116802 I

TR 114374 11/22 RCZC FCV,71-10 FCV 71-10 has None LS3 and LS4 on ~

No indicating light Ad)usted',limit arms, no,indications FCV 71-10 limit Checked ok.

light . arms are out of ,TR 116393 ad)ustment 11/22 Main Steam FCV 1-27 Red end Eeeen None Actuator loose Red and green light Ad)usted limit switch

'ndicating on limgt switch both on with valve and tightened lights are botl closed actuator. Checked on with valve ok. TR 114385.

clos'ed ll/24 Diesel Gen 3B D/G ~

Lube oil circu None Bad bearings on Noise and bearing Bearings replaced lating pr >n drive motor heating up Checked ok.

appears t 'av TR 114384 bad bearing 11/25 Neutron llFll ZRM Bad con~ector NJne Pin pulled loose Improper operation Replaced pin on wire Monitoring on "F" ZRM from wire. of "F" IRH and soldered aBnnectioq Checked ok TR 67697

OROUNS PERRY NUCLEAR PLANT UNIT 1 2 3 INSTRUtlEtlT tfAIHTEtbNCE SUMtfARY CSSC E UIPHEHT llONTE OF November, 197E 'OR'llE Effect on Safe Action Taken Nature of Operation of Cause of Results of to preclude Date System Component Maintenance the reactor ,. Malfunction Malfunction recurrence JHIT 1 ll/13 Primary PDT-64-138 Calibrati"n None Zero Shift Did not agree with None Containment ~ I v redundant indicator

'I

'.l/15 Standby LI-63-lB ,calibratiE n None Gage needed rezeroing Did not agree with None Liquid stick measurement Control SNIT 2 11/6 RCIC FI-71-1A Calibration None Zero Shift Indicatedl flow when None v ~ out Iof service 11/10 CRD Pds-85-63,64 Replace None Gages damaged Indicated high 5 P None UNIT 3 I

11/1 RPIS Pdobe 34-35 Replace None Bad "4" switch in IO's No. "4'n IO's Column None Column 11/17 Standby LI-63>>1B Calibration. None Cage needed rezeroing Didl not agree with 1X None Liquid of stick measurement Control 11/19 RCIC

'l-71-1B I

Calibration None Zero Shift Indicated flow when None shut down .

11/21 RPIS Probe 34-35 Replace None >

BaEI reed switches No 10, ll, 14, 15, 18 None or 40 indication 11/21 RPIS Probe .30-51 Replace None Bid reed switches.: o OD thru 09 indicatio None 22-39 ll/24 HPCI FT-73-33 Calibr>tb h

None Zero Shift Indicated flow when off None ll/26 Primary PDI-64-137,138 Calibrate None Zero Shift eadings did not agree None Containment

'E3 '

I J

I

~11/30 PIS Probe 42-43 Replace None Bad reed switch o "04" indication None

27 OUTAGE SECTION MONTHLY REPORT November 1978 Puel loading for unit three was completed November 9, 1978, and investigations into rod problems resulted in the changeout of the rod 46-39 and realignment of the fuel support casting. These rod problems and corrective actions lost a total of 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> in critical path time.

The RPV leak rate test identified the following leaks: Instrumentation flange, 2" Vent line in the drywell, valve 43-13 leaking, MSSV 1-537, bonnet leak on 74-54, and CRD flange leaks. Subsequent repairs and changeout of the safety valve caused the startup testing to slip from November 20 to November 22, 1978.

A1l. refuel floor activities were completed November 20, when the shield blocks were installed.

All dryweU. work, modification work and instrument work were completed November 21, 1978 except for post-mod tests and those tests to be completed during the startup testing sequence. The Held breakers were closed on unit 3 on November 25, ending the unit 3 cycle 1 refueling outage.

Preparations commenced immediately for the unit,l refuel outage which began November 26 at 8:53 p.m. Vessel disassembly of unit 1 went smoothly with only minor delays. The initial drywell entry revealed leaks on 68-33, -77 and 3-99, 98. The A, C, and D MSIV's failed the Local Leak Rate Test (LLRT) and will be repaired.

At the end of the period the unit 1 outage is approx&ately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> behind the overall planned outage.

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