ML20054L865

Monthly Operating Repts for May 1982

ML20054L865
Person / Time
Site:	Surry
Issue date:	06/15/1982
From:	Jones V VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20054L862	List: ML20054L861 ML20054L865 ML20054L867
References
NUDOCS 8207090018
Download: ML20054L865 (47)

Text

4 e

4 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 82-05 MAY, 1982 APPROVED BY:

d .5 A STATION MANAGER 1

l l

t 1

o!h00fjg PDR

. o i

Section Page 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 4,5 Load Reductions Due to Environmental Restrictions - Unit #1 6 Load Reductions Due to EnvironmentaI Restrictions - Unit #2 7 Average Daily Unit Power Level - Unit #1 8 Average Daily Unit Power Level - Unit #2 ,

9 Summary of Operating Experience 10-12 Amendments to ' Facility License or Technical Specifications 13 Facility Changes Requiring NRC Ipproval ik Facility Changes That Did Not Require NRC Approval 14-16a Tests and Experiments Requiring NR'C Approval 17 Tests and Experiments That Did Not Require NRC Approval 17 Other Changes, Tests and Experiments ,

17 Chemistry Report 18 Description of All Instances Where Thermal Discharge Limits Were Exceeded .

19 Fuel Handling 20,21 Procedure Revisions That Changed the Operating Mode Described in the FSAR 22 l

Description of Periodic Tests Which Were Not Completed Within the l

Time Limits Specified in Technical Speci'fications 23 Inservice Inspection 24 I

i 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 27 Maintenance of Saf ety Related Systems,During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 29-31 l

I

Section _P.afd Maintenance of Safety Related Systems During Outage or Reduced Pcwer Periods - Unit #1 - Electrical Maintenance 34 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 35,36 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 38 Maintensuce of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 40 Health Physics Summary 41 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee af ter Time Limits Specified in T. S. 42 b

O I

i l

l I

1 OPERATING DATA REPORT DOCKET NO. 50-280 DATE 08 JUN 82 COMPETED BY Vivian H. Jones ~

TELEPHONE 80s-357-3184 CPERATING STATUS

1. UNIT NAME SURRI UNIT 1

2. REPORTING PERIOD 50182 70 53182

3. IJCESSED TiiERMAL POWER (WT) 2441 l l

4. NAMEPUTE RATING (GROSS WE) 847.5 l NOTES l l 5. DESIGH ELECTRICAL RATING (NET WE) 788

6. NAXIMUN EEPENDABLE CAPACITX (GROSS WE) 811

7. MAXIMUM EEPENDABLE CAPACITY (NET WE) 775

8. IF CliANCES OCCUR IN CAPACITX RATINGS N/A (ITEMS 3 ZiiROUGE 7) SINCE UST REPORT, CIVE REASONS l

i 1 9. PC*'ER LEYEL TO WHICli RESTRICTED, IF ANZ N/A

.l ( AET WE) f 10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH 1R-TO-DATE CUMUM TIVE

11. ECURS Ib REPORTING PERIOD 744.0 3623.0 82751.0

'l 12. NUMBER OF iiOURS REACTOR WAS CRITICAL 744.0 3180.5 49215.0 3731.5

13. REA0 TOR RESERVE SixUTDOWN BOURS 0.0 0.0

14. iiGURS GENERATOR ON-LINE 744.0 3123.6 48198.4

15. UNIT RESERVE SiiUTDOWN iiGURS 0.0 0.0 3736.2

16. GROSS TiiERNAL ENERGY GENERATED (Wii) 1815949.3 1351986.6 111685253.0

17. GROSS ELECTRICAL ENERGY GENERATED (Wii) 573135.0 2324615.0 36143828.0

18. NET ELECTRICAL ENERGY GENERATED (WE) 543096.0 2204828.0 34282064.0

19. UNIT SERVICE FACTOR 100.0 */* 86.2 */* 58.2 */*

20. UNIT AVAIUBIZZTY FACT 0h 100.0 */* 86.2 */* 62.8 */*

21. UNIT CAPACITY FACTOR (USING MDC NET) 94.2 */* 78.5 */* 53.5 */*

32. UNIT CAPACITY FACTOR (USING DER NET) 92.6 */* 17.2 */* 52.6 */*

23. UNIT FORCED OUTAGE RATE 0.0 */* 5.5 */* 24.4 */*

24. SiiUTDOWNS SCHEDU2D OVER NEXT 6 MONTiiS MAINTENANCE 19 10 $ DAYS (TYPE,DATE,AND DURATION OF EACli)

- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATE DATE OF STARTUP

26. UNITS H TEST STATUS FORECAST ACHIEVED (FRIOR 10 CON 4EiCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COM4ERCIAL OPERATION

2 OPERATING DATA REPORT COCKET NO. 50-281 DATE 08 JUN 82 CONPLETED BY _Vivian H. Jones.

TEMPRONE 804-357-3184 OPERATIhG STATUS

1. UNIT NARE SURRY UNTT 2

2. REPORTING PERIOD 50182 TO 53182

3. LTCENSED TiiERNAL POWER (WT) 2441 l l

4. NAMEPLATE RATING (GROSS WE) 847.5 l NOTES l

5. DESIGN ELECTRICAL RATING (NET W E) 788

6. NAXIMUM DEPENDAB M CAPACITY (GROSS W E) 811

7. NAXIMUM EEPENDABLE CAPACITY (NET WE) 175

8. IF CliANOES OCCUR IN CAPACITY RATINGS N/A (ITEVS 3 TiiROUGli 7) SINCE LAST REPORT, GIVE REASONS

9. POWER LEVEL TO WiiICH RESTRICTEC, IF ANY N/A (KET WE)

10. REASONS FOR RESTRICTIONS. IF ANY N/A TiiIS MONTil YR-TO-DATE CUMJ'LATIVE

11. iiGURS IN REPORTING PERIOD 744.0 3623.0 79631.0

18. NUMBER OF ROURS REACTOR WAS CRITICAL 432.6 3068.1 47928.8

13. REACTOR RESERVE SiiUTDOWN iiGURS 0.0 0.0 0.0 14.110URS GENERATOR ON-LTNE 421.9 2997.2 47108.9

15. UNIT RESERVE SiiUTDOWN ROURS 0.0 0.0 0.0

16. GROSS TEERNAL ENERGY GENERATED (Wii) 937566.3 6556020.3 109853306.2

17. GROSS ELECTRICAL ENERGY GENERATED (WR) 298535.0 2099935.0 35717114.0

18. NET ELECTRICAL ENERGY GENERATED (WR) 282298.0 1978549.0 33907264.0

19. UNIT SERVICE FACTOR 56.7 e/* 82.7 */* 59.2 */*

20. UNIT AVAILABILITY FACTOR 56.7 e/o 82.7 */* 59.2 e/o

21. UNIT CAPACITY FACTOR (USING MDC NET) 49.0 */* 10.5 */* 54.9 */*

22. UNIT CAFACITY FACTOR (USING DER NET) 48.2 e/o 69.3 */* 54.0 e/*

23. UNIT FORCED OUTAGC RATE 3.3 */* 5.4 */* 16.6 */*

24. SiiUTD0iikS SCliEDUGD OVER NEXT 6 MONTiiS Fall NAINTENANCE-10-01 10 Days (TYPS,DATE AND DURATION OF EACB)

25. IF SiiUT DOWN AT END OF REPORT PEREOD,

- ESTINATE DATE OF STARTUP

26. UNITS IN TEST STATUS FORECAST ACliIEVED (PRIOR 70 COMERCIAL GPERATION)

INEZIAL CRITICALITY INITIAL EGCTRICITY COMMERCIAL GPERATION

I DOCKET NO. 50-280 UNITSIlUTDOWNS ANI) POWER REDUCTIONS UNIT NAME Surry 1 DATE 06-04-82 COMPLETED sy VIvian Jones REPORT MONTil May 82 TELEPilONE 80k-197-31 R4 rut. 477 "h -

c ._ c. 3: .

Cause & Corrective

.  ;, .E e E EM j2g5 LI"5

Event 5 *.,

ET g{'8 Action to No. Date g 3g g 97 0 0 Prevent Recurrence Repent #

" c5 E E j 6. j 6

1 1

w NONE DURING THES RI PORTl 4G PERl')D.

4 3

I 2 Method: Exhibit G-Instructitms F: Forced Reason: for Preparation uI Data l-Manual 5: ScheduleJ A. Equipment Failure (Explain) Entry Sheets for Licensee 2 Manual Scram. Event Report (LER) File (NUREG-B-Maintenance of Test 3 Automatic Scram.

C Refuelirrg .

4 Other iExplain) 01611 D Regulatory Restiiction I:-Operator Training A Ucense Examination 5 12 Administrative Eshibit I - Same Source '

G Oi vrational Error (Explain)

Il-Other (E xplain) , ,

19/77)

M

l l

I C TN UNIT SIluTDOWNS AND POWEK REDUCTIONS ur 2 -

l DATE 06-04-82 COMPl.ETED BY . VIvt an tan =

REPORT MONTil May 82 T El.ErilONE M- 3'i7-1184 Ext. 477

'a., Cause A Correceive

-, .]g 3 E Licensee ,E g -

Action to N. . D.n e c; 3g i .3 s y Eveni wU g? g3 u Pievent Recurrence H

fI e j y, Iteport a g -

0 ,

Reduced unit load / power in or 'er mo 0.0 A '

4 reseaf SV-SD-200.

82-26 5-9-82 F 82-27 5-10-82 F 0.0 A h . Saroe as above. .

0.0 A 4 i in Same as above. The safety valve us 8-28 5-13-82 F Isolated, rernoved and disassernbled.

,a The spring was .found to be broken causing the valve to malfunction.

~

N-8-29 5-15-82 5 307.7 8 3 Turbine trip-reacto'r trip by "B" S/G Hi-HI level while feeding in manual during power reduction for shutdown for scheduled spring maintenance outage .

t 4

3 I .' Method: Exhibit G Instructions l~: Forced Reason:

I-Manual for Preparation of Data S: Stheduled A. Equipment Failure (Explain) Entry Sheets for Licensee 2-Manual Scram.

D Maintenance of Test Event Report (LER) File it4UREG-C Refueling . 3 Auto.natic Scram.

4-Other (Explain) 016I1 D-Regulatory Resinicilon 1.-Operator Trainingit License Examination 5 F Administrative Eshibit I - Same Source G. Operational Essor (Explain) l'8/77) Il-Other (Explain)

e DOCKET NO.50-28i UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Surry 2 DATE 06-04-R7 COMPLETED BY Vivian Jones.

May 82

' REPORT MONill TELEPilONE 80h 'tC7-31RL r xt. 477 i

Cause & Currective

, iE 3 Y Licensee E3, o3 Action to No. Date i 5g i 2s& Event a3 viu @U Pievent Recurrence F

$E 5 3gc e  !

Report #

o c5 1

lla.4 A 3 Turbine trip-reactor trip by "C" S/G 82-30 5-28-82 F Hi-HI level while feeding S/G's in manual following Startup. "C" S/G feedwater flow control valve response was sluggish and the valve was exer-i -

vi cised several times prior to the next Startup.

o t

3 4 i 2 Method: Exhibit G Instructions f: Forced Reason: for Preparation ef Data A. Equipment Failure (Explain) I-Manual S: Scheduled 2-Manual Scram. Entry Sheets for Licensee D Maintenance of Test Event Report (LER) File INUREG-C. Refueling e 3 Autornatic Scraro.

4 Other (Explain) 0161)

D. Regulatory Restriction E-Operator Training & Ucense Examination 5 F Administrative Eshibit I- Same Source G. Operational Error (Explain) l'8/77) Il Other (Explain) e

6 LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.1 MONTH: May 82 DATE TI!E HOURS LOAD, MW REDUCTIONS, MW MWH REASON NONE DURING THIS REPORTildG PERIOD.

O a

a O

e 8

e

=

MONTHLY TOTAL

7 LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESIRICTIONS UNIT NO.2 MONTH: Mav 82 DATE TI!E HOURS LOAD MW REDUCTIONS, MW MWH REASON NONE )URING THIS ItEPORTING PERIOD. s MONTHLY TOTAL

.,--4

8 DOCKET NC 50-280 UNIT SURRY I DATE 6-1-82 COMPLETED BI C J COSTELLO AVERAGE DAILY UNIT POWER LEVEL YONTh: NAY 82 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET) DAY (MWE-NET) 1 738.4 17 729.8 2 737.2 18 731.2 3 734.4 19 731.3 4 131.3 20 732.0 5 734.9 21 732.8 6 735.7 22 732.8 7 733.0 23 731.4 8 733.9 24 725.8 9 734.0 25 718.1 10 733.5 26 717.5 11 732.9 27 717.5 12 734.3 28 721.2 13 731.C 29 723.3 14 731.3 30 727.5 15 726.0 31 721.1 16 733.1 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS ON THIS EGhM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN TiiE hEPORIING MONTH. TiiESE FIGURES WILL BE USED 70 PLOT A GRAPii FOR EACE REPORT-ING NONZn. NOTE THAT BY USING MAXIMUN DEPENDABLE CAPACITY POR THE NET ELECTRICAL

, R ATIh G C F TiiE UNIT , THERE MAY BE OCCASIONS WiiEN TiiE DAILY AVERAGE POWER EXCEEDS THE 100 */* LINE (CR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER CUTPUT SHEET Sn0ULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

l 9 DOCKET NC- 50-281 UNIT SURRY II -

DATE 6-1-82 ,

COMPLETED BY 0 J COSTELLO AVERAGE DAILY UNIT POWER LEVEL l

MOKYHs MAY 82 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET) DAY (MWE-NET) 1 702'.8 17 0.0 2 702.1 18 0.0 3 700.8 19 0.0 4 700.7 20 0.0 5 699.8 21 0.0 6 699.5 22 0.0 7 701.5 23 0.0 8 703.1 24 0.0 9 693.9 25 0.0

~

10 693.3 26 0.0 11 688.5 27 0.0 12 701.2 28 72.5 13 681.2 29 490.6 14 676.9 30 703.3 15 48.0 31 703.1 16 0.0 DAILY UhII PCWER LEVEL FORM INSTRUCTIGNS CN THIS FCRM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN 75E REPORTING MONTE. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTn. ftCTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL h ATIh G OF TH E UNIT, THERE MAY BE CCCASIONS WHEN THE DAILY AVERAGE PGWER EXCEEDS THE 100 e/o LINE (CR THE RESTRICTED PGWER LEVEL LINE). IN SUCH CASES, THE AVERAGE CAILY UAI2 PGVER CUTPUT SHEET SHOULD BE FOOTNGTED TO EXPLAIN THE APPARENT ANOMALY.

l

i 10 l

l

SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR May. 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 May 1 This reporting period begins with the unit at 100% power.

May 31 This reporting period ends with the unit at 100% power.

UNIT TWO May 1 This reporting period begins with the unit at 96% power. The 5A and 6A Feedwater Heaters are isolated and bypassed due to tube leakage. This imposes a 740 MWe restriction on the unit.

May 9 1842-Safety valve SV-SD-200 on the drain line to the "1 A" Feedwater Heater li f ted. Uni t load / power was reduced to 710 MWe/92% in order to rescat it.

May 10 0045-The safety has been rescated and a power increase started.

0105-The uni t was at 740 MWe/92% power.

2015-SV-SD-200 lifted. Reduced load / power to 690 MWe/90% in order to rescat it.

May 11 0042-The safety has been rescated and a power increase started.

0103-Stcpped power increase at 720 MWe/92%.

I 1525-started power increase to 740 MWe.

1600-Stopped power increase at 740 MWe/96%.

May 13 1614-SV-SD-200 lif ted. Reduced load / power to 700 MWe/94% in order to isolate drain line to "1 A" FW.HTR.

1640-Lcad decreased to 650 MWe due to loss of efficiency when the drains to "1A" FW.HTR. and/the steam. to thel reheater section of "A" and "D" Moisture Separator Reheaters (MSR) was isolated.

1840-Started increasing power 1854-Stopped power increase at 665 MWe/93%.

1933-started increasing power.

I 1943-Stopped power increase at 680 MWe/96%.

2014-Started putting "A" and "D" MSR's in service.

11

SUMMARY

OF OPERATING EXPERIENCE PAGE 2 May 14 0425 "A" and "D" MSR's fully in service with load / power at 715 MWe/99%.

2232-Started reducing power for unit shutdcen for Spring maintenance outage.

May 15 0230-stopped power decrease at 35% for chemists to draw steam generator blowdown samples.

0330-Started power decrease.

0406-The reactor tripped on a turbine trip caused by a Hi-Hi level in "B" S/G. The Hi-HI level was the result of a malfunction in the feedwater flow control valve control system.

1100-The Reactor Coolant System (RCS) temperature / pressure was <350 F/

450 PSIG.

1645-The RCS temperature was 200 F.

May 22 2314-The RCS was filled and vented following primary system maintenance.

0 May 23 1325-The RCS temocrature exceeded 200 F.

May 24 0559-The RCS temperature / pressure exceeded 350 F/450 PSIG.

1928-A leak on the weld for 2-RC-159 (the channel head drain valve for "A" S/G) was identified on the 2335 PSIG overpressure walkdown.  ;

2145-Started cooldown af ter verifying RCS was borated to cold shutdown concen t ration.

0057-The RCS temperature / pressure was <3500 F/450 PSIG.

May 25 0513-The RCS temperature was <2000F.

May 26 1218-The RCS was filled and vented following repairs to the weld for 2-RC-159.

May 27 0010-The RCE temperature exceeded 200 F.

0443-The RCS temperature / pressure exceeded 350 F/450 PSIG.

1446-The reactor was critical. '

2350-The unit was placed on the line.

May 28 0005-The reactor tripped on a turbine trip caused by "C" S/G Hi-Hi level. The Hi-HI level was due to sluggish response of the feedwater flow control valve while feeding the S/G's in manual.

12

SUMMARY

OF OPERATING EXPERIENCE PAGE 3 0015-Received a "R6d Urgent Failure" alarm while withdrawing the shut-down banks. The Electrical Dept. Investigated and found a ground in the power cables to rods N-9 and G-13.

1219-The ground problem on the power cables to rods N-9 and G-13 has been corrected.

1246-The reactor was critical.

1429-The unit was placed on the 1ine.

1539-Stopped power increase at 35% to get steam generator cation conductivity in specification.

May 29 0718-S/G cation conductivity was within specification and a power increase was started.

0853-Received a "6B" FW HTR high level alarm. Decreased load / power to 500 MWe/70%.

1009-Started increasing power. Isolated SB s 6B Feedwater Heaters.

1400-Stopped increasing load / power at 740 MWe/97%.

May 31 This reporting period ends with the unit at 740 MWe/96% power with the "5B" and "6B" FW HTRS bypassed and Isolated.

t l

i l

l . _ . . _ _ _ _ _ _ _ _ _ _ _ _

13 l

I AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l May, 1982 The Nuclear Regulatory Connission, on April 27, 1982, issued Amendment Nos. 77 and 78 to the Operating License for Surry Power Station Unit Nos.1 and 2 respectively. The changes have been designated as Technical Specification i change No. 87 ,

These amendments revise the Technical Specifications related to the auxiliary feedwater systems. One change adds the requirement that at least one of the three auxiliary pumps be operable when the temperature and pressure of the opposite unit are. greater than 350 F and 450 psig, respectively. One change adds an action statement which requires at least three auxiliary pumps be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Other changes include a requirement for a source of water for the one auxiliary feedwater pump of the opposite unit, flow tests for all of the auxiliary feedwater pumps, and valve exercise tests for the oumo discharge valves.

Accordingly, the paragraph 3.B of the Operating License for Unit 1 and 2, resoectively, is amended as follows:

(Unit 1) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 77, are hereby incorporated in the IIcense. 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. 78, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."

i l

l

14 FACILITY CHANGES REQUIRING NRC APPROVAL MAY, 1982 l

l NONE DURING THIS REPORTING PERIOD.  ;

FACILITY CHANGES THAT DID NOT REQUI.E NRC APPROVAL MAY, 1982 unit DC 81-34 Emergency Diesel Generator Alarms Modifications 1&2 This design change separated the disabling and non-disabling annunciators associated with each diesel generator.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect the operation of the Emergency Diesel Generators or related equipment. Disabling and non-disabling condi-tions will alarm separately and be presented more clearly to the operator.

DC 82-18 Auxiliary Feedwater Motor Driven Pump Bypass 2 indication in order to satisfy the criteria established in i EEE 279-1971 Section 4.13, the Auxiliary Feedwater Motor Driven Pump Ci rcuit ry was modi-fled so that the green Indicating light located on the benchboard in the Main Control Room is on wbc5 the pumps are locked out. Also the Auxi'lary Feedwater Pump overload trip annun-clato. was modified to include a pump lockout condition.

SUMMARY

OF SAFETY ANALYSIS The implementation of the AFW motor drive pump bypass, indication package does not affect the operation of any safety-related equipment. It does provide the operator with Indication and alarm when the AFW motor driven pumps are locked out or taken out of service by placing pump control in the pull-to-lock position.

15 FAClLiTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL l

MAY , 1982 )

Uni t  ;

DC 80-33 RCP Snubber Vertical Support Column Modification 2 This design change modified existing vertical support columns on the 12" Reactor Coolant Pump Snubbers to incorporate spring hangers in an attempt to reduce scoring created by snubber dead weight and/or vertical support column.

SUMMARY

OF SAFETY ANALYSIS The niodification should reduce wear on the Reactor Coolant Pump Snubbers without affecting their function and operation.

DC 80-54 Charging Pump Lube 011 Cooler TCV Modification 2 This design change provides automatic temperature control of the charging pump lube oli systems. An air operated control valve was installed in the service water outlet of each lube oil cooler (three per unit).

A capillary type thermal elenent uns installed in the oil line which provides the signal to a pneunatic indicating temperature controller. Control air is supplied to the tenperature controller with the output signal operating the control valve.

SUMMARY

OF SAFETY ANALYSIS The modification enhances the reliability of the charging pump lube oil cooler service water system. Automatic temperature control of the charging pump lube oil system enhances safe and efficient operation during normal and post-accident opera tions.

DC 80-67 Vent and Drain System Containment isolation Valves 2 This design change replaced the teflon seats in the trip valves with ethylene propylene seats. The dra in ba ll valves containing teflon were replaced with diaphragm valves containing ethylene propylene rubber diaphragms.

The trip valves and drain valves are qualified to the 40 year normal plus post-accident integrated radiation doses (us ing NUREG-0578 source terms).

SUMMARY

OF SAFETY ANALYSIS This modification upgrades the valves or material used in the valves. It does not affect station operation or the operation of the valves. This change increases the reliability of the isolation valves under accident conditions.

16 FACI LiTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MAY, 1982 Unit DC 81-04 Pressurizer Heater Control Swit6h Indication 2 for the Pull to Lock Pos it ion This design change provides control switch light Indication when the Pressurizer Heater Switch is in the pull to lock position.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect station opera-tion or the operation (control circuitry) of the Pressurizer Heaters.

DC 81-46 RWST Narrow Range Level 'Honitoring System. 2 This design change replaced the existing non-safety related RWST level switches with a non-safety related RWST Narrow Range Level Monitoring System. The new system monitors the span Just below the dome bend line and the bottom of the overflow line. This change will aid i the operators in maintaining the RWST within Technical Specifica tions.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect system operations or the operation of the RWST. The margin of safety is increased by alerting the operator to a potential violation of the Technical Specifications.

DC 82-14 Prevention of Tripping Transfer Breaker 15El 2 This design change adds .a General Electric SAM Timer (device 62) in the trip circuit of transfer breaker 15E1. This will provide a time delay trip of 300 milliseconds if the normal feeder breaker 25H8 does not '

trip. If the normal feeder breaker does trip, normally open contacts of breaker 25H8 are put in i the time delay circuit to drop out the timer, allowing breaker 15El to remain closed.

I SUMMAP.Y OF SAFETY ANALYSIS This modif ica t ton increases the ava ilabili ty of electrical power for operation of station

. auxiliaries. I t does not affect the operation of any safety related equipment.

l

16a FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL 1

MAY, 1982 DC 82-16B Replacement SKV Electrical Penetrations This design change replaced 8 of the 9 existing penetrations with new Conax penetrations. The design of these replacement penetrations utilizes ceramic bushings at the pressure boundary and requires no compound. The lack of maintainability of the old connectors and the difficulty in pro-curement of replacement components resulted in the decision to replace the penetrations with those of a proven and qualified design.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect station operations or the operation of safety-related equipment. The replacement of the penetrations enhanses the con-tainment pressure boundary, as well as the operation of the Reactor Coolant Pumps and Residual Heat Removal Pumps.

l l

l l

l

17 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MAY, 1982 None during this reporting period.

TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MAY, 1982 None during this reporting period.

OTHER CHANGES, TESTS AND EXPERIMENTS MAY, 1982 None during this reporting period..

18

'SURRY POWER STATION CHEMISTRY REPORT May 19 82 T.S. 6.6.3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS '

MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAG (A) Eo [A) Eo (A) Eo' E-1 E-2 . E-Gross Radioact., UCi/ml 4.11 1.92 2.89 7.32 2.65 1.88 Suspended Solids, ppm 0.1 0.1 0.1 0.1 0.1 0.1 E-1 E-2 E-1 E-1 E-1 E-1 Gross Tritium, UCi/ml

~

2.16 4.37 1.19 1.83 1.66 1.75 (A) E-1 (A) E-1 (A) E-1 E-2 E-3 E-2 Iodine-131, UCi/ml 1.65 1.17 1.49 6.93 1.19 1.23 I-131/I-133 1.4602 0.7081 1.1056 2.0000 0.6970 1.0683 Hydrogen, cc/kg '3.9

+ 32.3 36.6 40.1 5.0 27.8 (B) .

Lithium, ppm 1.20 0.69 0.83 1.45 1.15 1.33 Baron-10, ppm + 109.96 96.82 103.18 376.G2 147.78 246.0 (D) (

Oxygen-16, ppm .000 .000 .000 5.5 .000 .27 Chloride, ppm <.05 <.05 <.05 <.05 <.05 <.05 pH @ 25"C 6'J83 6.59 6.67 6.61 5.84 6.26

+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (E)~

RELEASES, POUNDS T.S. 4.13.A.6 Phosphate - Boron 1660

+

y-3 Sulfate -

Chromate .28 50% NaOH -

Chlorine REMARKS: (A) Activity levels indicate possible failed fuel (B) Two separate Lithium Hydroxide sdditions made 5-17-82(780g) & 5-26-82(670g) (C) Hydrogen levels reflect decassinc of Rx #2 foi ehutdown (D) Oxygen levels reflect unit #2 cold shutdown for maintenance - unit #1-100% Rx power entire month - unit #2 Rx trip on rampdm.rn 5-15-82 @ 0410 - Rx critical 5-28-82 6 commenced power escalation (E) The levels of these chemicals should create no adverse environmental impact.

}

19 DESCRIPTION OF ALL INSTANCES WHERE THERMAL Di$ CHARGE LIMITS WERE EXCEEDED May 82 Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.

May 1, 1982 Exceeded 15 F AT across station 2 Exceeded 15 F AT across station 3 Exceeded 15 F A7 across station 4 Exceeded 15 F AT across station 5 Exceeded .15 F AT across station

• 6 Exceeded 15 F AT across station 7 Exceeded 15 F AT across station 8 Exceeded 17.5 F AT across station 9 Exceeded 15 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 14 Exceeded J7.5 F AT across station 15 Exceeded 15 F AT across station 29 Exceeded 17.5 F AT across station

• 30 Exceeded 15 F AT across station 31 Exceeded 17 5 F AT across station *

• Indicates dates where station AT was less than or equal to 15.0 F across station for some time during the day.

The AT excursions were allowable under Technical Specification 4.14.B.2.

There were no reported instances of adverse environmental impact.

20 Unit 1 MIy 82

1. .

FUEL HANDLING

??

DATE NO. OF ANSI NO. NEW OR SPENT FUEL SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LE' l i-l u

i s

l f-9_

lE MUM r. DUMI NLi IMib MtrUMi lMLi FLMlUU.

E .

b *

i. .

.4 i

'i h d A e._,

>T i

= -

e e

e S

4 e

.g e i

s w-. - - - , - - . ---, , ,+- . - - .w..----. - - . . - - - - , e- - - -

-m . - -

Unit 2 M'.y '82

'~ '

FUEL HANDLING Ih DATE NO. OF ANSI NO. NEW OR SPENT FUEL SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LE i

NONE DURING THIS REPORTING PERIOD.

T

,g

.5 l -$

i G

22 PROCEDURE REVESIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR 1

MAY. 1982 l None during this reporting period.  !

.I e

e l

i 1

, .. - - . . . . - ., , ., , -..- ---n.- - ,,-, -. , , , .- - - - - . , , ~ , . , . , , , - . - - - - - -

23

. DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MAY, 1982 PT-23.1B Weekly Battery Test - was not completed as scheduled on .

5-3-82 for Unit 2. This PT is to verify that Main Station Batteries 2A and 2B and Emergency Diesel No. 2 are maintained serviceable. The test was conducted satisfactorily on 5-9-82.

I r

i 1

-w - - -- - -

,c ww-m- - * .,,-9m,.__ -_.-,.-.% .-, .-,.y .,w ,.------,y,-. -,.w- , y

24 INSERVICE INSPECTION MAY, 1982 UNIT ONE ._

No inservice inspection work was conducted this month.

UNIT TWO _

During the 10 day maintenance outage this month, inservice inspections were conducted per the Westinghouse Inspection Plan for the last 40 months of the first 10 year inspection interval.

No reportable Indications were found or recorded.

m --, ,y -y- m---.,4-- ev,, y , , .- _ a ,., - - - , -- ~.--

l 1

25 l REPORTABLE OCCURENCES PERTAINING TO ANY OUTAGE OR POWER REDUCTIONS MAY, 1982 l l

None during this reporting period.

a a

l l

w .,.

9 26 MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. I MECHANICAL MAINTENANCE MAY, 1982 l

l l

4 27 MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS i UNIT NO. 1 MECHANICAL MAINTENANCE MAY , 1982 NONE DURING THIS REPORTING PERIOD. .

i e {

i E

i 5

I a

s

O 28 MAINTCNANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 MECHANICAL MAINTENANCE MAY, 1982 l

i t

t I

l

..___-e -- --y.- --- .------ . --. , . . - - -

8 l i i

l -

I

. l l  ! j i i

! i "3""Eg23EO 02 g3 0 f'j g g* ::*S 2 l" 5 R " K ':

• 3 3 3:55 5 h

e n 4

a na======ema=g850 a=g : :g=23 =su In r==:a====s==25=ca:

RES28:35:C==%2: 62000 ==ke 6:0====t==0: o=====m:ss=an==ne: ===========e==

u s e s = a = a g = = =$ E $k k b ik$l0 $ $$ $ l:E

!!$N!!Nk! $!!$ $g = =S E E k $ $ $ $ $ $ $ $$ $ $

.. .  !$3*T.E S

- - . . _ _ , - - .. _ _ , . .., __ , ~ - - ... ... . . . - L ,, . -

E l t

5 E g ,

a f, a R e 4 g g g I< e

- e e a 's, t

• a 3  :

E

- e l"a I. e e E.

a r2= -n a" e =e og 3 3 o B E2 e$a

= e 3 =,gg d

- 4 te.

e g=atig gg g w!

2

aa a ngmg*.gg-r a:e a .m as a t ag

d e g

=* telea m e t,%eng u p BEE lkgt t a s er =Bn

• l t

e

5sga e...

,amme= ose-ame*g g sg-

,e*cd s

u:;:e, m s-,.

e n a5p a .="e6*a ss

---

s t m e 50 o e :a-I El n-hstgone Eb e - am oe=e 4- -

a i set e oo ,

• 88 e- pI8a :ag eg?ag aBe$ 5585E E E

• m a taabaar t mgau ah:o.ana zoo

.=

l'";ggge; gB q 3 ee n"R eugg5e$dt= 0

- - 2 :=, =

1[E :a g ~!!=ggag i a g' e a

!egI?ekwga 5 5 e imesmB! aakz)94 Edn!?B isk !E m =iine ! 0 44! am ka m

.I w _~ it l Ra  %*

9: u  !

Em 2 u '

g l, El$

~

we un u E - us u

• 5;;;

.m Rt 2: u, n a' D o .

ge =a =

2 o q: 56-a, e

.= lst m m e g! , ,e ,;,

, 4

'geg "2 *4!'4' 33 jgg W ,~* a84 mat:3- , b 1 24'

• e 2*E e,'

g h=t=

E

t. ega E-n.

i R se$

e t egeg- e1 ts2 52 osa 3:l ..

a gu. =

e3

~ 3 v,3 , ,g ,g a 3gg g e n

=g A= mag go o.

e mRoo e em =a 2 m tot ..

eis l

- 'ea p w-iium nam  !- es = ;3))Eg ----

=Bes:s -aen m s '3aHu dette. -- ir

! = r% a EB s, -ea m p.a p; a.ga :sso-se 3S [g. a-a

=1 . .e erk3- oggae

= E .- t I

- ite s e a- =.a -

m- c ,-geash*'goe

'.54 bt!5ha agg age na.M Ed g w 2

t egg &th m- ,a huu~=.: d w&l 2 =

g I h cac h.ks me a2=hz att 3 2 .- !.lE$msaeh3 e:d:'

- l

= s , , e  :-

$ r#

• S 3 2 g3 'e , a w  %: ,,.  ::

hh Yfhh Na 3tegPE $h i *

• Eb YY'Y hh hYhN R

vc #ateel;g= 8 E5 esQ-46kk88E88'kUl2ko0E

= it a c. A s E a r, A A .. , aatsaEA ;. -

s. . . , , - t A ,aa A

i k [

utEEE l:I22 2l 2 g22 g t!22222l:gaggy (egga a

u me-~~-w

+ s s a. H k 2 E u s t =a =: R u u w we :22$2a.:Illhe

..2 :: = $ ttt et s ZZu v v2Est -et et, s,u ns t' o. E

% l l l l l l l  !

in ten nnaaee::ezeen aeun a tamameneauav asaman saaea , ' ~

l e

t I

I

l :::l ::h:=lcc:::::l = ::::l: ::h: 2b::::::: 20:::

amandaadanaandadastanadanantaana ::::::::::::

l h

i ,

I l 1 i i , l , l i i l --

y......... ,; ag-i . a f r r .s : .: ,i s.;: :, ; ; ; 3 .:;;;

. s- . . . b

30. _ _ . _ _ _ _ _ _ _ _ _

i .

i h

+

4 ES 3 7"3=""g"  :; R ":.:

• Sn= n = ":::S E 2 g * ,, j $ 3 KK*

h

- E 5

x== ~ nn == gas:s s ga%** ::::::=u n:- ::::::: ne:

m g:e:gg=:Egs::::::

-  :.. 2ES  :::=

= = = = =ns = o : E. =sa s. a. =s.=s.g n...=m====,=s.

. oo< .. . . . ., .n.i o : :: .o..s s. . :. . . 2 :,. : :. :.. : .n gn=========

9. s u. s .s n .= =. ~

e:s ===

l l l l

, .. . . . , . . .. . ....m.. . ..... .... ... .. . ..

D N

g . . ~

g e

=

a b a a aE I

a ap a go o

M 8l:S u 2 4 me-b

= i.

$w 2 Do E E *'

r.au s'a ' a a" r n,by r z W

~ +3e m.

k g g*ua e'

e

~ =~ =

t 0 $a= wg . .a .,

.33

,=

= b s

u=

Eso s

e u=yy gt ne pgB

e,"J3en~p , ; ~ ~ , 3 , , , e g , , g " 3g %a. a.e, .

. asg M"2"to=,.a n = m g el. avoa m 6, a*  !

. gisen =~,2 a=gmage s E

1

3 =s -

a" z '* Eggsee a

L -i 2

• n an 26

,nobe rea- g : t~~ - : a meg haE e  :: m k: hat *

• h2 6a ds3 22e2,*E'e as B bal *6422 221s

,e illii!! libs.il pl khaci !Re ,a !!Ibibli = gB.'*-m -

= m - a 3 ==~,

gg F- aes n=5 3 E gge. :,me R a!laa =e e! B pg3g etumat$ge.3339 e om 5 e tl 3 .

D

u 2 *

De 8 'Y E ~T 5: 'e E .mam - p =

E ga 4

m e

2. o

-R u t

.e a

2 *-3 p a = .e lli in i $"

i =. g e ::

2 =$

I-Re,g o'

m a

$Etag 2 RW3 ou a! Je  ! I Eg .ga #g U" =

B c ge. . ~

ag an " i E a= E3 ' "t" 'CA* *gh35 3 ->

ge <

a nen n.e,2 a e :=o

• va ge as a :s t e a,tg gg-La"g,e: 1 = o t e- - = ~

semlR.ee Lag.us 4

~ ,

~

s e.outVV ze :1::5 =m- "

t' B - e - mm oge - E g g c,igu==

=  ::33 % = n wa-a ,Se nags,u[g~.

= un geh,n.g e rE g ss a==t= ,u m

= =.

, . e"a s . a  % n8a eng. "e =,

y y se G-p:1 1s. e a  % g lgalati 2 E h 3*2zzz, *tth s5 2slgames e Lg"g g -

a I aE E

! h. t !a  ;. maze = .o ash.a teeu e m.

2

?  ? 5 ,000

'h

- s ,. o ,,

.a

=

~

u ne

=

o

s a  ??? 3 a== m+ ? ?? .=34 Ti. . c. Y ? 2 l M???o- T 7 :.1% x :1312; L, 2 tve:~re ? v t y p* e,"> t- Lk tsa ar; em u" ner?ir a

e aterrue=$

a 2 yBenit4

.,Q

. c. a a .u .m? e, kltAakt,i.AAGae se,a , a w ,

ita usttal u.a aAH A A %s. .a t'aeac.aata al s22.E e == I f gh o w.a g,. a f .. am=Imma igls=.p=ag =,, WE snetent.

=4 g 03gessatene ceengte ant e ast3g u sIZZEt2Est :22Z2 s2EZ2t :E e.EtRZZZZtwa+$EZa4IZ222 I l l I l l E nueseelmanaanalaeuatee n naamaasenamiBEnlesee  ; ,

I i i i ,~ ~ ~i ~ e..i.

e t ~~~~~~.,~ ~~~ ~~~~~~~~~~~~. .i.~~ .,. ~.I. ~~~

t  ! '22%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%?t%%%%%%%%%%%

[. g kgRRRRRRRORRgRRORRORRRORRRRRORRRR00000000000000  !

u

= o::::::::::o ::::::::::::::::::::::::::::::::: .

I 4

4 i , , '. ,

e...... ......4 m: : 4 .. :u 2  : .,. 22,. ,  :,,: st ,- -

2 . 3-  : _

_ - - - O

_ _ _ . . . _ _ _ _ _ _ . _ _J L _ _ _ _ . _ _ _ _ _ _ _ . _ . _ . ._ ___

! i .

i l l

t EEEEE EEEEEE 33EE!!EE$EESIE SE6!6EEEEEEEEIEEE!E gi $  ::

iw ..

I f ganta=h 028'4 St l:23 ::.:::E C ::::Egn="E'M=t8:R a j  : Eg:B:;28 EE  :::=23

ot E08=:2282*I

ESSE  ::S

::: E *l:O gtat::: r. : ,, g g 3=gt : g:K Eg

.  !!EEEEE!!EEEEEEEEEEE!i3EEEE BEE SEE!!EE8 a ::: :=

j= ...f..<. . . .I. . . .

= . . . . .. . ,,.. .. ,, . . <...... . . .l. . .l. .

it

.  : .g. = :g u 2

3 :a oomo g . . ., ",,EI, l3 .g j .

g .= =

E

• am s$ang"iti gt 33 VE .Ei! 3-g E =e , 4M *-

Y EE J "A En s *tN Z - - lit E olg4 EWh=g w k. " E 8 "E wee Jit

.ge a *

! g=8

. g

.g a .8g 8~~~k'*. E** s,s I C II *as -wu go we

> ,eae $:'..3 - 'E<

et e :322 t y- -

- ~~gE! i gag ~e't :..e.= = g9o9 f -

o .

-u m ea$ng.as goEt=g"m .e5Ese d.a,: . . -~~

,aaaame,*e == hanen enstagg e

a

=

jts u mal m %ss tee<crezen' w

oegn +a m--

== 2s553gn aaihaE6ga 22 e p eI, ~s 25 :.ea-n@e ,ema m',,eep-@log

- 5

,e 4$e lim e gamenla$j e -

• =  := = g=! !-

dgg

• e !E

• t"E E $gg ! pi 3~ $gp= -

5 h. 't2 ,h la==, .=,3 E, E s<l :E.

3",: = r !w2 II<laM= g k.NS=mu$ u k.45 = .=. 3 d w=l2,g a, l b

=.=, l22 i

b hd i . a es g . . . .

}

ce* - g I

' l' Ia :s 21:

i, lS nt = ,.,

.w a g = ,

g g g M5 l5

, 8 81582 su mm k . 1 l Wb s 2 t hi :d* 33 Mibb 2 a ,2%lt  ?

E lio = i^*E

• It "4 4BER 33: 5 GR4a 3 E' =. *tt R . Jt' R o 1

,, I- RE E

• I

e. 'If eu ! [2

.w e

i .

.lg a g,h e g c.

3: i .!gs

• 1aa cauema:g  %:3)222 i -~.

g:,3 a ee. a nm-e

=

me g isl.. t oo. 1"25 . E'm i gg ga i's

!EE !g=,6:lg een e e ,

g ;g= ,

i *m a.a *=*= 2'5 156,et - 18 8 E :

a  : -

5 pga a u ~[E i s-[gga l,fa ! g :=2a .

. 's98a-a am-

..~, e .> n .- E 3 ca he 2: ~33, les ggag! ,

.g- aglgR

.a. e aree-s n w w" Bgge w . . ~:i. .a ah a

,=~ e.I. !.~g, g a by

. . o z m" a' .. e. ue.- . .

.e~e,.. .. n z" o n !... =.

W I E i o El 0 ,6=.<

8*g3 ll 5

.c .432 21

= : a.

2 5 o

=

, *8

.o. 4.:. 48*M 9.R.0 '. 2 1. 4 4 ::. c.

kg'.g' l.

o

l :I'

, ,Ea. =. 4  :.

4 : yata AR eaa n . A E R4ake a i s*a'e6:.haE i t ?. ada aa :. a a '

, AE!2R A J.taaa a j

b 3 - l

~ ti.=een g$5 e='e .g 1a8)!

a DD m em e'** ss a*  :> 2 a - e mmaesee Ue ::U W e *- me "te m

i 8 34"# N " =.4' 4 4' t t eh Rw otf4533 tt 4 u . 4 Ws2R. .

4 t t .t m u.E4."R"4E'E t,3.  :: .Z 2 -

l l l l l l lE aaBel ectesmanHawaaB asuttaa sauaau imaseannavana i[.:::::::::::::::::::::::::::::::::::::::::::: i I i i l i i a 6 I l l I g  ; E awa E ce>c>es :c:::c:cccccesceE 3 e cc damaga ~ agad ============>>>c g

lg 3

co$ooo$ooooohooooooooooopooooooooooooooooopo cesecececcecececececc b

• t  !

g 4 I

l l I

. , i i  : . ,

I' w... . .. .,i: r.> rrs: .:: e >:i..s: .:.  :::,,  :;

9 32 MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 1 ELECTRICAL MAINTENANCE

~

MAY, 1982 i

i l

l l

33 MAINTENANCE OR SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 1 ELECTRICAL MAINTENANCE

.I M AY , 1982

.i

'! NONE DURING THIS REPORTING PERIOD. ,

I \

I i

I i

P I

P

34 I

)

MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 i

ELECTRICAL MAINTENANCE MAY, 1982 l

l i i

e l

r

Il CEPTcELEC 8 JUM 82 s esos AN PACE %

4

UNIT 3- 6/08/82

(MAINTEWAMCE OF SAPETT RtLATED SYSTEMS MRIM hv7 ACE OR RtwCED POVtR PERIODS)

RtTPERVCT STS COMP MARKR0 SUN % ART VKPERP V MR TOTEWRTM

$ --05/15f 82-et -BtfS fit-1 C4. C = 50 IG-#0P-4 C C-PROB 6PN-C r 2 te%t%1ttS 100

. 05/15/81 EPM CRAMER 38t+282 CRAMERS REED BAUMIMC BAUNCED LOAD = SAT 2 20513t500 2%

. 05/16/82 M BREAKER BRK$ PRESSURIZER RTR BRt RAS CROURD M ET MPAIRED CAMAGED CABLE MCORREGTED C 2 20%0st%00 381 y; 05fts/8t - SI - YelVE i-;;C Pt96tf-VAlft Vilb-ret MiUT-ELN Volvt OFtRATEP BAT 2 205tS0508 -tt- - - - - - - ,

',- 05/ts/81 CR VALVE RC*'-2303B IMCICATERG LEGRTS Sh W INTERMVCIATE RETURE TO SERVKE 2 205160%t9 13

,3 05/11/82 IA VALVE TV-IA-101A C0 R0T HAVE OPER INCICATION REPLACED CEFECTIVE WITCR CTCLED VAL 2 20%261033 503

,, G*ftff81 X P;f e,72 3 ;; C MrBVTT00 :: : C  ;;i.,;;i: BV -t---20% t81s 3 5 i

,, 05/11/82 M ENP NTR P-10A PUSRBUITM ES BAD MPLACED & 2 20%28t336 %15

,. 05/18/81 RR EWP MTR 2-RN-P-tA IRSPECT UPPER 11 RUST BtARIRC$ IRSPECTED TRRUST BtARIRCS SAT t 20%3008%5 at

.L - --03118/82 u L tTCMTENG iii PARTTM-CRt0Wt"9W-tRt R&-CRCUND twt'!CATT M -ttTSTS 2 % $03t120 183 - - ~~ - -

., 05/18/82 CR RT P8-CK-20C LW AMPS CW PT 21 CKT REPAIMD 2 1051810%2  % ,~

,,, 05/18/82 CR hT P9-CK-20C LOV AMPS ON PT 21 CRT MPAIRED 2 2051810%3  %

. 99ft8f8i 55 27 Fi-si-k&A L& a ,ia &G Fi ki eKi Riinthi& 2 k&stei&+ o n 05/19/81 W BRK RRV-MS-20tA REPLACE MEAKER REPLACED BMAKER ARD TtBTED BAT 2 20%091130 16 u

,, 05/19/82 RP INSTR CLEAR Al!. MALT .  ;' MLA13 CLEARED 2 20%2%2050 t ,

n -- OSit9182 -CS-VALVE l,Gi-CS*t029--tISI*fRtTOW-Pet l,ein weis" ' tE5C&,nn s en And E G ,,nseu $At 1 - 20ste0991 it 05/19/82 RS VALVE MV-RS-255 A ANUST LTMITS 30 ANUSTMERT MADE ELECTRICALLY 2 20$180855 21 l 05/19/82 BS NOTOR RATCR CIKOR AMD RECUW DRIVE NOTOR C15COMMECTED ARD MCORNECTED SAT 2 205180951 2% y

OS/tsf81 - tM FALii iT-iAw%$ fiiSO s osw,AnA$MFC0EW"2W'1F8T Nui$ s i 202190826 &

..t,I , REPLAttD ikio a dive & i$ '

s , 05/20/82 CC VALVE 17-CC-2108 9ALVE POSITICW LTMIT MENRE2 LINIT M RiiS I101 CTCLED BAT 2 205t82035 t6 l ,, 05/20/82 CC VALVE TV-CC=210C VALVE POSITIQC EJMIT MIKRES 't ' ANUSTED E2MITS CTCLtD VALVE SAT t t0518203s is e r i,. -05/21/87 -SS-VALVs TV-SS-tetB ERTtflNtPTATE-t!TES-ANUST-t/S nasLAC2D ElkiT-MiitN-S;T t ~ testit%tt 1>0 2 2051802%1 3  !

,. 05/21/82 CS VALVE NOV-CS-2038 ANUST ACASTAT MLAT ANUSTED ACASSTA AS PER PROCEwRC ANUSTED ACASTAT AS PER EMP-C-RT-%5 3 205180250 8 i i,, 05/21/82 CS VALVE NOV-CS-203A ANUST ACASTAT REUT i, 09fttf81-itt iGV i,Gi-an-2&& i&Bll NABS-0ttT 4tFftT06-ittftATi&G .. a.waw -TO-SESRVitt 2 t09totsuo 19 -

, 05/22/82 CR RCY CR-2200 PULL REW CABLES l Pt!Lt. R8V EABLt R00Ktb W tRECk 8At t 203160805 121

. 05/22/82 PE PERET A-16 PERETRATIQW LEAkIR0 ,5. N LEAKS t 20%t31110 2%

PEWETRATTOR-t.thkINC M LEAK 9 - t - 20%t$titt t% e

.. ~ ~05/22/82 - Pt ~ PtRu t*ti

., 05/22/82 PE NMET A-18 PEMETRATIOW LEAKING M 82-16 REPUCED PERETRATIQW 2 20%13t113 2% ,

05/22/81 E% PEMET C-3 PEMETRATICW LEAKIRC ' N0 LEAKS 2 20%13111% 1%%

,. - -"DS/22/82 - ST - VAlii i Gi-&i-kifik DTSCfREC0W-90fb ooi &E5. a...no AND auia s.v sai i i&iket% su 91 l I . 05/22/81 SI VALVE NOV-SI-28618 DISC /RECOR NR kECM i DISCORRECTED ARD RECOM85TED BAT 2 10%201%2t 61 s 05/22/82 BC INP MTR 2-K-P-LA STEAM CLEAR COOLERS CLEARED COOLtRS 2 20%221505 12t

{ " 05/22/82 ~nC ~NCTOR k =RC=Pno ascAW2LEM i&&Lih5 CLinai& C&GLERS 2 20%2ttsuo Sti

<. 05/22/82 M NOTOR 3-RC-P-1C STEAM CLEAM C00MRS CLEANED C0OLERS 2 20%221501 151 t l 2 20$1%%%01 80 2 05/21/82 51 hT MOV-2861A RENOVE AND MPLACE htAT TRACIRC POR MMOVED MPUCED REAT TAPE '

hi iw&i*$i sad 5 m.: a i ek& anrLaii ha d ihnwibG ==VEtt-MPtMBtMfid IME i i&St%1%02 e&

. 0$f22/81 bi

~ 05/22/82 CS VALVE NOV-CS-203C ANUST ACASTAT MLAT ANUSTED ACASTAT MUT TESTED SAT 2 2051802%8 $

,, 05/22/82 CS VAVLE N0V-CS-2030 ANUST ACASTAT ANUSTED ACASTAT MLAT TESTED SAT t tL51802%9 3 '

. ~ 05/22/82 ~ VS - N0 TORS k=VS*t*6u satCK-tsu en &ii&ATECW- VANS CRECKED-SAf"tLECTRTCALLI 2 - 203t90999 13

. 05/22/82 VS ttXTINC 2-VS-P-1A REPLACE 50 MM07" LEAKING BT C$AMPERS CinEt.KED SAT 2 205200132 5% l

. 05/22/82 VS CUCTINC 2-VS-P-tB REPLACE 50LER(2 0 LEAKINC BT 50MMOID MPLACEC 2 205200135 %6 ,

,, 05/22/87-ffC an an -flC=%21v nnTCREW-AWD-RE"0NWfWas u evn suas anTCn8N1FPt.1CES40NttiTE i 209200829 %8

(

, 05/22/82 W VALVE NOV-W-25tP DISC /RECOM PCR ktCR CEPT RECONNECTED TESTED SAT 2 205201502 51 05/22/82 GR VALVE FCY-CR-2tno LtMIT SVITCRES CORRODED PROM LEAKS

• Switches NOT USEC 2 205201530 20

, 05/22/82 M9 - 90V --S6V-M9-tetAB-MPLACE Cell IM 6elPNelP VALVE REPLACMP COEL TESTEP-6AT t-195 tt t t0% --- - 8 -

I

,, 05/22/81 MS SCV SOV-MS-20tRR REPUCE COIL REPLACED COIL TFSTEC SAT 2 205121105 8

• I W

y - - - - - - - , - -

36 . _

l i . .  !

8 g

1 6 l.

i i l i i '

l  !

E

- an g =ss-- :gs agge jg  !

e a k at

" g .* . in . en .g an e e . n i> m w g N e i g c .e w e W "E

" N"E:>=3522 '*?g*e: 20ELl:l* :::2225 e

2:232"; ;26 E 322 2 g$"

R2.222 12 222,'

2., " l 22lt22222 t22:422

,, 2 222"

~

u ~~a nna a mm e n ,.a. man... ,,e n

- $ = .

g  ;=

j 3 i

g

~

nN $e na 5 gI u 3  !

e to a  : A=B

$ 2 h Eg ;2.g:s R4 k g 3 2 4  !? = u 8 in a=mb' a ' O *' 24" M4 3 Ik 405 $$8 ='3 b' i eau se =t ago to* .ta' a

al a".Re

=ER ce !%

4nElth naa Eb

=

• $=gt *!8 : = :g*E

!=

g' tE::t 5 4":' 1

'Eg g

,a > =

E,a I.#2= ,.  :

. << lWa,a Wl l,5= 2n 2=wWelm! =L

= i

,.t ..3 g- .

R2  ?  :

M l3 a DE

.m gE t'

e p

-sg .

~

=%

e

, gltl e, .

c!r m o%

g o m a

g4 h E s.

ag g 1 Et c 't

• 4 *

• E '-

=!34 58

= $l=gg*a 5 *aom *a e 2

[lge ag

"*'nge;5 E e

s a y s ~a~rE ese .

t

• U *=t l"*4 E a8'Ilgabet

~b2 D 8 38k ogg a Bl s "*D$ st m 4,ei Es !NG92i ivtBas E 5 sE*

a

~

e

' Ige'ne= h,e e g, u <s=e E'g eg insm=

B4 *

• b

,k l 'li E. e le u i n, a 2,'e h...a -oR '$.a .~ 5eu k

. in D 4t *= 4 M 1O M , I

$ 22 2 ;" " . : 42:g". s

'? 2 2 E?? ?Y:rgE

=

3 *

?? R???5? Fft 2

~

E4A RE yt o'3E ayl day ll2" *?4 E 'tt fag  :". A u *., .*a m i ,4?

. $' Q u e li khh e2 lv2 MA38= CRRlEER Ekn Eh j i

E g 2 522 g{g22 52 g 54E e

u n e.g v e (REEsa ou, . ,asu ve ,auR= % E~ R -E*

E ,a. t a ,

l i E cannae :tasas :acustl:aa ::e n I i i I a I h "****""**EeE$EE=EEUEE.EE  !

3 ============3 >>>>g=====

u ,

h k

e j=b EUEEEEEEEEEE'EEEEE'EEEEE p...........  ::pss ::::: E, l i

I  ; '

l l I , l

n. m m:n..: ,,........m: .: n. 3,

I 37 l

MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 1

~

INSTRUMENT MAINTENANCE MAY, 1982 i

'\

l

?8 i

MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 1 INSTRUMENT MAINTENANCE MAY, 1982 NONE DURING THIS REPORTING PERIOD.

[

f l

t i

6 I

f

[

i P

-.- .,,-n , , . _ , - . - ,-- - - - ..-,,--,- - _ - - . - - , _ , - . _ - - - . - . . , _ , ..,n,., , n,- - - . _,, _, - - . . . . - - - - - - .- - . .----- , - -,--,, , --e

~

39 l MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 INSTRUMENT MAINTENANCE MAY, 1982 i

l i

- - - - - . ~ - _ _ _ , _ . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ , _ . _ . . . _ _ _ _ _ _ _ _ .

~

~

_ __ _ _ _ _ _ _ __ _ . _4 0_ __ __ __ __ _.

. i .

I

'E m d =e

:: =: :-----::- 5 3 : :: - sg=a--! 3

. . i z 1 k ! =EN 1

• R

=-  ::= =- 5.fNa.sg:==s:!sE==: IM $ N NEYIP - -

ass!== n== = :== a=: In. = n = g,:::: g x == == ==g== :s

a. s.

s $..' u.s. = R ess ::=sss:1:s2u ss l:s2 2ss,ss -

8 2:

, . . . . .l . . . .. . . . .. . . . . - - . . . .l. . .. ,l. .,

e a ~L e . .

EE t "I E -

Es Eli B 3a 4 m' a R $a , =

E e a.n . .

a tu me e. . :g.

$5: . g3 =BB B

aa 8e lal .

i

• a eE8

.3aE==- '

8 JEE&eE g g g ,

,8 P= gee n

=  :

,==r

! *a a*B s.

n eg 3.IEE e A t ,1,a-d "lE===;t Ete 9]ls4,e$'

h

.s tEEi l.t 338-as;i l

=

i h:

.se '

g/tele=

-!!u a - /

2. tee!a e 22, aEm a- ,tGg,~ k-en**:t:

u R tl l;oeay t =

$ 2h*g 6 B'$= t a. aB q W' : J c 2 6 L 2 g

=

g:aTEE.!?

e gg g{!g (3gg! 0 4; 4 nE4glia # g!52I

= s.  ! I a. .

EElle illikil, li Hi ! Gli!

mi e ue . ,

En I N ti E$ 8 8 aa nsae  !! y< =iI

• l 8 eti: t ti: v =

at Ejn 4 s '.j:. g ;ll :;,:a lig s J

p =u$* E't a:t 'lEj'E a

-- sg ,; . t a4 .esI tt int *% 1 d u n.c.s lin *m

s, .

= EE $t = naut ' '

2 tb.

a 4

2 h'54g. M,a b.< uI at E< g4I *::r.

1s ' h. t'* 2*3

• 3 g . .

. ia

%  ! igg ddl iddl IlkI lh D I kg u

- m R2*ila -

%I 8I *E 1 g9::! = k*g

• E a =

!:aatte

, ,as!!agg

- ~ a

=

nA sa.ih. '.

es43a p=gga$e 1 a igg g jggh 5 :c to-m"E5h 1 D'il 23 t

m.

glnsee a!!$g 2

'g3cEkn .

=aR I' s EEEufE325, .,lin ! E n e, 16 sue ee .

i a .

A k 33 3 . . . 25 w o i 4 ==l: .< . '

t T r. g'f=2n . )E g.>"'

5 . 30  ;' W ?5, l

' g == '.73

$' @'5g?'.'E'A j =.l. J.

2 ?ltPR'd'Jilt = . .l. y Q*

fi.?;g a is GaliaEEss ii saik&6BGEnE6d6 mI t

. <., o e _f  ;

5" 4$ .h..h..h,$$$$$0k

mism Es eac 5Ecesi m b inb ~h5h!!$$hEbl:h z~a ze sea mit g$

I l

i e l l

l l j ,

E IIDdbdkkkd ED $kNdk.,k.khEkdkkINN DhEd l l l a t

l g-~~~

l L.-~i ~~e~~~~ I i a

l E #2222222222Phhhbbh:th33333332%A>>>

I l h RRRRRRRRRCRCkRRRRROR$.0RRRRRRRORRRRR

- . . . . . . . ......s......................

l l.

_m R-l 7 7.f f F 'i*' . *s I iI E .O  ;;,f . 5 r ) ; , ';.,,

s

41 HEALTH PHYSICS MAY, 1982 a

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.

1 l

1 l

s i

i 1

- -- - - - , . -. - - ~ , . - . - . _ _ , - - - - - . _ - _ - - - , _ _ _ _ _ _ _ - - - - - . _ _ . - - , - - - _ _ - - . . . _ , ~ , . . ~ . . . . . - _ - - , - - . . , . , - - - . . - - . - . --. _ -- .. - ~ -

42 PROCEDURE DEVIATIONS REVIEWED BY STAT 10M NUCLEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS i

MAY, 1982 None during this reporting period.

i d

e t

I 1

l-k

- . _ - - - _ _ - - . _ - - - - . _ - _ - - _ - .. _ _ .- --. - ..