ML20053B989
| ML20053B989 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/06/1982 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20053B985 | List: |
| References | |
| NUDOCS 8206010399 | |
| Download: ML20053B989 (43) | |
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VIRGINI A E'.ECTRIC AND POWER COMPANY
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SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 82-04 APRIL, 1982 APPROVED BY:
SW 4
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STATION MANAGER L
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820 6 010 3 7 ct R
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Section g
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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 6
Load Reductions Due to Envirouzental Restrictions - Unit #1 7
Load Reductions Due to Environmental Restrictions - Unit #2 8
Average Daily Unit Power Level - Unit #1 9
Average Daily Unit Power Level - Unit #2 10 Summary of Operating Experience 11 Amendments to Facility License or Technical Specifications 16 Facility Changes Requiring NRC Approval 17 Facility Changes That Did Not Require NRC Approval 17 Tests and Experiments Requiring NRC Approval 18
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Tests and Experiments That Did Not Require NRC Approval 18 Other Changes, Tests and Experiments 18 L
Chemistry Report 19 Description of All Instances Where Thermal Discharge Limits Were Exceeded 20 Fuel Handling 22 Procedure Revisions That Changed the Operating Mode Described in the FSAR 23 Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 23a Inservice Inspection 24 Reportable Occurrences Pertaining to Any Outage or Power Reductions 25 Maintenance of Saf ety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 26 Maintenance of Saf ety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 28 I
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11 Section Page
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Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 30
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Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 32 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 34 Maintenance of Safety Related Systems During Outage or Reduced Pcwer Periods - Unit #2 - Instrument Maintenance 36 Health Physics Sumary 38 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee af ter Time Limits Specified in T. S.
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-1 3FiiUTIiG DlT/ RE?)RT t
DOCKET NO. 50-280 DJTE 05 %tY 82 C)"FLETED BY SUE D. DUNN TELEF5 li? 804-357-3184
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CE!5JTING ST/TUS
- 1. UNIT H/VE SURRY UllIT 1
- 2. TEP:.TIKG FERIOD 40182 72 L3002
- 3. L1CEl;5EE TiiERVAL P.WEin \\WT) 2441 l ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~ ~ l 4 !I'!EP'J.7L R/ TING (CE ES %'E) 847.5 l NOTES l
- 5. I'!CIGil ELECTEICAL R/ TING (NET %'E) 788
- 6. L'/XI:4Ul.: DEPENDABLE CAPACITY (GROSS WE) 811
- 6. IT C.iAi;GE5 OCCUR IN C/FACITY hATIllG3 N/A (1TE+7 3 THROUGli 7) SINCE L/5T 1.EFJtC, GIVE REA5&i!5 9.1%'ER LEVEL TO LiiICE iiESTRICTED, IF ANY N/A
(:lET l&E)
- 50. RLA33,l5 F R RESTEIC: IONS, IF ANY N/A i
THIS V:l:TH Yh-T3-DATE CUMULAT1vE r
I
{
S1. E:URS II; 5EP RTING FERIOD 719.0 2B19.0 82007.0
- 22. i;Uh;hCi? 0F h3URS REACTGh L AS CEITICAL 666.0 2436.5 48471.0
- 13. Ei/CTDE RESERVE SEUTDNN EDURE 0.0 0.0 3731.5 b4. E UES G!l.ERATOR 2h-LiliE 626.0 2379.6 47454.4
- 25. U.IT RESEliVE SliU27)&n'N EGUE5 0.0 0.0 3736.2 b6. Gh ~55 :hERVA *, E/;ERGY GENERATED (.W'H) 1454960.8 5536037.3 109869303.7
- 17. GE255 FLECTi: CAL ENEhGY GENER/TED ('O'E) 465525.0 1751480.0 35570693.0 18.1;ET E*,ECTRICAL ENEhGY GENERATED (!&'E) 441210.0 1661732.0 3373S968.0
- 19. Ul.II SEl.VICE FACTJin 87.1 e/o 82.7 ele 57.9 e/o
- 20. Lt.IT AVAILABILITY FACTOR 87.1 */*
82.7 e/o 62.4 e/o
- 22. UNII CAFACI:Y FACT:n (USING DER NET) 77.9 */*
73.2 e/o 52.2 e/o
- 23. Lt.Il TGhCED GUTAGE RATE 12.9 */o 7.0 e/o 24.7 e/o
- 34. EEUTDWi;5 iCHEDULED OVEh ll EXT 6 M)l.'TES !.l ail:TENA:lCE 19 10 2D/.Y5 (2YP3,lVTE AND DUEATION GF EACE)
- 25. IF 5?iU2 D3di; AT El;D OF hEPORT PEFJ0D, EETI*tAST D/TE OF STAETUP i
- 26. UliITS IN TEST STATUS F&EECAST
/CliIEVED tPRIOR :: CGVYEECIAL OPER/TI:li)
INITIAL CTJTIC/IJTY I!;ITIAL ELECThICITY C7.:VEECIAL OFER/ TION
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. 1 GPEn*TP;G DAT/ EEFOR:
I L
D CKET N3. 50-281
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D/TE 06 "/Y 92
+
CCXP:ETED ?Y 2.,l. COSTE::0 1E:EFE2?;E 804-35? ' 184 CEEMTIl.G 3:A TU.~
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1. I?. I T il/ VE SUEEY U?iIT 2 3.1.EP:nTIisG PEEI:D 40182 70 43082
- 3. :1CEasiD IliEiGA: P:WEF (b'T) 2441 l
l
- 4. I:/*.lEPL/.TE RATIilC (CEOES 'AT) 842.5 l11:TE5 l
- 5. DESIGd iLEC' DICAL ElTIhG CNEI K T)
?86
- 6. h/2I-l# DEFE!!DABLE C/F/ CITY '.Gis:55 '4T) til i
?. *.'AXI'4d" DEP!7;DAHLE CAP / CITY (NET NE)
??5
?
- 8. IF CliANGES 3: CUE Ili CAE/ CITY itATIilG3 ll//
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\\IT?!3 2 TER:UGE ?) SI:!CE US:
1 1:LF.13"', GIVE ELAS h5 4
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- 10. l'i A5&l!S F E PEETEITTIONS, IF Ai;Y N/A l
THIS NONTE YE-T:-DATE Ci&lU:lTIVE
- 11. ECU3317! EEP ISI:lG PEEI:D
?19.C 28?9.0 7B8B?.0
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- 13. I:E/:T01. EEEEEVE E4UTDOW!i E UES 0.0 0.0 0.0 i
- 14. E:355 GiliER/.T F 2h-I!!E 618.9 2575.3 4EEe?.0
- 15. UhIT 3EEEE/E SEUTD:Wl: E:UES 0.0 0.0 0.0
- 17. G1.:53 ELECTEICA: E!!ERGY GENEi;ATED (W5) 446450.0 1801u00.0 35h?BS?9.0 i
16.1.E2 Ei.EC2EICA: EliEFGY GEiiEh2TED (WE) 422584.C 1696251.0 33624966.0
- 19. U?.IT 3Li.VICE FACT P B6.1 e/o 89.5 */o 59.2 e/o
- 20. UNIT AViID EILITY F/CTOR 86.1 e/o 89.5 */**
59.2 */*
- 21. b?.IT CA! CZ2I FiCT:I (CEIilG VDC NET) 75.8 e/o 76.0 e/o 55.C e/o
- 22. U'iTI CAPACITY F/CT&i: (UEING DEE NET)
?4.6 e/o
?4.B e/o 54.1 e/o
- 23. Uf;II E&i.CD CUTAGi EATE 13.9 e/o 5.8 e/o 16.? e/o
- 24. SizUiD:rl.i 5CHEDULED DVEF. l: EXT 6 XGhTES 3FEING MAIUTE!lANCE 14-82 10 days.
(TXPE,PAIE.AND DIEATIDE OF EACli) i
- 25. 71 5:iUT D:,.7: AT END lF REPOET PEEIOD, FE7I.! ATE DATE OF STA. CUP
- 36. U::IT3 IN TEST STATUS FORECAST ACHIEVED (PRI 2 T C:M:EECI/: CPERATION)
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I!;ITIA: CEITICA:ITY l
IliITIA: E*ECTEICITY C&.:XEFCIAL lFE.GATI:li i
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.m DOCKET NO.
50-280 I
UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT NAME Surry 1 DATE. 05-06-82 Apr il, 1982 COMPLETED BY Vivi an H. Jones TELEPHONE (804) 357-3184 ext. 477 REPORT MONT11
~k E"L IE 3
.h Eh Licensee E.t Cause & Corrective No.
Date h
3g g
jg5 Event 5i b
Action to
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E
$E 5
jgg Report *r vi0 0
Preveni Recurrence
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f 82-8 04-09-82 S
0.0 F
4 Reduced power to allow securing "A" mai n feedwa ter pump to reduce "A" reserve station service transformer i
load durin unit 2 startup.
82-9 04-12-82 F
0.0 A
4 Operator reduced power to stabilize the unit following loss of the high O'
pressure heater drain pump.
82-10 04-li-82 F
24.8 A
3 Loss of "A" RCP caused a reactor trip on low flow and a high steam flow -
Ic
- T and SI.
The electrical ave problem was corrected prior to s ta r t-up.,
j 82-11 04-14-82 F
7.2 H
3 The ' reactor tripped on a header to i
line steam 'ressure differential p
s ignal.
The Sl was caused by a spurious vibration induced header pressure 4
I 2
3 signal
- F: Forced Reason:
Method:
Exhibit G. instructions.
S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparailun of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examinathm F Administrative 5
G-Operational Error (Explain)
Eshibit I.Same Sourte.
19/77)
Il Other (Explain)
m t
m 50-280 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT N AME D "" Y '
DATE 05-06-82 REPORT MONT11 Apr i l, 1982 COMPLETED BY VIvian H Innos TELEPHONE (504) 357-3154 ext. 477
!E 3
$h Licensee Eg Cause & Corrective No.
Date g
3g 25&
Eveni g'i2 Action to 8-yE E
y ;f, c Report #
=> U Prevent Recurrence o
O c5 82-12 04-15-82 F
13.7 A
3 The reactor tripped on a low level in "C" S/G coincident with a feed flow - steam flow mismatch.
It was later discovered the " feedback arra" on the "C" main feed flow control valve was broken, s
82-13 04-15-82 F
11.7 H
3 The reactor tripped on a header to f
I Ine steam pressure di f fe. rent tal pressure s ignal. All associated pressure transmitters and circuitry was checked prior to startup.
82-14 04-16-82 F
7.4 A
3 The reactor tripped on a low - low level in "C" S/G..The broken " feed-back arnf' on the main feed flow control valve was discovered and
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repaired following this trip.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G. Instructhms S: Scheduled A-Equipment Failure (Explain) l-Manual for Preparation of Data B Maintenance or Test 2 Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automalic Scram.
Event Report (LER) File (NUREG.
D-Regulatory Restriction 4-Ot her (Explain) 0161)
E-Operator Training A License Examination F-Ailminist rative 5
G-Operational Error (Explain)
Exhibit I. Same Source.
(9/77)
Il-Other (Explain)
m m
n 50-280 UNIT SilOTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME surry 1 DATE 09-06-87 April, 1982 COMPT.ETED BY - Vivian H es REPORT MONTil TELEPHONE
( 8 01 ) $$7-31 4
5 j
jE 3
y Y3 Licensee
.Eg Cause A Corrective No.
Date
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3g i
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Event g'g Eb
^ ' " " " ' "
F fE 5
j 5, Report sr wU Prevent Recurrence g
c5 82-15 04-16-82 F
17.8 G
3 The reactor tripped on "C" S/G low, level coincident with a feed flow -
s t eam f low mi sma tc h s ig na l wh i l e feeding the S/G's in manual.
82-16 04-25-82 F
8.5 A
3 The reactor tripped on a low low level in "C" S/G when the main feed flow control valve failed closed.
T The diaphragm on the pneumat Ic opera-tor was replaced pricr to startup.
82-17 04-25-82 F
1.9 G
3 The' reactor tripped on an intermedial e range neutron detector high flux signal because the operator failed tc block this trip at 10% power. The operator was counseled regarding the failure to block the trip as required.
I 2
3 4-F: Forced Reason:
Method:
Exhibit G-Instrue:I ms S: Scheduled A. Equipment Failure (Explain) l-Manual for Preparation oI Data B Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C. Refueling 3-Automatic Scram.
Event Report (LER) Tile (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & IJcense Examination F. Administrative 5
G Operational Error (Explain)
Exhibit I Same Source 19/77)
Il-Other (E xplain)
e m
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50-281 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME durry 2 DATE 05-06-82 Apr.11, 198 2 COMPLETED gy V i v i a n 11. Jones REPORT MONT11 TELErtlONE (804) 357-3184 ext. 477 3
3 Licensee Eg b.
5_ ?
3 h $h Cause & Corrective b
No.
Date g
3g g
jg5 Event g?
l Action to fU H
$5 5
jgg Report #
mU Prevent Recurrence b
82-22 04-03-82 S
- 0. 0 A
4 J
Reduced power to a llow secur ing "B" main feedwater purnp for seal repairs.
82-23 04-04-82 S
0.0 A
4 Rednced power to allow secur Ing "B" ma. n feedwa t er pump fo r s ea l r epa i rs.
i 82-24 04-06-82 F
100.1 A
1 Reactor shutdown due to 1 GPli uni-i solable reactor coolant It akage throu.
ph valve packing. Valve was repacked
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prfor to unit recovery.
82-25 04-13-82 F
0.0 A
4 Turbine runback on spurious dropped rod signal caused by' loss of both s
auto tie transformers in the switch-ysrd.
Auto tie transformers were repa Ired,ar.d ' returned, to service.
I I
2 3
4 F: Forced Reason:
Method:
Exhibit G. Instructions -
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data
)
B. Maintenance or Test 2 Manual Scram.
Entry Sheets for Licemce c Refueling 3-Automatic Scram.
Event ReporI(LER) File (NUREG-D. Regulatory Restriction 4-Ot her (Explain) 0161)
)
E-Operator Training & License Examination F Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source t9/77)
Il-Other (Explain) i
-7 i
LOAD REDUCTIONS DUE TO ENVIRONFENTAL RESTRICTIONS
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April, 1982 I
UNIT NO.1 MONTH:
i
,l DATE TI!E HOURS LOAD. }N REDUCTIONS, IM MWH REASON I
4 NONE DURI NG TH IS REPORTING PERIOD.
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4 t
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e 4
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MONTHLY TOTAL
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5
.e e.
...-n e
n.
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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: Apri1, 1982 REASON DATE TI!E HOURS LOAD. MW REDUCTIONS. MW MWH f
d i
i 1
l l
1 i
NONE DURING THIS REPORTING PERIOD.
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i MONTHLY TOTAL i
DOCKET NO 53-280 UNIT SURRY I DATE 5-1-82
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COMPLET D BY 0,1 COSTELLO AVERAGE DAILY UNIT PadER LWEL YJ7TH: APRIL 82 AVERAGE DAILY POWER LEVEL AVERAGE DAILY P%TR LEVEL
. DAY (NJE-NET)
DAY (NVE-NET) 1 742.1 16 0.3 2
743.0 17 340.1 3
741.6 18 710.0 4
739.8 19 732.9 5
743.8 20 731.3 6
739.4 21 730.9 7
728.5 22 730.2 9
734.1 23 732.3
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9 620.5 24 731.7 10 613.0 25 247.8 11 741.5 26 605.0 12 734.0 27 734.0 13 529.6 28 736.4 14 0.0 29 733.9 15 0.7 30 735.5 DAILY UNIT P0 DER LEVEL FOR4 INSTRUCTIONS ON THIS FORs!, LIST TiiE AVEhAGE DAILY UNIT PSTR LEVEL IN MVE-NET FOR EACH DAY IN THE REP 0 ICING XONTH. TiiESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-IVC P.* NTH. NOTE THAT BY USING MAXIMUV DEPENDABLE CAPACITY FOR TliE NET ELECTRICAL RATING OF ThE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEDS ZHE 100 =/* LINE (Oh THE RESTRICTED PXTR LEVEL LYNE). IN SIEH CASES, THE AVERAGE DAILY UVIT E0VER QUTPUT SiiEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANGWLY.
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i DOCKET NO 50-281 UNIT SURRY II DATE 5-1-82 COMPLETED BY 0 J COSTELLO
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AVERACE DAILY UNIT POWER LEVEL MONTE: APRIL 82 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET)
DAY
(%T-NET) 1 697.9 16 621.8 2
698.5 17 701.2 3
681.5 18 702.1 4
530.7 19 701.3 5
698.2 20 701.6 6
94.6 21 702.5 7
0.0 22 702.1 8
0.0 23 702.3
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9 0.0 24 701.7 10 307.7 25 673.3 11 699.1 26 703.8 12 700.6 27 702.1 13 677.8 28 703.0 14 699.3 29 701.7 15 698.9 30 702.3 i,
DAILY UNIT POWER LEVEL FOM INSTRUCTIONS ON THIS F2la. LIST THE AVERAGE DAILY UNIT POWER EVEL IN MWE-NET FOR EACE DAY IN ThE EEPOR'ING MONTE. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING NONTH. KOTE TiiAT EY USING NAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF TEE UNIT. THEhE MAY BE CCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 e/* LINE (OR THE RESTRICTED POWER LEVEL LTNE). IN SUCH CASES. THE AVERAGE DAILY UNIT HJER CUTPUT SHEET SHOULD BE FOOTNOTED TO UPLAIN THE APPARENT ANOMALY,
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f-1 4
SUMMARY
OF OPERATING EXPERIENCE APRIL, 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 April 1 This reporting period begins with the unit at 100% power.
April 9 0940 - Started reducing power to allow securing the "A"
main feed pump to reduce the "A" Reserve Station Service Transformer load to less than 2000 amps.
1123 - Stopped reducing power at 73% and secured the "A" MFP.
April 10 1032 - Started the "A" MFP.
1035 - Started increasing power at 3% per hour.
4 1950 - The unit is at 100% power.
April 12 0331 - The High Pressure Drain Pump tripped on a low level signal. The control room operator reduced reactor power /
turbine power to 89%/710 MWe and stablilized the unit.
0414 - The H.P.D.P. was restarted and a power increase started.
0718 - The unit is at 100% power.
April 13 1710 - The reactor tripped on "A" reactor coolant loop low flow signal and safety injected on a high steam flow coincident with low T signal. This occurred as a result of the failure of a light $ning arrestor on the No. 2 Autotie transformer. The loss of the No. 2 Autotie transformer and the subsequent loss of the No. 1 Autotie transformer on the resulting fault current caused the 34.5 KV Bus to transfer to No. 4 transformer.
During this transfer the "A" Reactor Coolant Pump trippad resulting in the low "A" loop reactor coolant flow signal and subsequent high steam flow-low T, SI signal.
April 14 1043 - The "A" RCP was started following restoration of the No.
2 Autotie transformer and the 34.5 KV bus normal power supply.
1021 - The reactor was critical.
1758 - The generator was placed on the line.
SUMMARY
OF OPERATING EXPERIENCE APRIL, 1982 (continued)
UNIT ONE 1759 - The reactor tripped and the unit safety injected on a steam header to line differential pressure signal. The cause of the SI signal was believed to be vibration of the steam header pressure transmitter induced by steam line vibration.
2255 - The reactor was critical.
April 15 0110 - The generator was placed on the line.
0200 - The reactor tripped on a "C" steam generator low level 1
coincident with a feed flow-steam flow mismatch signal while feeding the S/G's in manual following the synchronization of the main generator.
1105 - The reactor was critical.
t 1539 - The generator was placed on the line.
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1540 - The reactor tripped and the unit Safety injected on a steam header to line differential pressure signal. This SI was almost identical to the SI on April 14.
All circuits and signals were calibrated and verified to be satisfactory. Additional instrumentation was installed to record steam pressure and valve movement during startup.
April 16 0041 - The reactor was critical.
0325,- The generator was placed on the line.
0335 - The reactor tripped on a low-low level in "C" S/G while feeding in manual following synchronization of the main generator.
Subsequent investigation revealed the " feedback arm" on the main feed flow control valve controller had broken off. This rendered the valve inoperable and was responsible for the S/G low level.
0420 - The reactor was critical.
1101 - The generator was placed on the line.
1109 - The reactor tripped on a "C" S/G low level coincident with a feed flow-steam flow mismatch signal while feeding the S/G's in manual following synchronization of the generator.
1432 - The reactor was critical.
April 17 0500 - The generator was placed on the line.
0545 - The feed flow control system and turbine control systems were in auto and power increase continued at 3% per hour.
I
SUMMARY
OF OPERATING EXPERIENCE APRIL, 1982
(
(con tinued)
UNIT ONE 1730 - A fire was reported in the refurbishing building. The fi re brigade responded to the fi re.
Due to the apparent magnitude of the fire outside assistance was requested from the local volunteer fire department. The local volunteer fire departmen t responded.
1757 - The fi re was declared 'out.
The refurbishing building is as Tsolated building and at no time did the fire pose any
~
threat to any other building.
April 18 0730 - The unit i s a t 100% power.
1745 - An unplanned release of radioactive gas occurred as a result of a leaking relief valve. The leaking relief valve was isolated and repaired.
April 25 0655 - The reactor tripped on a "C" S/G low-iow level signal when the main feed flow control valve f ailed closed. The cause of the failure was a hole in the pneumatic operator diaphragm.
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1303 - The reactor was critical.
1523 - The generator was placed on the line.
1526 - The reactor tripped on an intermediate range neutron detector high flux signal because the operator failed to block this trip af ter reaching 10% power.
1600 - The reactor was critical.
1720 - The generator was placed on the line.
1804 - The power increase was stopped at 35% to verify secondary chemist ry within specifi cations.
1810 - The secondary chemistry was verified in specification and a power increase at 3% per hour started.
April 26 1559 - The uni t is at 100% power.
April 30 This reporting period ends with the unit at 100% power.
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_14_
SUMMARY
OF OPERATING EXPERIENCE APRIL, 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 TWO April 1 This reporting period begins with the unit at 95% power and limited to 740 MWe because the SA and 6A Feedwater Heaters are bypassed.
April 3 2055 - Started decreasing power to allow securing "B" Main Feedwater Pump for maintenance.
2316 - Stopped decreasing power at 70% and stopped "B" MFP.
April 4 0613 - Started "B" MFP following maintenance.
0615 - Started increasing power.
0720 - Stopped power increase at 86% to evaluate continued seal leakage on the "B" MFP.
0843 - Started decreasing power to allow securing "B" MFP for maintenance.
0947 - Stopped decreasing power at 69%/550 MWe.
1009 - Stopped "B" MFP for maintenance.
1 2000 - Started "B" MFP following maintenance.
2031 - Started increasing power.
2234 - Stopped power increase at 96%/740 MWe.
April 6
_0001 - Started reducing power for unit shutdown due to greater than 1.0 BPM unisolable reactor coolant system leakage. The leak was thru the packit.g gland on a valve.
0532 - The generator was taken off the line.
0549 - The reactor is shutdown.
0820 - Started cooldown and depressurization of the reactor coolant system (RCS).
1601 - The RCS temperature and pressure were less than 350*F and 450 PSIG respectively.
2134 - The unit was at cold shutdown (RCS temperature 200*F).
SUMMARY
OF OPERATING EXPERIENCE
(.
APRI L, 1982 (continued)
UNIT TWO April 8 1715 - The uni t exceeded 200 F RCS temperature.
2217 - The RCS exceeded 350 F/450 PSIG.
April 9 0535 - The unit was at hot shutdown.
1034 - The reactor was critical.
April 10 0940 - The generator was placed on the line.
2000 - 5 topped increasing power at 97%/740 MWe.
April 13 1710 - The turbine ranback on a spurious dropped rod signal as a result of an electrical voltage spike on excore neutron detector N-44.
The electrical volatge spike was a result of the loss of No. I and No. 2 Auto tie Transformers in the switchyard. The unit was stabilized at 69% power.
1816 - Started increasing power.
2100 - Stopped power increase at 95%/740 MWe.
April 16 1036 - Started decreasing power to allow securing "B" MFP for maintenance.
1145 - Stopped power decrease at 70%.
i 1157 - Stopped "B" MFP for mbintenance.
1920 - Started "B" MFP following neintenancs.
1926 - Started increasing power.
2110 - Stopped power increase at 97%/740 MWe.
April 30 This reporting period ends with the unit at 97%/ power at 740 MWe.
4 e
i
? AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l
APRIL, 1982
!(
The Nuclear Regulatory Commission, on March 25, 1982, issued Amendment Nos. 75 and 76 to the Operating License for Surry Power Station Unit Nos. I and 2 respectively. The changes have been
~
designated as Technical Specification change No. 85 l
These amendments revise the Technical Specifications to change the frequency of calibrating seismic instrumentation from semi-annual to each refueling.
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. 75, are hereby incorporated in the license. The licensee sh'all 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. 76, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical
(
Specifications."
The Nuclear Regulatory Commission, on March 25, 1982, issued Amendment Nos. 76 and 77 to the Operating License for Surry Power Station Unit Nos. I and 2 respectively. The changes have been designated as Technical Specification change No. 86.
These amendments revise the Technical Specifications to permit startup following shutdown, with the reactor coolant's specific activitygreaterthan1.0yCi/ccDOSEEQUIVALENTl-131,toaccomodate iodine spiking.
Please also note the additional reporting requirement associated with this change on page TS3.1-15a.
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. 76, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci f i ca t ions."
(Unit 2) "B.
Technical Specifications
(
The Technical Specifications contained in Appendix A, as revised through Amendment No. 77, are hereby incorporated in the license. The Ilcensee shall operate the facility in accordance with the Technical Specifications."
FACILITY CHANGES REQUIRING NRC MPPROVAL APRI L, 1982
(
NONE DURING THIS REPORTING PERIOD.
FACI LITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL AP R i t, 1982 Unit DC 80-67 Vent and Drain System Conta inment isolat ion Valves 1
i This design change replaced the teflon seats in the trip valves with ethylene propylene seats. The drain ball valves containing teflon were replaced with dia-phragm valves containing ethylene propylene rubber d ia phragms. The trip valves and drain valves are qualified to the 40 year normal plus post-accident integrated radiation doses (using NUREG-0578 source terms).
SUMMARY
OF SAFETY ANALYSI S
~
This modification upgrades the valves or material used
(.
In the valves, i t doesnot af fect station operation or the operation of the valves. This change increases the reallability of the Isolation valves under accident conditions.
DC 81-11 Modification of instrument Air Compressor Unit 1-1A-C-3A & 3B 1&2 This design change modifies the starting circuitry to the vacuum priming house instrument air compressor.
Before the modification, both compressors operated at the same time.
Now one compressor runs during normal bperation and the other compressor is in stand-by for back-up.
SUMMARY
OF SAFETY ANALYSIS This modification does not affect the station operation or the operation of any safety related equipment.
It increases the efficiency of the Instrument Air Compressor.
(
. i TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL
(
APRIL, 1982 None during this reporting period.
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL april, 1982 None during this reporting period.
OTHER CHANGES, TESTS AND EXPERIMENTS APRIL, 1982 None during this reporting period.
I.
l.
(
1 l
~O-y5p 2 O E SURRY P0kTR STATION
~
CHEMISTRY REPORT
(
April
, 19 82 T.S.6.6.3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO.
2 (B)
ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAG (A)
(A)
E-1 E-2 E-Gross Radioact., UCi/ml 3.94 3.20 2.48 3.28 3.80 y,79 Suspended Solids, ppm 0.1 0.1 0.1 0.1 0.1 0.1 E-1
-1 E-1 E-2 Gross Tritium, UCi/mi 1,37 4.73 -
1.10 1.33 6.75 9.98 -
IA)
(A)
E-Iodine-131, pC1/ml 5.14 8.48 1.05 3.33 3.07 -
6.86 I-131/I-133 1.3485(A) 0.6000 0.8983 (A) 2.2200
.4520 1.0536 Hydrogen, cc/kg (C) 49.5 32.7 37.4 48.0 25.9 35.6 Lithium, ppm 1.08
.40 (A)
.76 1.40
.79 1.08 Boron-1C, ppm +
195.8 110.7 125.3 302.6 156.0 179,0 Oxygen-16, ppm
.000
.000
.000
.000
.000
.00C Chloride, ppm
<.05
<.05
<.05
<.05
<.05
<.05 pH 0 25*C 6.81 6.31 6.62 6.61 5.83 6.45
+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (D) l RELEASES, POUNDS T. S. 4.13. A. 6, l
Phosphate Baron 1027 Sulfate Chromate
.14 50% NaOH Chlorine Remarks: A) Values reflect RX trips on: 4-13-82 1715. 4-15-82 0200; 4-15-82 1540; 1
4-16-82 0335: 4-16-82 1110: 4-25-82 0655: 4-25-82 1530: (B) Unit 2 rampdown for leak in A-loop RTD by-pass line to 0% Pwr 4-6-82 @ 0600, back on line 4-10-82 (C) Hydrogen values
(
do not reflect degassing (D) These levels of chemicals are not hazardous to the environment.
April, 1982 DESCRIPTION OF ALL INSTANCES WHERE
(
THERMAL DISCHARGE LiMI TS WERE EXCEEDED
~
Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.
April 1, 1982 Exceeded 17.5 F AT across station 2
Exceeded 17.5 F AT across station 3
Exceeded 17.5 F AT across station 4
Exceeded 15 F AT across station
- 5 Exceeded 17.5 F AT across station 6
Exceeded 17.5 F AT across station 10 Exceeded 15 F AT across station
- 11 Exceeded 15 F AT across station 12 Exceeded 15 F AT across station
(
13 Exceeded 15 F AT across station
- 17 Exceeded 15 F AT across station
- 18 Exceeded 15 F AT across station 19 Exceeded 15 F AT acorss station 20 Exceeded 15 F AT across station 21 Exceeded 15 F AT across station 22 Exceeded 15 F AT across station 23 Exceeded 17.5 F AT across sta tion 24 Exceeded 17.5 F AT across station 25 Exceeded 17.5 F AT across sta tion
- 26 Exceeded 15 F AT across station
- 27 Exceeded 15 F AT across station l
28 Exceeded 17.5 F AT across station
(
29 Exceeded 15
% AT across station 30 Exceeded 15 F AT across station
- lndicates dates where station AT was less than or equal to g
(
15.0 F across station for some time during the day.
Tt e AT excussions were allowable under Technical Specification 4.14.B.2.
There were no reported instances of adverse environ 4ent impa ct.
The temperature change at the station discharge exceeded 3 F per hour on the following dates and for the noted reasons:
On April 13, 1982, due to a Unit I reactor trip; and on April 25, 1982 due to a Unit I reactor trip.
These events were allowable in accordance with Technical Specification 4.14.B.I. There were no reported instances of adverse environmental impact.
The temperature change at the station discharge exceeded 3 F per hour on April 3,1982, due to a rapid increase in circulating water flow through Unit I and Unit 2 main condensors. This event was reported in accordance with Technical Specification 4.14.C.1.
(
l
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l 1
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.o FUEL HANDLING l
APRIL, 1982
(,
UNITS ONE AND TWO None during this reporting period.
e
PROCEDURE REV1SIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR
(
APRIL, 1982 None during this reporting period.
O w_------- - -- - - -, - --- ------ - - -------- -,. _ - ~----_-
-23a-DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS
(_
APRIL, 1982 e
None during this reporting period.
9 i
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1
_24 INSERVICE INSPECTION APRIL, 1982 UNITS ONE AND TWO None during this reporting period.
M REPORTABLE OCCURENCES PERTAINING TO ANY OUTAGE OR POWER REDUCTIONS 1- [
APRIL, 1982
\\
None during this reporting period.
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There was no single release of radioactivity or radiation, exposure specifically associated with an outage that accounted for mo,re than 10%
of the allowable annual values in 10CFR20.
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(
APRIL, 1982 Date'SNSOC Procedure No.
Unit Title Date Deviated Reviewed OP-1B 2
Containment Checklist 03-03-82 04-20-82 OP-1E 2
Containment integrity Checklist 03-03-82 04-20-82 e
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