ML18024A850
| ML18024A850 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/31/1979 |
| From: | Dewease J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A849 | List: |
| References | |
| NUDOCS 7906150283 | |
| Download: ML18024A850 (36) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT Hay 1, 1979 i~iay 31, 1979 DOCKET i%uSERS 50-259, 50-260, AND 50-296 LICENSE NUiiBERS DPR-33'PR-52'ÃD DPR-68 Submit.tted By:
Plant Superintendent 790615099+;
TABLE OF CONTEiXTS Operations Summary Refueling information
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2 Significant Operational Events Average Daily Unit Power Level Operating Data Reports Unit Shutdowns and Power Reductions.
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9
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12 15 Plant Maintenance Outage Section ifonthly Report 18 34
0 erations Summar 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 six reportable occurrences repoxted to the i'uxing the month of May.
Unit 1 The unit did not scram during the month.
Unit 2 The unit was down for refuel the entire month.
The unit scrammed four times during startup.
On May 26, the unit scrammed on high IRK flux during rod withdrawal.
On May 28, the reactor scrammed on TRM high flux due to a feedpump control malfunction.
The reactor scrammed on May 29 due to vessel low water level (feedwater control, malfunction).
On May 30, the reactor scrammed when the MSIV's closed during venting of the main steam line flow sensors.
Unit 3 The unit scrammed once during the month.
On May 13, the reactor scrammed on low water level due to a feedpump control malfunction.
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 Feedwater nozzle Closure studs 0.00407 0.18688 0.17378 0.00280 0.12200 0.00251 0.09658 0.10829 0.07406 Note:
This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.
Common S stems Approximately 1.07E+06 gallons of waste liquid were discharged containing 5.87E-OI.
curies of activity.
2, 3,
and 6 were operational.
Repair work on Tower 4 was completed.
Installation of new fillmaterial on Tower 5 continues.
Refueling 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 assembl'es into the core, replacing presently loaded 7 x 7 fuel.
Unit 1 (Continued)
I 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 524 assemblies.
With present capacity, Unit 1 does not hhve full core discharge capability in the pool.
Unf.t 2 Unit 2 began its second refueling beginning on April 27, 1979, with a scheduled restart date of June 1, 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 involves 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"fuel assemblies and 268 discharged cycle 2 fuel assemblies in the spent fuel storage pool.
The present storage capacity of the spent fuel pool is 1080 assemblies.
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.
4 Unit 3 Unit 3 is scheduled for its nezt refuel outage beginning on September 1,
1979, with a scheduled restart'ate 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.
1 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 Onerational Events Uait 1 Date T~4e Event 5/01/79 0001 1530 Reactor thermal power at 20% with power ascension in progress Commenced PCIOMR from 75% thermal power S/O2 A
S/O3 2305 0018 0300 Reduced thermal power from 86% to 45% for control rod pattera adj'ustment e
Control rod pattern adjustment completed, commenced power ascension Commenced PCIOHR from 70% thermal power s/o4 1930 Reactor thermal power at 99%, steady state 5/05 2210 2355 Reduced thermal power from 99% to 85% for turbine CV tests and SI's Turbine CV tests ann SI's completed, commenced power ascension s/o6 0030 0700 Commenced PCIOHR from 95% thermal power Reactor thermal power at 99%, steady state 5/07 S/11 0300 0330 0430 0700 1500 2000 Reduced thermal power from 99% to 70% due to "A" recirculation pump run back (blown fuse 2A-P16A)
Blown fuse replaced, commenced power ascension Commenced PCIOHR from 95% thermal power Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 93% and locked "B" recirculation pump scoop tube when placed on manual due to HG set coatroller malfunction.
"B" recirculation pump scoop tube unlocked, commenced power ascension S/12 0630 Reactor thermal power zt 99%, steady state 5/18 2200 Reduced thermal from 99% to 40% for control rod sequence ezchange from "B" to "A" S/19 0020 0225 0405 Commenced turbine CV tests and SI's Turbine CV tests and SI's completed, holding for control rod sequence exchange Control rod sequence e:<change from "B" to "A" completed, commenced.
power ascension 5/20 5/21 0330 0350 Commenced PCIOHR from 90% thermal power Reactor thermal power at 99%, steady state
I Si nificant Operational Events Unit 1 Date Time Event 5/23 1155 1200 1300 Reduced thermal power f om 99% to 90% for isolation oz "A" low pressure heaters for level controller maintenance "A" low pressure heater level controller replaced and heaters placed in service, commenced power ascension Reactor thermal power at 99%, steady state
'=* '/24 2140 2310 Reduced thermal power from 99% to 55% for control rod pattern adjustment Control rod pattern estaolished, commenced power ascension 5/25 5/26 5/31 0100 0800 2400 Commenced PCIOHR from 80% thermal power Reactor thermal power at 99%, steady state Reactor thermal power at 99%, steady state
7 Si nificant Operational Events Unit 2
Date Time Event 5/01/79 0001 Reactor at cold shutdown for scheduled refueling outage (cycle 3 fuel) 5/26 1816 1928 Commenced rod withdrawal for startup (turbine unavailable)
Reactor scram no.
77 while subcritical on I%M hi flux 5/27 5/28 0207 0322 0327 1443 2213 Commenced rod withdrawal Reactor critical no.
88 Reactor made subcritical Reactor critical no.
89 Reactor scram no.
78 on IRM hi flux (feedpump (1) control malfunction) 5/29 5/30 0027 0200 0632 0808 0910 0912 1223 1000 1532 1740 Commenced rod withdrawal Reactor critical no.($)
Reactor scram no.
79 on low water level (feedwater control malfunction)
Commenced rod withdrawal Reactor critical no.
91 Reactor made,subcritical Reactor critical no.
92 Reactor scram no.
80 on HSIV isolation during (1) venting of main steam line flow sensors Commenced rod withdrawal Reactor criticaL no.
93 5/31 2400 Reactor critical with startup in progress with turbine still unavailable
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Si nificant Operational Events Unit 3
Date Time Event 5/01/79 0001 Reactor thermal power at 80%, holding for maintenance on "C" reactor feedwater pump 5/13 0110 0230 0835 Maintenance and vibration checks completed on "C" reactor feedwater pump and pump placed in service, commenced power ascension Commenced PCIOMR froyi)8% thermal power Reactor scram no.
72 from 95% thermal power on low reactor water level due to reactor feedwater 5/14 2355 Reactor feedwater pump maintenance completed, holding for hydrogen sensor replacement 5/16 0510 0629 1447 1547 Hydrogen sensor
- replaced, commenced rod withdrawal Reactor critical no.
82 Roiled T/G Synchronized generator, commenced power ascension 5/17 J
5/18 0700 1720 1745 Commenced PCIOMR from 70% thermal power, control rod sequence "B"
Reduced thermal power from 90% to 75% for maintaining reactor water level while charging "C" string high pressure heaters Commenced PCIOMR from 75% thermal power 5/19 2315 Reduced thermal power from 88% to 50% for control rod pattern adjustment and for turbine CV tests and SI's 5/20 0137 0145 0700 Concrol rod pattern adjustment completed, holding for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension Commenced PCIOMR from 72% thermal power 5/21 2300 Reactor thermal power at 99%, steady state 5/25 2240 Reduced thermal power from 99% to 80% for turbine CU tests and SI's 5/26 0045 0240 1523 Turbine CV cests and Si's completed, cormnenced power ascension Commenced PCIOMR from 88% thermal power Reactor thermal power a" 99%, steady state 5/31 2400 Reac or thermal power at 99%, sceady state (1) Equipmenc malfunction
9 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
COPIPLETED BY MONTH DAY AVERAGE DAILYPOWER LEVEL (irlWe.Net)
DAY AVERAGE DAlLYPOWER LEVEL (MWe.Net) l7 872
~1.
5 1056 1060 1045 18 l9 20 2l 23 1048 1057 1053 1051 IO 12 l3 l5 l6 1063 1043 1044 1063 1056 15 26 27
'2S
'79 30 3l 868 1070 1070 76 1065 INSTRUCTIONS Qn this format. list the average daily unit power level in iNIWe.Net for each day in the reporting tnt>nth. Cotnpute to the nearest whole megawatt.
(')l>7)
AVERAGE DAILYUNITPOWER LEVEL i
DOCKET NO.
50-260 Browns Perry 2
DATE COMPLETED BY TELEPHONE 205-729-684 6 hIONTH DAY AVERAGE DAILYPOWER LEVEL (hiWe.Net)
DAY AVERAGE DAlLYPOWER LEVEL (hIWe-iNet) 5 6
7 8
9 10 l2 l3 14 IS I6 17 l8 l9 80 22 23 25 26 27 28 29 30 31
-2
-10
-10
-10
-10 INSTRUCTIONS On this format,!ist the average daily unit power level in M~Ve.Net for each day in the reporting tnonth. Compute to the nearest whole megawat t.
(9j77 l
AVERAGE DAlLYUiVITPOWER LEVEL Browns Perry 3
DATE ~2~7 COMPLETED BY TEI.EPHONE 205-729-6846 MONTH DAY AVERAGE DAILYPOWER LEVEL (MWe-iVet)
I 856 DAY AVERAGE DAILYPOWER LEVEL (MWe.Net) 747 17 3
6 9
10 13 IS 16 853 877 879 879 877 875 873 873 868 339
-13 18 19 10 21 22 23 14 25 26 27 28 19 30 31 898 894 803 1010 1054 1043 1051 1048 1066 1010 1068 1071 1050 1064 INSTRUCTIONS On this format. !ist the average daily unit power level in ib('iVe.Net for each day in the reporting month. Compute to the nearest whole rnegawat t.
('>!77)
12 OPERATING DATAREPORT DOCKET NO.
DATE 6-2-79 COMPLETED SY ~~n TELEPHONE ~~9 6846 OPERATING STATUS I. Unit Name'
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Namephte Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
Notes
- 8. IfChanges Occur in Capacity Ratings (Items i(umber 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Net i~IWe):
- 10. Reasons For Restrictions. IfAny:
'his Month Yr.-to.Date Cumuhtive 167.31 0
2937.72 744 0
0 8,610,022 2, 315,045 770,280 2 794 415 750 029 81.1 100 81.1
. 100 72.4 94.7 6.7 0
(Type, Date. and Duration of Each):
Il. Hours In Reporting Period
- 12. Number Ot 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)
I'7. 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 LIIonths 4566.44
'22629.069,382,694 19,6 8,5 0
19'00 635 53.4 53.4 42.3 37
~ 3 5
- 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 INITIAL ELECTRICITY COiIAIERCIALOPERATION (oi77)
~t.
13 OPERATL iG DATAREPORT DOCKET NO.
DATE COMPLETED BY TELEPHONE ~~6846 OPERATIjIG STATUS Notes Unit Name.
Browns Ferrv 2-Z. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Namephte Rating (Gross MWe):
S. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross jlfWe):
a itv Net MWe:
- 7. ibfaximum Dependable Cap c
(
)
- 8. IfChanges Occur in Capacity Ratings (Items i lumber 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
- 11. Hours In Reporting Period
~ 12. Number Of Hours Reactor Was Critical
"-'3. Reactor Resene Shutdown Hours
"', 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH)
IS. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit AvailabilityFactor
- 21. Unit Capacity Factor (Using ifDC Net)
- 22. Unit Capacity Factor (Using DER iNet)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over ilext 6 ilfonths 0
0 o
0
- 8. 25 2770.40 0
0 0
0 0
0 2,857,580 76.5 76.5 72.2 72.2 1.3 (Type, Date. and Duration of Each):
11 534.96 18 838.26 0
17, 171,368 1
7 747 0
50.5 50.5 42 '
42.0 41.9
- 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 liNITIAL ELECTRICITY CO%I ifERCIAL OPER ATIOii
- Inforajation unavailable (9/77)
OPERATIiIG DATAREPORT DOCKET NO.
DATE 6-2-79 COibIPLETED BY DRIES ~rg TELEPHONE ~y'~ol46 OP ERATlilG STATUS Notes
- 1. Unit Name'
- 2. Reporting period:
Mav 1 7o
- 3. Licensed Thermal Power (ilIWt):
- 4. Nameplate Rating (Gross ibIWe):
- 5. Design Electrical Rating (Net siIWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe):
7 Maximum De endableCa acit Net MWe:,
1065
~
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)
- 8. If.Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To which Restricted, IfAny (Net ibIWe):
- 10. Reasons For Restrictions, IfAny:
This sblonth Yr:to-Date 3623 744 3539.25 83.75 3522.17 0
10,762,566 3 593 640 3,504,795 97.2 9
0 8
90.8 Il. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 69
~ 9
- 14. Hours Generator On-Line 664.8
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 1,927,118 ty. Gross Eiectrient Energy Generated iMtVH)
- 18. Net Electrical Energy Generated (M'IVH)
- 19. Unit Service Factor
- 20. Unit AvailabilityFactor
- 22. Unit Capacity Factor (Using DER Net) 78.0
- 23. Unit Forced Outage Rate 10.6 '.8
- 24. Shutdowns Scheduled Over Next 6 i~lonths (Type, Date. and Duration of Each):
uta e Seotetaber 1.
1979 Cumulative 19'27 16,630.45 1189.16 16252.15 0
46,913,948 15 361,140 14,909,983 82.4
~ 71.0 71.0 8.1
~
I e
- 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIAL ELECTRlCITY CORI!itERCIAL OPERATION
(</77)
- ~
UNITSIIUTDOWNS AND PO1VER REDUCTIONS REPORT hIONfll DOCKET NO.
COMPLETED IIY JlOa QKLCQ=
TELEPIIONE No.
Date PI Vll Q
I v l/l Ltccrtscc
. Event Rcport rr C+
Q 0o N
m Cr C
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cD C ~
O Cr Cause &. Corre<ttve Action lo Prevent Recurrcncc 80 79 05 02 Derated for control rod pattern ad ustment 79 05 07 Derated due to "A" reclrc pump run back 82 79 05 38 Derated for control rod sequence exchan e from "II" to "A" 83 79 05 24 Derated for control rod pattern ad ustment F: Forced S: Scheduled
()/>>)
Reason:
A.Equipmcnt Failure (Explain)
II hlaintenance or Test C-Rcfuelinl, D.i<et;ulatory Restriction E.Operator Training & I.iccnsc Examination F-Administrative C Operational I.rror (Explain)
II Other (fixplain) hlethod:
I.hlanual 2.hlanual Scram.
3-Automatic Scram.
4.0ti>er (Explai>>)
Exlribit C
~ Instructions for Preparation of Data Entry Sltecls lor l.icc>>see Event Report (I.L'R) File (NUREC-OI6I)
Fxhibit I ~ Satnc Source
UNITSI IUTDO)UNS AND POlVER REDUCTIONS REPORT h(ONTII DOCKET NO.
50 260 UNIl NAhIE Bt-ownn F 2
COh(PLETED OY ~~~n TELEPIIONF 205-729-684<6 No, Date IArjo fP~
I Q A
~ n
~ cc
~ CA Liccllscc Event l(cporl 4 0
Q OO 0
Cause k, Corrective Acllollt<l Prevent Recurrence 86 79 05 01 744 Refueling F: Forced S: Scheduled
(<>/77)
Reason:
A.Equipment Failure (Explain)
I).hlaintenance or Test C. Refueling
- D Regulatory Restriction E.Operator Training A license Examination F.Administrative G Olrerati<mal (error (I'.xplain)
II Other (Explain) hlethod:
I hIanual 2.hlanual Scram.
3-Aulontatic Scram.
4.Other (Explain)
Exhibit G-Instructions for Preparation of Data Entry Sheets for I.iccnsee Event Report (LL'R) File (NUREG.
016I)
Exhibit I - Same Source
UNITSIIUTDO\\VNS AND POPOVER REDUCTIONS UNITNAhfE Browns Perr 3
COhIPLETED BY TELEPllONE No.
Date PI u
gr, c
'~
U~ r.
w rir Licensee
. Event Rcport 8 CQ IV 0o Vl cn G r
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Cause &. Corrective Action lo Prcvcrtt Rccurrcrtce 93 79 05 01 Derated due to high vibration on oCo Rx feed um 9'9 05 13 F
79.2 Low Rx water level due to feedwater pump controls malfunction. Unit remained down for replacement of torus H2 sensors 79 05 19 Derated for control pattern adjustment and turbine CV tests F: Forced S: Scltcduled
('>/77)
Reason:
A.Equipment Failure (Explain)
B.hlaintenance or Test C.Refueling D Regular ory Rest riclion E Operator Training k License Examination F-Adodrrisl ra Ilac G Operational Lrrur (Explain)
~
I I.Other (lixplain)
Method:
I.hlaoual 2 hlaoual Scram.
3.Aulotnatic Scram.
4.0t I>er (L'xplain)
Exhibit G - Instractions for Preparation ol'Data Entry Sheets I'or Licensee Evcllt Rcport (LER) File (NUREG-OI 6I )
5 Exhibit I - Satnc Source
CSSC E UIPHEHT BROWS PERRY NUCLEAR PIANT UNIT HEC1IANICAL HAINTENANCE SUIDIARY Por the Honth of Hay 19 79 DATE SYSTEH COHPONENT EFFECT ON SAFE NATURE OP OPERATION OF IIAINTENANCE THE REACTOR CAUSE OP IIALFUNCTION RESULTS OF HALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE Rx.
and Turbine Bldg. Vent Air washer screens Dirty screens Insured clean air in reactor and turbine bldg Airborne parti-cles Dirty'screens Cleaned screens i/22 Rllk SN Cl RIIRSW pump discharge vent Seat and floe damaged; woul not seal off None Defective seat and float Lack of seal Replaced seal an float i/20 SI.C SI.C accumula-tors IlHI 40 None None None HHI 4O i/17 i/20 Control Bay Vent Control Bay Vent lB control bay chiller C Bay chiller lA Clean tubes Valve needs replacing None None Dirty tubes Valve leaking None Hone Cleaned oil cooler and installed new
- gaskets, cleaned evaporator and reassembled opened raw water cooler and inspected.
0 Plugged holes
CSSC H VIPHHNT BROMNS PERRY NUCLEAR PIANT UNIT 1
hfEClfANICAL1fAINTENANCE SUMfARY For the Honth of Nay 19
~9 DATE SYSTEH COHPONENT NATURE Or'fAINTENANCE EFFECT ON SAPE OPERATION OP TflE REACTOR CAUSE OP ffALPUNCTION RESULTS OP ffALFUNCTION ACTION TAKEN To PRECLUDE RECURRENCE Rx. Recirc Recirc pump shaft seals Check pressure and annuncia-tions None None one hecked pressures and mnuncia tions Control Bay Vent.
Computer room CO2 operated dampers Excessive cabl weight None Excessive cable weight ables heavier than ampers rnstalled weights on dampers 1-85-516A Packing leak Necessary for safe shutdown Loose packing
'eeking leak ightened packing
CSSC E UIP11ENT BROWS PERRY NUCLEAR PLANT UNIT 2
~
MECHANICAL MAINTENANCE SUNHARY Por the Honth of 14y 19 79 DATE SYS TEN COHPONENT NATURE OF NAINTENANCE EPFECT ON SAPE OPERATION OF THE REACTOR CAUSE OP W LPUNCTION RESULTS OF 11ALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE
'7 Rx. Recirc Recirc pump shaft seals Check pres-sures and annunciations None None None Checked pressures and annunciations I9 Rx.
Zone Vent 2-6~i-510 area Remove sheet-metal None Sheetmetal covering openings lloles blocked off'emoved patch cov ng openings
'23 CRD 2-PSV-85-37B Install CRD drain and vent pilot valve repair kit Necessary for safe Rx. shut-dowll Needed CRD drain and vent pilot valve repair kit installed None',
Installed kits
CSSC E UIPffENT BROWS FERRY NUCLEAR PLANT UNIT 3
MECHANICAL tfAINTEHANCE SUMfARY For the lfonth of 'y 19 79 DATE SYS TEH CO>1POHENT EFFECT ON SAFE NATURE OF OPERATION OF lfAIHTENANCE TflE REACTOR CAUSE OF MALFUNCTION RESULTS OF lfALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 5/7 Rx. Recirc Recirc pump shaft seals Check pressure None and annuncia-tions Hone Hone Checked pressure and annunciations 5/8 Control Bay Vent.
CO> operated dampers in computer room 3
Excessive cable weight Hone Excessive cable weight Cables heavier than dampers Installed weighes on dampers 5/13 Fuel pool Cleanup 3A fuel pool cleanup'pump Leaking at None inboard pack-ing Packing leaking Leaking Adjusted packing 5/14 Primary Contain-ment Torus Open manhole None None None Hanhole opened Primary Contain-mene Torus Open Hanhole None None None kfanhole opened 5/15 Drywell Doors Drywell doors Replace o-ring Insures primary gaskets containnlent Worn gaskets Heeded gaskets Replaced gaskets
BROILS PERlti NUCLEAR PLAM1 UHIT EI.ECTRICAT. HAINTENANCE SlkkfARY Page 1 of 1
)ate System Component 'ature of Haintenance E
ect on Sate Opera tion of The Reactor Cause of Halfunction Results of Halfunction Action Taken To Preclude Recurrence 79 Standby diesel Battery char-ger A for D diesel gen-.
erator and battery char-ger A for C diesel gen-erator Battery char-ger mould not charge Not applicable Failed resistor on chargers Batteries not charg-ing-Replaced resistors, placed on equalia-ing charge, per-formed EHI 4, checked OK, TR's 125928 a
125931
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CSSC E UIPtlENT BRO'alHS FERRY NUCLEAR PLANT UNIT ELECTRICAL HAIHTEHAHCE SIQfARY For the 11onth of Hay
]'9 79 Page 2 of 5 System Hain
- steam, Rt 1CU, RCIC$
- 11PCI, and RHR Component Limi:torque motor opera-ted valves located in
- drywell, steam tunnel, and RHCU room listed in a ttaclunen t A
-of EtlI 16 Nature of Ilaintenance Perform EtK 16 (limi-torque geared lind.t switch gear box lubricant inspection and replace-ment unit 2 E
ecton
'a e
Opera tion of
.The Reactor Not applicable Cause of Nalfunction Beacon 325 grease breaking down due to high temperatures Results of Halfunction Potential failure of geared limit switch Valve 8 FCV-1-55 1-57 1-56 71-3 1-169 1-170 69-1 68-33 68-1 68-77 68-79 68-3 74-78 73-2 71-2 69-2 68-35 74-48 1-58 rat 87940 137903 142746 137913 137907 137908c-137910 130997 87944 142773 130996 87945 137915 1427 137911 130998
- 137914, 137904 Action Taken To Preclude Recurrence Inspected and removed all Beacon 325 grease, replaced lubricant with Mobil grease 28, performed EHI 18 and EHX 16~.
Primary contain-ment lli rad-refuel zone relay 16AK63A coil Annunciator inoperable Not applicable Open relay coil Annunciation would not clear Replaced coil, tested functional, TR 127244
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CSSC E UIPHENT BROlPilR FERRY MVCLEAR PLANT VRIT ELECTRICAL HAINTENANCE SUGARY For the ffonth of Hay 19 79 Page 4 of 5 I)ate 5-24-79 System IfPCI Component Uni.t 2 IfPCI ramp genera-tor and EGff box Nature of llaintenance Ramp genera-tor and EGH box would not operate pro-perly ect on
'a c Operation of The Reactor Not applicable Cause of Halfunction Electronic equipment ap-.
parently shorted out by mechani-c'al problems in EGR Results of Halfunction If in operation,
. ffPCI would have failed to operate Action Taken To Preclude Recurrence Replaced-ramp gen-erator and EGH box, checked OK, TR 125916 5-24-79 Reactor water recircu-lation FCV-68-1 (R/C 2-A suction valve) limit switch 813 Adjust limit switch 813 Not applicable Limi.t swi.tch out of adjustment Unable to start recirculation HQ set Adjusted limit switch 813, checked OK, TR 110327 5-24-79 Reactor water recircu-lation FCV-68-3 Adjust limit switch 813 Not applicable Limit switch out of adjustment Unable to start recirculation HG set Adjusted limit cn switch 813, checked OK, TR 125917 5-24-79 Reactor.
water recircu-lation FCV-68-77 Adjust limit switch 813 Not applicable Limit switch out of adjustment Unable to start recirculation HG set Adjusted limit swi.tch 813, checks OK, TR 125919 5-24-79 Reactor water recircu-lation FCV-68-79 I
Adjust limit switch 013 Not applicable Limi.t switch out of adjustment Unable to start recirculation HQ set Adjusted limit switch 813, checked OK> TR 125918
RROMiYE PERRY RUCLEi'R PLRRT UUTT 2
ELECTRXCAL MAINTENANCE SUHIIARY 39 79 Page 5 of 5 it e System Component Nat:ure of llaintenance ect on ba e
Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 25-79 llPCI Auxiliary oil pump motor Check start circuit None, unit in refueling out-.
age Motor and 250V breaker failed Xf in operation, 1IPCX would have not operated properly Replaced auxiliary'il pump motor and breaker,. teated OK, TR 126988
~30-79 Radiation monitorin Cam 90-57 pump mot:or Pump inopera-tive Not applicable Pailed motor bearings Motor.inoperable Xnstalled new motor, tested OK, TR 138902 79 Hain steam Hain steam isolation valve 1-37 Valve posi-t:ion indica-tion inopera-tive Not applicable Loose limi.t switch arm Green light (closed Tightened limit stays on with valve switch arm, tested open OK, TR 124737 79 Control rod drive IIS-85-47 rod out, rod notch over-ride switch Chtlck over-ride switch Not applicable Pai.led override switch Override switch inoperable Replaced override switch, tested OK,'R 124785
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CSSC E UIFIIENT ER0%13 FERRY NUCLEAR PLANT UllLT 3
ELECTRICAL HAINTENANCE SIMARY A
For the IIonth of Hay 19 79 Page 2 of 3
)ate 3-15-79 System Hain steam Component Nature of Ilaintenance Check relay E
ect on a e Operation of The Reactor Not applicable Cause of Halfunction Limit switch 3
and 4 on FCV 14 and limit switch on FCV-1-26 Results of ARfalfunction Relay de-energized Action Taken To Preclude Recurrence Adjusted limit switch actuator, tested OK, TR's
- 115816, 115815, and 106115
>-3.5-79 IIPCI FCV-73-45 (testable check valve) indicating lights Check red light cir-cuit Not applicable Limit switch out
,of adjustment Red light (open
.position indica-tion) inoperable Adjusted and clea limit switch and tested valve OK, TR 126&61 5-15-79 RPS Reactor Scram reset switch return spring Spring does not function properly Not applicable Spring out of keeper Failure of spring to return to nor-mal position Replaced spring, tested operation OK, TR 122627 5-15-79 Hain steam FCV-1-52 Limit swi.tch for 5AK3II relay out of adjustment Not applicable Limit switch failed 5AK3H relay dropped out Replaced limit switch, checked OK, TR 106114 5-15-79 Radiation Honitorin Cam unit:s 3-
~ 90-249 and 3-90-251 vacuum pump belt:s Check belts Not applicable Morn belts Preventative maintenance
'Replaced belts, checked OK, TR 131042
CSSC E UIPHENT
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RRO'.iWS Pram Wcr.ml rr.@AT,ynZT 3
ELECTRICAL MAINTENANCE SRMARY For t:he lfonth of Hay 19 79 Page 3 of 3 System Component Nature of Haintenance
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ect on a e Operation of The Reactor.
'ause of lfalfunction Results of Halfunction Action Taken To Preclude Recurrence 79 Rllk FCV-.74-68 (testable check valve)
Closed posi-tion.(green) indicating "
light irioper-able Not applicable Broken leads at Reed switch on valve Green'light-failure Repaired
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i-16-79 RCIC FCV-71-3 limit switch ChecIc limit Not applicable switch Defective limit switch Unable to determine proper positiop of valve Replaced limit switch, performed EllI 18, TR 142759 i-16-79 Air con-ditioning 3B chiller Check operat-ing cycle Not applicable Oil pump starter contactor fail-ure Chiller inoperable Tightened starte'r connection, checked OK, TR 126847 (A
i-21-79 llPCI LA-73-8 (HPCI turbine exhaust: drain pot hi level annunciation)
Check hi level drain Not applicable Float stuck Alarm in Freed float, cleared annunciator, checked operation, OK, TR 126699.
5-22-79 Fuel pool cooling and de-mineraliz-ing LS-78"28 (fuel pool) lli level sbitch in-operable Not applicable Bad switch Would not come-in for.high level Replaced switch,-
'performed Etll 48, TR 127326
CSSC EQUIPHENT HROIINH IHRRRY NVCI.HAR PLASHY UHYY INSTRlJt tENT HAINTENANCE StMfhRY For the Honth of
)ate System Component Nature of.
Haintenance
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ect on Sa e
Operation of The Reactor Cause of Halfunction Results of Halfunc tion.
Action Taken To Preclude Recurrence i-29-79 Primary Contain-ment PDT-64-138 Calibrate None Zero drift Indication did not agree with redun-dant indicator None ti-31-79 Emergency Equipment Cooling tJater PdS-67-1 Replace None Diapliram rupture High DP al'arm would not clear Hone I
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CSSC EQUIPlfENT BUO)JtLS FUlNY UUCLEAll 1'LANT UllLT 3
INSTRUffENT HAXNTENANCE SUHffARY For the Honth of Hay 19 79
)ate System Component Nature of.
Haintenance E
ect on Sa e
Operation of The Reactor Cause of Halfunc tion Results of Halfunction Action Taken To Preclude Recurrence 79 Radwaste FQ-77-6 Calibrate None Zero shi ft Indicates flow wi.th pump off None
~-5-79 Neutron XfQf "F" Honitor- ~
inf; Repair None Open detector cable in dry-well No indication of.
power lave'1 None
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34 OUTAGE SECTION MONTHLY REPORT May 1979 Major work for the outage group during the month of May. consisted of scheduled maintenance to Un't 2 which was down for refueling.
Scheduled maintenance involved work in the drywell and testing and repair to the
'main steam isolation valves, other primary containment isolation valves and miscellaneous system valves.
There were also modifications and maintenance performed on the main steam relief valves, feedwate" heaters and condensers.
Electrical work consisted of maintenance on the electrical boards and motors and other scheduled maintenance.
The low pressure "B" section of the turbine was inspected and over 1000 dovetail pins replaced.
Major turbine valves, such as the stop,
- control, bypass,. intercept and cross-around relief, were inspected.
The Unit 2 outage was completed on June 1, 1979, making the total length of the outage 34 days.
There were several ongoing modifications which were not related to the Unit 2 refueling outage.
The magnetic switch and conduit pull to the control room for the security modification was underway along with the installation of the 480V reactor MOV boards.for the LPCI modification.
The excavation for the hypochlorite building was underway and is also continu'ng.
The trip logic and cable terminations are almost complete on the cooling towers, with testing underway.