ML20052F971
| ML20052F971 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/07/1982 |
| From: | Jones V, Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20052F964 | List: |
| References | |
| NUDOCS 8205140200 | |
| Download: ML20052F971 (46) | |
Text
i 0
5- . 3 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 82-03 MARCH, 1982 APPROVED BY:
- h LCS A STATION MANAGER O
0205140200 820415 PDR ADOCK 05000200 R PDR
o i
4 i Section Pane j Operating Data Report - Unit #1 1 Operating Data Report - Unit #2 2
Unit Shutdowns and Power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #2 4 Load Reductions Due to Environmental Restrictions - Unit #1 6 Load Reductions Due to Environmental Restrictions - Unit #2 7 Average Daily Unit Power Level - Unit #1 8
Average Daily Unit Power Level - Unit #2 9
Summary of Operating Experience 10 Amendments to Facility License or Technical Specifications 15 l Facility Changes Requiring NRC Approval '
16 Facility Changes That Did Not Require NRC Approval 16 Tests and Experiments Requiring NRC Approval 19 Tests and Experiments That Did Not Require NRC Approval 19 Other Changes, Tests and Experiments 20 Chemistry Report 21 Description of All Instances Where Thermal Discharge Limits Were Exceeded 22 Fuel Handling 23 Procedure Revisions That Changed the Operating Mode Described in the FSAR 26 Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 27
, inservice luspection 28 Reportable Occurrences Pertaining to Any Outage or Power Reductions 29 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 30 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit- #2 - Mechanical Maintenance 32 e
4
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h Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 34 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 36 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 38 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 40 Health Physics Sunssary 42 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee af ter Time Limits Specified in T. S.
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___ _ - _ _ _ _ - A
CPERATING DATA REPORT l ,
DOCKET NO. 50-280 DATE 07 APR 82 CONPLETED BY Vivian H. Jones OPERATING STATUS TELEPHONE 804-357-3184
- 1. UNIT NAME
- 2. REPOR"'ING PERIOD SURRY UNIT 1 30182 T033182
- 3. LICENSED THEliNAL PWER (WT) 2441 l~
- 4. NAMEPLATE RATING (GROSS WE) l 847.5 l NOTES l
- 5. DESIGN ELECTRICAL RATING (NET WE) 788
- 6. NAXIMUM DEPENDABG CAPACITY (GROSS MWE) 811
- 7. MAXIMUM DEPENDABG CAPACITY (NET WE) 775
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A (ITD!S 5 THROUGH 1) SINCF LAST REPORT, GIVE REASONS
- 9. F W ER LEVEL TO WHICH RESTRICTED, IF ANY N/A (NET NVE)
- 10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH XR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.0 2160.0 81288.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 732.2 1768.5
- 13. REA:"ZOR RESERVE SHUTDWN HOURS 47803.0
- 14. HOURS GENERATOR ON-EINE 0.0 0.0 3731.5 728.6 1753.6 46828.4
- 15. UNIT RESERVE SHUTDOVN HOURS 0.0 0.0 3736.2
- 16. GROSS THE}iNAL ENERGY GENERATED (WB) 1735017.5 4081076.5 108414342.9
- 17. GEOSS E MCTRICAL ENERGY GENERATED (MWH) 556885.0 1285955.0 35105168.0
- 18. NET ELECTRICAL ENERGY GENERATED (WH) 530421.0
- 19. UNIT SERVICE FACTOR 1220522.0 33297758.0
- 20. UNIT AVAILABILITY FACTOR 97.9 =/* 81. 2 */
- 57.6 */=
97.9 e/o 81.2 e/= 62.2 e/o
- 21. UNIT CAFACITY FACTOR (USING MDC NET) v2.0 e/o 72.9 */*
- 22. UNIT CAPACITY FACTOR (USING DER NET) 52.9 */*
- 23. UNIT FORCED OUTAGE RATE 90.5 */* 71.7 */* 52.0 =/*-
3.4 e/o 4.7 */* 24.8 */*
- 24. SHUTDOWNS .SCHEDUGD OVER NEXT 6 MONTHS (TYPE,DATE,AND DURATION OF EACH) MAINTENANCE - 11/19/82 - DAYS-Io i
- 25. IF SHUT DWN AT END OF REPORT PERIOD, ESTINATE DATE OF STARTUP
- 26. UNITS IN TEST STATUS t
l FORECAST ACHIEVED (PRIOR TO COMMERCIAL CPERATION)
\ INITIAL CRITICALITY INITIAL E MCTRICITY COMMERCIAL OPERATION i
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NO. 50-201 =-
' DATE 07 APR 82 COMPLETED BY Vivian H. Jones -
TELEPHONE 804-357-3184 ,
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- 1. UNIT NAME ..
- 2. REPORTING PERIOD - -
/ SURRI 30182,TC=33182 UNIT 2 x?
- 3. UCENSEE THER4AL PWER (MWT) ~ _ 2u41 I~ i .~ l /,:
- 4. NAMEPLATE RATING (GEOSS'WE) 847.5 l NOTES - ~ ' '
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- 5. DESIGN EGCTRICAL RATING (NET .WE) :188 %
-s
- 6. NAXIMUV DEPENDABLE CAPACITY (GR2SS MVE) '811 ' %.
s 2
- 7. NAXIMUM DEPENDAEG CAPACITY (NEi' W:) <775 ~,_, %,$ .
- ~'
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS ~ 'N/4 : \ *
- ' .~
(ITB45 3 TitROUGH 7) SINCE LAST l- .
REPORT, GIVE.. REASONS ,
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- 9. POVER GVEL TO VEICH RESTRICTED, IF~ ANY N/A j "
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a (NET MVE) '. '
's 1'
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, S' THIS MONTH lfR-TU-DAT? CUMULATIVE- .
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- 11. HOURS IN REPORTING PERIO: 144.0 2160.0 78168.0,.
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- 12. NUMBER OF HOURS REACTOR WA3 URITICAL ~ 611.C .
- 1993.2 ~ 46853.9 %
- 13. REACTOR RESERVE SHUTDOWN HOURS ~" 0.0 ' :- 0.0 ,. 0.0*, '\,,
' ' s, '
- 14. 500RS GENERATOR ON-UNE .
\ s / .. 589.8 , 1956.4 %6068.1 * .
- 15. UNIT RFSERVE SHUTDOVN-HOURS / - 0. 0 ' , 0.0
- O.0 *
- 16. GROSS THERMAL ENERCI GENERATED (GH) 1285201.7 4218236.1 107515522.0
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- 17. GROSS ELECTRICAL ENERGI, GENERATED (NVH)
- 18. NET ELECTRICAL ENERGY GENERATED (NWH) -
402635.0 377753.0 1354920.0 35032}29.0 M73667.0 33202382.0
- Q%
- 19. UNIT SERVICE FA"IOR 79.3 e/* $0.6 */* 58.9 */o
- 20. UNIT AVAILABIU T!. FACTOR 79.3 */* 90.6 e/* 58.9.6/o
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 65.5 =/* 76.1 */* 54.8 ele 1
- 22. UNIT CAPACITY FACTOP (USING DER NET) 64.4 */* 74.8 e/o 53.9 */o ' "
-\
- 23. UNIT FORCED QUTAGE-RATE . -n 5.4 e/o 2.9 e/o 16.8 */* '\
- 24. SEUTDWNS 3"HEDULED OVER NHT 6 MONTHS SPRING MAINTANCE - 5/7/82 - 10DATS
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(TYPE,DATE.AND DURATION OF EACH) ~' ~
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- 25. IF SHUT DWil AT END OF REPORT PERIOD. /
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ESTIMATF DATE OF STARTUP '
- 26. UNITS IN TEST STATUS F? RECAST ACHIEVED ..
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(PRIOR TC C04MERCIAL OPERATION)
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INITIAL CRITICA U TY x x INITIAL EUCTRICITI , ,
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i UNIT StIUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-280_ ,
1 UNIT NAME Surry One DATE .AnrII 7. 1982 REPORTMONT1g Harch. 1982 COMPLETED Bir _Viv. an H. Jon.es l TEt.EPHONE (8041 357-3184 ext. 477 1
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Date k r. 8 $ m Event uT "
Action to i
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$E E jgg Report # N0 Prevent Reevnence 6
i 82-6 03-20-82 S 0.0 H 4
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Reduced power to allow stopping i
equipment to reduce load on "A"
' Reserve Se a tion Serv *cc Transformer j
to <2000 amps during Unit 2 recovery.
i 82-7 03-25-82 F 15.4 H 3 50-280/ Instrument technicians aerforming a e
{
' 82-040/03L-0 periodic test placed inst- =entation T in " trip" which.In coincidence with a i switch out adjustment caused the "A" reactor coolant, pump to trlgi causing a low flow reactor trip. The switch i
was adjusted prior to unit startup.
,i i
i i
i I 2 3 4 f F: Forced Reason: Method: EnhlMt G-Insirecthms (
S: Scheduled A-Equipment Failure (Explain) I-Manual for recperothm of Dasa B-Maintenance of Test 2-Manuel Screm. Entry Sheets for t.icensee C-Refueling 3 Automatic Screm. Event Report (LERI File (NilREG-D Regulatory Restricthm 4-Other (Emplain) . 0161)
E-Operator Training & IJcense Eneminathm F-Administrative 5 G Operstional Error (Explain) Exhibit I Same Source l'8/77) Il-Other (Explain)
a DOCKETNO. 50-281 - '
UNIT SHUTDOWNS AND POWER REDUCT10NS Surry Two UNIT NAME __
DATE, Anrli 7_ 1982 l
COMPT.ETED BY Vivian H. JQDes REPORT MONTH Harch. 1982 11ELEPHONE (804) 357-3184 ext. 477 3 -
]E 3 Ef Licensee E*, k Cause A Corrective Acthm to N. Date k 7. g 5 3 s a: Event g3 mo u H
$E E j;gg Report # g p,,,,,,gec,,,,,c, 6
82-17 03-01-82 S 120 7 H I Continuat8on of shutdown for maintenance which began 02-27-82.
82-18 03-08-82 F 0.0 A 4 Power reduction to rencve 2-SD-P-1 A (high pressure drains pump) from service for repairs.
82-19 03-11-82 F 24.1 G 3 50-281/ the unit was shutdown imi T.S. 3 3 8 j.
82-017/03L-0 Jue to a loss of recirculation flow to the boron injection tank. The recirculation flow, was. reestablished prior to startup.
82-20 03-20-82 F 9.4 A 2 .
Loss of EHC pressure due to a relief
~
valve lifting caused all turbine 9overnor valves to drift closed.
Operator manually tripped the turbine and reactor; problem was corrected prior to unit startup.
l
^
l 3 4 l 2 F: Forced Reason: Method: Ezhibit C. instructions A Equipment Failure (Explain) 1-Manual for Preperselon of Data S: Scheduled 2 Manuel Screm. Entry Sheets for Licensee B-Maintenance of Test C Refueling 3 Automatic Screin. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & IJcense Enaminathm -
F-AdminisiratIve 5 G-Operational Error (Explain) Exhibit I Sane Source t'8/77) II-Other lExplain) .
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l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKEYNo. 50-281 ,
UNIT NAME Surry Two DATE dDr I 7. 1982 Cotet.ETEDgy Viv an H. Jones
' REPORT MONTH March. 1982 TEt.EPHONE (804) M7 Il8de ext. 477
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c5 82-21 03-30-82 F 0.0 A 4 Reduced power to allow 2-FW-P-IB j
(main feed pump) to be taken out of 1
service for repairs.
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. 4 F: Forced Reason: neetlood: Exhibit G-lastructkms 5: Scheduled A Equipment Failure (Explain) 140anual for Preparstkm of Data B-Maintenance of Test 2 Menest Screm. Entry Sheets for 1.kensee C Refueling . 3 Automatic Scram. Event Report (i.ERI File (NUREG.
D-Regulatory Restrictlim 4Oher (Emplaini 0161)
E. Operator Training & IJeense Examinathm ,
F Administrative 5 I
G.Operallonal Esens (Enplain) Eshable i .Same Source l's/77) Il-Other (Explaini
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LOAD REDUCTIONS DUE TO ENVIROIOGNTAL RESTRICTIONJ UNIT NO.1 MONTH: March. 1982 DATE , TIME ROURS LOAD. W REDUCTIONS. W WH REASON None durir s this reporting period.
O MONTHLY TOTAL
}
LOAD REDUCTIONS DUE TO ENVIR000 ENTAL RESTRICTIONS UNIT NO.2 MONTE: Ma rch , 1982 DATE e TIME HOURS LOAD. W REDUCTIONS. W WH REASON None durir g this reporting period.
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I MONTHLY TOTAL
D0:1:3 NO 50-29,0 UNIT SURI:7 I ,
' DATE k-1-82 C0YPLETEI' EY Vivian H. Jones AVEWCT DAILY Ul!!T P%TR LWEL VD:ITh : 4Ait:h 82 AVERAGE DAILY PATR LEVEL AVERAGE DAILY POVER EZYEL DAY (%T-liET) DAY (M T-NET) 1 751.7 17 747.7 2 752.L 18 745.5 S 746.8 19 7ut.6 4 747.e 20 E54.2 5 748.5 21 744.8 6 747.8 22 745.8 7 749.0
, 25 745.6 P 7u9.2 24 744.9 o
751.9 25 S29.5 10 748.5 26 280.0 11 748.S 27 E78.5 12 744.u 22 7h4.1 la 7u6.6 29 759.c 14 741.9 40 7uS.L 15 744.5 S1 745.2 16 7u6.u XILY UVI: E:JER LEVEL ECR.: IllSTRUCTICliS
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JA 11.IS F016, E.737 Tli? AVERACE DAILX Ul;IT P%TR EELTL IN ML'E-NET FOR EA3 Dly Il! w
.?HE LLPOL'II;G VORTH. THESE EIGUREF VILL BE USED TO PLOT A GRAPH FOR EA:li REPORT- .
- !.'3 VCliTH. RO7E THAT BY USING MAXIMU.V DEPEllDAELF CADA:ITY F:R THE flET ELECTRICAL 1ATIl>G OF THE Ui;IT, THERE YlY BE OCCAEIONS WHEN THE DAILY AVERAGE P3TR EXCEEDS
.'HE 1C C * / o LINE (CR THE RESTRICTD POJER LnTL LINE). II: 20:5 CASEE, THE AVERAGE MILY UIIT FakTR CUTPl?I SHEET SHOULD BE FOOTNOTED TO HPLAIN THE APPARENT Ati2?ALY.
e
- 9" D:CEE71:0 50-281
' UXIT SliRRY I:
- DATE k-1-82 COVPLETED BY Vivian H. Jones AVFR/GE DAILY Ur:IT n'ER LEVEL tiGi!TEs 14AIX7i 82 AVERAGE DA~LY PNER EEVEL AVERAGE DAILY PWER LEVEL DAY (WE-NE') DAY (.WE-flET) 1 0.0 17 697.0 2 0.0 1E 696.3 4 0.0 19 69t.S L 0.0 20 SSS.9 5 0.0 21 602.4 6 S81.8 22 622.0 7 428.7 25 626.5 8 sos.S 24 624.F 9 712.1 25 69t.5 10 722.9 26 694.8 11 490.0 27 696.9 12 8S.2 28 696.5 13 614.9 29 696.0 it 669.5 30 682.4 15 693.8 31 649.4 16 696.6 DAILY U.VIT FRER LEVEL Faki INSTRUCTIONS 2R TE:S FORs , Z ST THE AVERAGE DAILY UNIT 5'ER ZEVEL :N YdE-NET FOR EACH D!.Y IN IRE 1.2F0 ICING N0i!TH. THESE FIGURES WILL BE USED TO PLOT A GRA?ii FOR FA:H REPCI:-
' TNG VONTH. NOTE TVAT BY USING NAXI4UV DEPTNDAELE CAPA:ITY FOR THE NET ELECTRICAL hATIkG 2F THE UNIT, THERE MAY BE OCCASIONS WiEN THE DAILY AVERAGE PNER EXCEEDS
!HE 1C0 e/* LINE (Oh THE RESTRICTED PNER ZEVEL LINE). IN EUCH CASES, THE AVERAGE b.t:LY U: LIT FWER CUTPUT EHEE"I SHOULD E! FOOTNOTED TO EXPL/.IN THE APPARENT ANCYALY.
SUMMARY
OF OPERATING EXPERIENCE MARCH, 1982 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT ONE March 1 This reporting period begins with the unit at 100% power.
March 20 1000 - Started reducing power to allow stopping 1-FW-P-1A (main feed pump) and 1-CN-P-1A (main condensate pump) to reduce "A" Reserve Station Service Trans-former load to < 2000 amps during Unit 2 recovery.
1155 - Stopped power decrease at 72% power.
1157 - Stopped 1-FW-P-1A and 1-CN-P-1A.
1548 - Started 1-FW-P-1A and 1-CN-P-1A and commenced increasing power at 3% per hour.
March 21 ' 0330 - The unit is at 100% power.
March 25 1035 - During the performance of Monthly Periodic Test (safety injection and feedwater control isolation logic) the breaker to the "A" Reactor Coolant Pump ("A" RCP) opened. This resulted in a RCP "A" breaker open reactor trip. Reactor and generator power dropped off to zero very rapidly
- along with steam flow from "A" S/G. Steam flow from S/G's B & C didn't fall as fast as programmed flow, thus a 2 out of 3 high steam flow signal was generated. Tave dropped below 5430F giving a low Tave signal, which combined with the high steam flow signal to give a Safety Injection.
1912 - The reactor was critical.
l 1958 - The reactor tripped on a Safety Injection (SI) signal from steam header to steam line AP. The SI was spurious and caused by vibration of the header I pressure transmitters mounted in the turbine l building.
l 2312 - The reactor was critical.
March 26 0157 - The generator was placed on the line.
0219 - Power increase was stopped at 35% to verify Steam Generator chemistry in specification.
1102 - S/G chemistry was verified in specification and a power increase at 3% per hour commenced.
SUMMARY
OF OPERATING EXPERIENCE MARCH. 1982 March 27 1300 - The unit was at 100% power.
March 29 1230 - Leakage past the reactor coolant system (RCS) make-up valves during boration to the spent fuel pool introduced unwanted boron in the RCS. This caused a reduction in RCS temperature (Tave).
1245 - Started reducing power to recover Tave.
1305 - Stopped power decrease at 86%/710 MWe. Tave has been recovered.
1348 - Started power increase at 3% per hour.
1525 - The unit was at 100% power.
March 31 This reporting period ends with the unit at 100%
power.
UNIT TWO March 1 This reporting period begins with the unit at cold shutdown for environmental upgrads of various power supply cable splices and various maintenance items.
March 4 1715 - Commenced primary system heatup.
1810 - RCS temperature exceeded 2000F (Cold Shutdown condition).
I 2243 - Started 2-RC-P-1A (reactor coolant pump) after repairs on the "open" limit switch on the cold leg stop valve were completed. The failure of this LS prevented makeup of the logic circuit for starting 2-RC-P-1A.
March 5 0025 - RCS temperature and pressure exceeded 3500F and 450 PSIG respectively.
0800 - The unit reached hot shutdown condition.
1349 - The reactor was critical.
l March 6 0045 - The generator was placed on the line. The delay be-
[ tween reactor criticality achievement and the gener-ator going on line was due to problems encountered I
with the auxiliary overspeed governor solenoid valves.
t The solenoid valves were diaassembled and repaired.
I l
1 l e
SUMMARY
OF OPERATING EXPERIENCE MARCH , 1982 March 6 0150 - The unit was at 35% power and holding for steam (cont'd) generator (S/C) chemistry verification.
- 0319 - S/G chemistry verified in specification and power increase started.
1418 - Stopped power increase at 66% to maintain conden-sate polishing building AP 5,50 PSIG uniti the high pressure heater drain pump is returned to service.
March 7 0403 - Attempted to start the 2-FW-P-1A main feed pump.
The attempt failed due to a ground on the inboard motor. The gound was a result of water in the motor. The water entered the motor when the relief valve on a feedwater heater lif ted.
1553 - The high presscre heater drain pump was returned to service.
March 8 0825 - The "A" MFP was returned to service.
0840 - Started increasing power.
1030 - The unit was at 100% power.
1427 - Commenced power ' reduction to stop the high pressure heater drain pump.
l 1433 - Stopped power decrease at 94% power and secured the high pressure heater drain pump for shaft seal repairs.
1 l
1446 - Commenced power reduction to reduce AP across the i
condensate polishing demineralizers to 5,50 PSIC.
1645 - Stopped power decrease at 70% power and 540 MWe with six condensate polishing demineralizers in service.
l 2342 - Returned seventh condensate polishing demineralizer l
to service and commenced increasing power until AP is equal to 50 PSIC.
March 9 0146 - Stopped power increase at 86% power.
0226 - Started the high pressure heater drain pump.
0320 - Started increasing power.
0527 - The unit was at 100% power.
1720 - Numbers 2 and 3 Governor Valves started drif ting closed causing loss of approximately 50 MWe.
. j3 !
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SUMMARY
OF OPERATING EXPERIENCE MARCH, 1982 j
March 9 1743 - Stabilized the unit at 690 MWe/85% power.
(cont'd) 1753 - No. 2 and 3 GV's slowly opaning.
1838 - The unit was at 100% power.
1942 - Isolated EHC fluid to no. 3 GV to clean the EHC strainer in the servo-valve.
March 10 1111 - Number 2 GV failed closed causing drop in load to approximately 700 MWe and in power to approximately 90%. The EHC fluid to no. 2 GV was isolated to allow cleaning the strainer in the servo-valve.
1345 - Valved in EHC fluid to no. 3 GV.
1400 - Valved in EHC fluid to no. 2 GV.
1548 - Commenced increasing power. The strainers for no.
I and no. 4 GV's were also cleaned.
1620 - The unit was at 100% power.
March 11 1200 - The Chemist reported low boron concentration in the samples drawn on the boron injection tank (BIT).
Investigation by the Operations Department revealed no recirculation flow to or from the BIT and no boric acid flow to the blender. Started two (2) hour " clock" for start of shutdown due to loss of BIT recire.
1208 - A valve was discovered closed on the suction of the boric acid transfer pump supplying boric acid to the blender and boric acid recire on the BIT. The valve was opened and boric acid flow to the blender was restored.
1355 - All attempts to restore recirculation flow on the BIT have proven unsuccessful and a shutdown has commenced.
1735 - The reactor tripped form 15% power due to a high level signal from the 6A feedwater heater. The high level was a result of leaking tube (s) in the feedvater heater. The 5A and 6A feedwater heaters were subsequently bypassed and isolated.
March 12 1500 - The reactor was critical after the plug in the inlet line to the BIT recire was cleared and the heat tracing on the lines restored.
1742 - The generator was placed on the line. The upper limit for turbine power is 90% with the SA and 6A feedwater heaters bypassed and isolated.
. , - , ,w e --~ -- - +,-,---e - -- -n,-,,-g--,--y----- - , - --
SUMMARY
OF OPERATING EXPERIENCE MARCH. 1982 March 12 1903 - Stopped power increase at 35% to verify S/G chemistry.
(cont'd) 1910 - S/G chemistry was in specification and a power increase commenced.
March 13 0005 - Stopped power increase at 90%.
0145 - Stopped the high pressure heater drains pump for shaf t seal repair.
March 14 0527 - Started the high pressure heater drains pump.
0,835 - Started increasing power to 740 MWe.
0915 - Stopped power increase at 740 Mwe/95% power.
March 20 0545 - All turbine governor valves started drifting closed causing a loss of turbine load. The control room operator manually tripped the turbine and the turbine trip caused a reactor trip. A relief valve lifting on the EHC system caused a loss of EHC pressure to the hydraulically operated GV's allowing them to close.
0642 - The reactor was critical.
1506 - The generator was placed on the line.
1601 - Stopped power increase at 35% to verify S/G chemistry.
1623 - S/G chemistry was in specification and a power in-crease has commenced.
2045 - Stopped increasing load and power at 87% on the turbine and 97% on the reactor.
2205 - Reduced turbine load to 85% and assumed all auxiliary steam loads.
March 30 2129 - Started reducing power to allow removing 2-FW-P-1B (main feed pump) from service for repairs.
2210 - Stopped B MFP.
2218 - Stopped power decrease at 560 MWe/72% power.
March 31 0545 - Started B MFP.
1 0554 - Started power increase.
0715 - Stopped power increase at 740 MWe/96% power.
This reporting period ends with the unit at 96% power and limited to 740 MWe as a result of SA and 6A feed- ~
water heaters being out of service.
AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS MARCH. 1982 The Nuclear Regulatory Commission, on January 19, 1982, Issued Amendment Nos. 73 and 74 to the Operating License for Surry Power Station Unit Nos. 1 and 2 respectively.
~
These amendments revise the Technical Specifications to allow an
, increase in enrichment for new and spent fuel from 3 7 to 4.1 weight percent of U-235 -
Accordingly, the paragraph 3 8 of the Operating License for Unit I and 2, respectively, is amended as follows:
(Unit 1) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, are hereby incorporated in the license. The IIcensee shall operate the facility in accordance with the Technical Specifications."
(Unit 2) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 74, are hereby incorporated in the license, The licensee shall operate the faellity in accordance with the Technical Specifications."
The Nuclear Regulatory Commission, on February 2, 1982, issued Amendment Nos. 74 and '75 to the Operating License for Surry Power Station Unit Nos. I and 2 respectively.
These amendments revise the Technical Specifications to reduce the minimum number of thimbles required for incore flux mapping .
from 40 to 38.
Accordingly, the paragraph 3.B of the Operating License for Unit I and 2, respectively, is amended as follows:
(Unit 1) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 74, are hereby incorporated .
in the license. The licensee shall operate the facility in accordance with the Technical Specifications."
(Unit 2) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 75, are hereby incorporated in the IIcense. The licensee shall operate the facility in accordance with the Technical Specifications."
, FACILITY CHANGES REQUIRING NRC APPROVAL March, 1982 None during this reporting period.
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL March, 1982 Unit D/C 80-45 Add Gasket to Top and Bottom of RSHX 1&2 This design change isolates the diaphragm from potential excessive positive containment pressure by installing a gasket between the diaphragm and the coverplate. This is a more conservative measure taken to provide protection for the diaphragms during a LOCA.
SUMMARY
OF SAFETY ANALYSIS The modification will not affect the operation of any safety related equipment; it serves only as an added degree of protection for the system involved.
D/C 81-03 Liquid Storage Warehouse 1&2 j
To insure that proper fire and safety precautions are utilized, a storage facility was built for flammable, combustible and corrosive liquids. This warehouse was constructed in Storage Area "C" east of the Plant Warehouse.
SUMMARY
OF SAFETY ANALYSIS This facility allows for the proper storage of flammable and corrosive chemicals, thereby enhancing the safe and l
efficient operation of the plant.
i D/C 81-08 Ba111stic Protection and Modification of Masonry Block Walls 58-27-0-6, 7, and 4 1&2 l
1 To ensure that Masonry Walls SB-27-0-6, 7, and 4 meet i
ballistic requirements and seismic criteria, the following 1
design change (s) were made in response to IE Bulletin 80-11:
- a. Installed ballistic shielding (Level 4)
- b. Relocated safety related equipment
- c. Reinforced wall by the addition of steel members.
- FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL March, 1982 Unit D/C 81-08 Ballistic Protection and Modification of Masonry Block Walls SB-27-0-6, 7, and 4 (continued) I&2
SUMMARY
OF SAFETY ANALYSIS The modifications associated with this design change support the FSAR commitments. The structural steel added by this modif* cation does not adversely affect the structural capability of the existing floor slabs.
D/C 81-19 Machine Shop Replacement Facility 1&2 D/C 81-198 Structural Steel Frame for Machine Shop Rep lacemen t Facility, was implemented.
SUMMARY
OF SAFETY ANALYSIS
~
The addition of the Machine Shop Replacement Facility
does not minimize the safety of operating units or effect the operation of safety related equipment.
- D/C 81-31 Installing Indicating Light for Valve Position I&2 This design change installed indicating lights on the vertical board of control room for A0V-IA-103 (Unit 1) and A0V-IA-203 (Unit 2) to verify if the valves are i
positioned open or closed. These valves open to supply
{ suction to air compressors upon containment isolation.
SUMMARY
OF SAFETY ANALYSIS This modification does not effect the operation of any safety related equipment. It will improve the operational ability of containment instrument Ai r System.
D/C 81-57 Fuel Pool inspection Light Receptacles 1&2 This design change installed four receptacles on the pool side of the crane well for fuel inspection flood lights. This was accomplished by installing a 480/120 1$ transforemer and four water tight electrical outlets.
SUMMARY
OF SAFETY ANALYSIS This modification does not offect the operation of any safety related equipment.
D/C 81-101 Replace impe11ers in Radiation Monitoring Sample Pumps 2 This design change replaces the existing impellers with
' larger impellers to provide the required TDH. The TDH was increased due to D/C 80-56. -
e., ---
,y.,, , . - . . , . , . - - , . , , . , , . - - . - . - . - _
', i FACILITY CHANGES THAT-DID NOT REQUIRE NRC APPROVAL March, 1982 Unit D/C 81-101 Replace Impe11ers in Radiation Monitoring Sample Pumps 2 (continuco)
SUMMARY
OF SAFETY ANALYSIS This modification does not affect station operations or operations of the radiation monitoring sample pumps. It does provide the increased TDH requirements.
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- TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL March, 1982 None during this reporting period.
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL March, 1982 Date Special Test No. Unit Title Completed ST-52 2 Reactor Coolant System Flow Measurement Test 03-08-82 ST-36 2 Steam Generator Moisture Carryover Measurement 03-16-82 l
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. .. OTHER CHANGES, TESTS AND EXPERIMENTS March, 1982 None during this reporting per}og, 0
/
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SI'RRY POCR STATION MLF. 2 0 76 CHDf1STRY REPORT March , 19 82 T.S. 6. 6. 3.d PRIMARY COOLANT UNIT NO. 1 ANALYSIS 1MIT No. 2 i
MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERACI Gross Radioact., UCi/mi (A) (A) (A) -l j -2 -)
4.27 1.70 2.51 3.60E -
5.41E 1.73E Suspended Solids, ppm 0.1 0.1 0.1 0.1 0.1 0.1 Gross Tritium, UCi/mi 1.50E
~ ~ ~ ~ ~
6.65E 1.04E 1.23E 7.71E 9.94E
~
Iodine-131, DC1/ml (A) -2 -2 -2 -4 -2 5.58 7.33E 7.33E 7.63E 9.58E 1.38 _E I-131/I-133 1.2214 .3708 .8673 .8955 .4808 .7358 Hydrogen, cc/kg 38.1 21.5 29.1 49.8 27.6 36.8.
Lithium, ppm 1.35 .86 1.10 1.38 .55 .99 Boron-10, ppm + 204 109 133 456 162 246.
Oxygen-16, ppm (D)
.000 .000 .000 .005 .000 .000 Chloride, ppm kO5 <.05 <.05 <.05 <.05 <.05 pH 0 25'c 6.88 6.43 6.66 6.66 5.66 6.26 ~
+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL D)
RELEASES. POUNDS .
T.S . 4.13. A. 6 c Phosphate -
Boron 1055 Sulfate -
Chromate .15 50% NaOH -
Chlorine -
Remarks: (A) Indicates possible failed fuel elements (B) Unit trip @ 1035 3-25-82 on line
@ 0300 3-26-82(C) Unit shutdown condition 3-1 3-6-82: on line 2 0045 3-6-82; 3-11-82
@ 1335 commenced ramn-down due to lov boron iniection tank concentration - Rx trin 1735; Rx on line 3-12-82 @ 1742: Rx 3-20-82 0 0454 on line @ 1540 3-20-82(D) These levels of chemicals should create no adverse environmental inoact.
l
.e DESCRIPTION OF ALL INSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED March, 1982 Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.
, March 6, 1982 Exceeded 17.5 F AT across station
- March 7, 1982 Exceeded 17 5 F AT across station March 8, 1982 3 Exceeded 15 F AT across station
- s March 9, 1982 Exceeded 17 5 F AT across station * ,
March 10, 1982 Exceeded 17.5 F AT across station March 11, 1982 Exceeded 17 5 F AT across station
- March 13, 1982 Exceeded 17 5 F AT across station March 14, 1982 6 Exceeded 15 F 0 AT across station March 15, 1982 Exceeded 17.5 F AT across station
- March 16, 1982 Exceeded 17 5 F AT across station March 17, 1982 Exceeded 17 5 F AT across station March 18, 1982 Exceeded 17 5 F AT across station March 19, 1982 6 Exceeded 15 F AT across station March 20, 1982 Exceeded 15 F AT across station
- March 21, 1982 Exceeded 15 F AT across station
- March 22,1982 Exceeded 15 F AT across station March 23, 1982 Exceeded 15 F AT across station
- March 24, 1982 Exceeded 15 F AT across station March 25, 1982 Exceeded 15 F AT across station
- March 27, 1982 Exceeded 15 F AT across station
- March 28, 1982 Exceeded 15 F AT across station
- March 29, 1982 Exceeded 15 F AT across station *
~
March 30, 1982 Exceeded 15 F AT across station
- March 31, 1982 Exceeded 17 5'F AT across station *
- lndigates dates where station AT was less than or equal to 15.0 F across station for some
- Ime during the day.
' The AT excursions were allowable under Technical Specification 4.14.B.2. There were no reported instances of adverse environmental i
impact.
The temperature change at the station discharge exceeded 3 F per hour on the following dates and for the noted reasons:
On March 20, 1982, due to a Unit 2 reactor trip; On March 25, 1982, due to a Unit I reactor tirp; and On March 28, 1982, due to natural causes (2 5 F increase in station inlet water temperature).
These events were allowable in accordance with Technit.a1 Specification te.14.B.1. There were no reported instances of adverse environmental impact.
The temperature change at the station discharge exceeded 3 F per hour on March 12, 1982, due to a rapid increase in circulating water flow through Unit 2 main condenser. This event was reported in accordance with Technical Specification 4.14.C.I.
1
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, .. .' FUEL HANDLING March, 1982 UNIT ONE Twenty four (24) new fuel assemblies and twenty four (24) new BPRA's were received in March, 1982 for Unit one refueling.
UNIT TWO None during this reporting period.
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FUEL HANDLING I March, 1982 UNIT ONE DATE 180. OF ANSI NO.
SHIPPED / RECEIVED NEW OR SPENT FUEL ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT i SHIPPING CASK ACTIVITY LEVEI 03-04-82 12 LMOAM3/3 6% <2.5 MR/HR LMOALF/3.6% <2.5 MR/HR LM0AMN/3.6% <2 5 MR/HR
__ LMOAL5/3.6% <2.5 MR/HR l LM0ALG/3.6% <2 5 MR/HR LMOAML/3.6% <2 5 MR/HR LMOAMH/3 6% <2.5 MR/HR LMOALW/3.6% <2 5 MR/HR LM0ALJ/3 6% <2.5 MR/HR LMOAME/3.6% <2 5 MR/HR LM0ALU/3.6% <2 5 MR/HR LMOAMK/3.6% <2.5 MR/HR 03-11-82 12 LMOAMP/3.6% <2.5 MR/HR LMOALP/3.6% <2.5 MR/HR I
LMOALL/3.6% <2.5 MR/HR LMOAMQ/3.6% <2.5 MR/HR LM0ALN/3.6% <2.5 MR/HR LM0AM2/3.6% <2.5 MR/HR t
LM0AM1/3.6% <2 5 MR/HR
~
LMOALM/3 6% <2 5 MR/HR i
LMOALQ/3.6% <2.5 MR/HR j LMOAMJ/3.6% <2.5 MR/HR 4
LMOAM5/3.6% <2.5 MR/HR LMOAM0/3.6% 4.5 MR/HR '
,, , ,._ _._._ ,,y_, , , _ . _ . . . 5 ,, , , - , _ - - , - - - , - - , , . . . , , . , , . , _ - - . - - _
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FUEL HANDLING-March, 1982 ,
UNIT "iWO ,
DATE NO OF SHIPPED / RECEIVED ASSDIBLIES PER SHIPMENT INITIAL hBMENT SHIPP A IV LEVEI
\
I None-during this' reporting period.
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k PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR March, 1982 None during this reporting period.
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DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TF.CHNICAL SPECIFICATIONS March, 1982
~
None during this reporting period.
INSERVICE INSPECTION
_ MARCH, 1982 UNITS ONE AND TWO No inservice inspection work was conducted.
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REPORTABLE OCCURENCES PERTAINING TO ANY OUTAGE OR POWER REDUCTIONS March, 1982 None during this reporting period.
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HEALTH PHYSICS MARCH, 1982 There was no single release of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20.
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< PROCEDURE DEVI ATIONS REVIEWED BY STATION NUCLEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LIMITS SPECIFIED IN TECHNI CAL SPECIFICATIONS MARCH, 1962 Date SNSOC Procedure No. Unit Title Date Deviated Reviewed Nuclear Assurance 1 Out-of-Core Sipping 01/30/82 03/11/82 Corp. Document Procedure 720, Revision 1 i
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