ML20211Q255
| ML20211Q255 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1986 |
| From: | Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8703030048 | |
| Download: ML20211Q255 (50) | |
Text
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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT
-J TO THE NUCLEAR REGULATORY COIMISSION
" NOVEMBER 1986" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 r
Submitted by.
P. R. Wallace, Plant Manager G703030040 G61130 PDH ADOCK 05000327 gr fj }y PDH R
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TABLE OF CONTENTS Page I.
Operational Summary Performance Summary 1
Significant OpeVitional Events 1
Fuel Performance and Spent Fuel Storage Capabilities 2
PORVs and Safety Valves Summary 2
Licensee Events and Special Reports 2-5 Offsite Dose Calculation Manual Changes 5
II.
Operating Statistics A.
NRC Reports Unit One Statistics 6-8 Unit Two Statistics 9-11 B.
TVA Reports Nuclear Plant Operating Statistics 12 Unit Outage and Availability 13-14 Reactor Histograms 15 III. Maintenance Summary Electrical Maintenance
~ 16-17 Instrument Maintenance 18-21 Mechanical Maintenance 22-23 Modifications 24-31 IV.
Environmental Qualification (EQ) Summary 32-38
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OPERATIONAL
SUMMARY
a
O PERFORMANCE SUfWULRY November 1986 The following summary describes the significant operational activities for the month of November. In support of this summary, a chronological log of significant events is included in this report.
The units remained in an administrative shutdown the entire month due to design control review, configuration control updating and resolution of significant employee concerns: Outage related maintenance and modifications are being performed. Unit I has been off-line 465 days. Unit 2 has been off-line.466 days.
SIGNIFICANT OPERATIONAL EVENTS
- Unit 1 Date Time Event 11/01/86 0001C The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.
11/30/86 2400C The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.
Unit 2 Date Time Event 11/01/86 0001C The reactor was in mode 5.
The administrative shutdown due to design control review, configuration c'ontrol updating and resolution of significant employee concerns continues.
11/30/86 2400C The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.
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- FUEL PERPORMANCE Unit 1 The core average fuel exposure accumulated during November was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
Unit 2 The core average fuel exposure accumulated during November was O MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.
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SPENT FUEL PIT STORAGE CAPABILITIES The total storage capability in the spent fuel pit (SFP) is 1,386.
- However, there are five cell locations which are incapable of storing spent fuel.
Four locations (A10, All, A24, A25) are unavailable due to a suction strainer conflict, and one location (A16) is unavailable due to an instrumentation conflict. Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1,033.
PORVs AND SAFETY VALVES SUtetARY No PORVs or safety valves were challenged in November 1986.
LICENSEE EVENT REPORT (S)
The following licensee event reports (LERS) were reported to the Nuclear Regulatory Commission in November 1986.
LER Description of Event 1-86046 The Technical Review Committee of Sequoyah discovered that past performances of SI-161.2, " Snubber Functional Testing (Hydraulic and Mechanical)," did not comply with Technical Specification (TS) 4.7.9.e.3 (functional test acceptance criteria) for one snubber (unit 2) due to to errors in calculations. When corrected, drag forces exceeded fifty (50) percent of the previous recorded values. In addition, five (5) supports (unit 1) were identified which lackel an engineering evaluation as required by TS SR 4.7.9.f when documentation clearly I
indicated that the snubber had exceeded 50 percent of the previously recorded drag force value.
An evaluation has been performed on the involved snubbers and all were found within acceptance criteria. They will have documentation completed before each respective unit startup.
SI-162.2 is an adequate procedure; however, it will be revised to ensure the required steps are performed in calculating the drag force values and proper actions are taken it drag forces exceed 50 percent of previous recorded values.
This event was discovered October 10, 1996.
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l LER DescriDtion of svent 1-86047 An emergency diesel generator (D/G) start occurred at 2020 ccT, October 17, 1986, in which all D/Gs started, resulting in 2A-A D/G being loaded to the system after breaker 1414 tripped open causing a loss of voltage on start bus 28, 6.9 kV unit board 25 that supplies normal power to 2A-A shutdown board. Two minutes prior to this event, start bus 2B was transferred from the alternate supply breaker (1412) to the normal supply breaker (1414) after maintenance without any difficulty. Breaker 1414 is the normal feed fron common atation service transformer "C" 2
to start bus 2B which feeds the 6.9 kV unit board 28.
A thorough inspection and test of breaker 1414 and associated circuitry were performed with no determination as to the cause of this occurrence. Further investigations are being performed. All D/Gs were returned to normal position.
3 1-86048 During a review of SI-260.2 (performed in mode 6), " BIT Cold 1.eg Injection Flow Balance, Pump Performance and Check Valve Test,"
was found inadequate as required by SR 4.5.2.h.2.b on August 20, 1986. This test is performed each refueling outage or after system modifiation to verify the portion of the BCCS in association with CCPs. The flow rate for one CCP is l
five hundred and fifty-five (555) gym or less with the system being in its minimum resistance configuration with the miniflow valves open.51-260.2 was performed with the miniflow valves closed.
A new procedure, SI-260.2.1 (performed in mode 5 with the miniflow valves opened and the reactor closed) was approved to determined if a T3 violation existed. Pump 2A-A (flow rate 562 gpm) failed to meet the acceptance criteria. Pump 28-B was tested and found acceptable. The throttle valves were adjusted in the injection lines to increase the system's resistance, decreasing the flow rate of 2A-A CCP.81-260.2 will be revised j
to ensure SR 4.5.2.h.2.b requirements are reflected.
1-86049 An inadvertent D/G start occurred on November 2, 1986, at j
0302 CST due to personnel error. While returning breaker 15-5 i
6.9 kV shutdown board to service, personnel mistakenly tripped the normal feeder breaker to IB-B 6.9 kV shutdown board. This action initiated all four (4) D/Gs to start, IB-B loading due to loss of power. All D/Gs were stopped and returned to normal position. A similar event occurred as reported in 1.ER 1-86038.
I signs will be added to 6.9 kV unit boards for further identification.
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1.ER oescription of avent 2-86005 A CVI occurred at 1450 CDT, October 16, 1986, on unit 2 from an inadvertent spike on RM-90-1068 (containment lower compartment vent monitor). The spike was caused by spurious EMI, although no actual high radiation levels existed in containment at this time; however, the RM has a gaseous detector channe1 which has a wider band width than the particulate or iodine channels. The spike was caused on this channel, and it was assumed that heli-arc welding operations caused the EMI. The exact welding operation could not be determined. All systems operated correctly during t.his event. The CVI was reset and all valves returned to normal. A design request was initiated to add capacitors as filtering devices to help reduce the frequency and magnitude of spikes on RM-90-106B and other similar type RMs in the future if approved.
ABBREVIATIONS 1.
D/G(s)- Diesel Generator Technical Specification 2.
TS Surveillance Requirement 3.
SR Surveillance Instruction 4.
SI 5.
ECCS - Emergency Core Cooling System Centrifugal Charging Pump 6.
CCP Containment Ventilation Isolation
- l CVI Radiation Monitor 8.
RM 1
Electromagnetic Interference 9.
SPECIAL REPORT (S)
There were no reports submitted to the NRC in November 1986.
OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah offsite dose calculation manual during the month.
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9 OPERATING STATISTICS (NRC REPORTS)
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OPERATIND DATA REPORT DOCKET NO. 50-327 DATE DECEMBER 10,1986 COMPLETED BY D.C.DUPREE TELEPHONE (615)S70-6544 l
OPERATING STATUS 1.
UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1
NOTES:
2.
REPORT PERIOD: NOVEMBER 1986 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (GROSS MWE):
1220.6 5.
DESIGN ELECTRICAL RATING (NET MWE):
1148.0 i-6.
MAXIMUM DEPENDABLE CAPACITY ~ (GROSS MWE):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0 C.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.00 8016.00 47497.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 24444.91
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE O.00 0.00 23871.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 16.. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-3522.00
-35906.00 24906831.00
- 19. UNIT SERVICE FACTOR O.00 0.00 50.26
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 50.26
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 45.68
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 45.68
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 35.87 i
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
i
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.
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l' NOTE THAT THE THE YR. -TO-DATE AND l,
CUMULATIVE VALUES HAVE BEEN UPDATED.
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r UNIT SHUTDOWNS AND POVER REDUCTIONS DOCKET NO.
50-327
' UNIT NAME Sequoyah One-DATE December 2, 1966 COMPLETED BY D. C.
Dupree REPORT MONTH NOVEMBER 1986 TELEPHONE (61315/u-6344 6
w a
c Cause & Corrective cg g
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Date g
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4 Design Contro'1, Coinfiguration Updating, and Employee Concerns.
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3Hethod:
i 1F:
Forced Reason:
l S: Scheduled A-Equipment Failure (Explain) 1-itanual W
for Preparation of Data B-llaintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NtIREG-0161)
E-Operator Training & Li, cense Examination Outage F-Administrative 5-Reduction SExhibit I-Same Source G-Operational Error (Explain) 9-Other
.6 II-Other (Explain)
OPERATING DATA REPORT e
DOCKET NO. 50-328 DATE DECEMBER 10,1986 COMPLETED BY D.C.DUPREE TELEPHONE (615)B70-6544 OPERATING STATUS
~
1.
UNIT NAME:,SEGUOYAH NUCLEAR PLANT, UNIT 2
NOTES:
2.
REPORT PERIOD: NOVEMBER 1986 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (GROSS MWE):
1220.6 5.
DESIGN ELECTRICAL RATING (NET MWE):
1148.0 c.-
6.
MAXIMUM DEPENDABLE CAPACITY 4 GROSS MWE):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0-O.
IF CHANGES-OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST RE' PORT, -GIVE -REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.00 8016.00 39457.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. HOURS GENERATOR ON-LINE O.00 0.00 21494.42
- 15. UNIT RESERVE SHUTDOWN HOURS O.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 23536780.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-6605.00
-57778.00 22574179.60
- 19. UNIT SERVICE FACTOR O.00 0.00 54.48
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 54.48
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 49.G4
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 49.84
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 37.82
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
THE STARTUP OF UNIT-2 HAS DEEN SCHEDULED FOR APRIL 1986.
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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1986 COMPLETED BY D.
- c. Dupree TELEPHONE (615)870-6544 REPORT MONTH NOVEMBER 1986 a
Se Cause & Corrective o eo O Licensee so ee m
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4 Design control, ConYiguration Updating, and Employee Concerns.
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3Hethod:
IF:
Forced Reason:
S8 Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-!!aintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NtfREG-0161)
E-Operator Training & License Examination Outage F-Ailministrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source Il-Other (Explain)
D OPERATING STATISTICS (TVA REPORTS) l l
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TbA M83Q (DNP6 84 NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant NOVEMBER gg 86 720 Month Period Hours Item No.
Unit No.
UNIT ONE UNIT TWO PLANT 1
Averaae Hourly Gross Load. kW 0
0 0
2 Maximum Hour Net Generation. MWh 0
0 0
3 Core Thermal Energy Gen. GWD (t)2 0
0 0
4 Steam Gen. Thermal Energy Gen., GWD (t)2 0
0 0
8 5
Gross Electrical Gen.. MWh c#
0 0
0 6
station use, renn 3,522 6,605 10,127 f
E 7
Net Electrrcal Gen.. MWh
-3,522
-6,605
-10,127 8
Station Use, Percent N/A N/A N/A 1
9 Accum. Core Avg. Exposure, MWD / Ton 0
0 0
6 10 CTEG This Month,10 BTU 0
0 0
6 11 SGTEG This Month,10 BTU 0
0 0
12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use, Hours. Min.
0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 16 Turbine Avail. Factor. Percent 0.0 0.0 0.0 y
17 Generator Avait. Factor. Percent 0.0 0.0 0.0 g
e 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 2
20 Unit Avail. Factor. Percent 0.0 0.0 0.0 21 Turbine Startuos 0.0 0.0 0.0 22 Reactor Cold Startuos 0.0 0.0 0.0 23 g
24 Gross Heat Rate, Btu /kWh N/A N/A N/A
,6 25 Net Heat Rate, Btu /kWh N/A N/A N/A 26 Y
27 g
28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature *F N/A N/A N/A d
30 Exhaust Pressure, InHg Abs.
N/A N/A N/A E
31 Intake Water Temp., *F N/A N/A N/A 32 33 Main Feedwater, M lb/hr N/A N/A N/A y
34 35 36 37 Full Power Capacity, EFPD 404.86 360.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 j
39 Oil Fired for Generation, Gallons 3,564 2
40 Oil Heatina Value. Btu / Gal.
138,000 54 41 Diesef Generation. MWh O
Max. Hour Net Gen.
Max. Day Net Gen-Load MWh Time Date MWh Date Factor, %
a 43 N/A N/A N/A N/A N/A N/A O
Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.
j 2(t) indicates Thermal Energy.
3 Ln DEC.151988 i
Date Submitted Date Revised 9Nd a
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UNIT OUTAGE AND AVAILABILITY e
SEOUOYAH Nuclear Plant Licensed Reactor Power 3411. MW(th)
Unit No.
TWO Month /YearNOVEMBER 1986 Generator Rating 1220.5 MW(e)
Period Hours 720 Design Gross Electrical Rating 1183 MW MEmOD OF UNIT CORRECTIVE ACTION Tome Unit Avastatge T'e e Not Availat$e SHUMING STA NS TAKEN TO PREVENT Time Time OUTAGE CAUSE DOWN DURING REPETITION Total Gem Not Used Turtune Gen.
fleactor Unit Out in REACTOR OUTAGE Day Mrs l Min Hrs ! Min Hrs [ Mon Hrs l Min Hrs l Min Hrs ! Min Hrs l Min Has ! Min Hrs ! Men Design Control Configuration N/A Mode 5 1
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SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -
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SEQUOYAH TWO REACTOR HISTOGRAM 100
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12 16 20 24 28 32 NOVEW8ER 1986
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SUMMARY
OF MAINTENANCE ACTIVITIES r
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SUMMARY
(ELECTRICAL) l l
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SUMMARY
12-03-36 PAGE 1 CCG MR. COMP U FUNC SYS ADDRESS. DATE.... DESCRIPTION............................. CORRECTIVE ACTION......................
A551206 1 BCTC 079.HB /8D1 11/06/86 1-BCTC-079-HB /8D1 10FF ON SAFETY SW REPLACED BROKEN 480V DISCONNECT SWITCH.
WHICH SUPPLIES 480V RX SIDE FUEL TRANSFER CONSOLE B119212 1 MV0P 072 0040 09/23/86 1-MV0P-072-0040-Art *NPRD*,*10CFR50.4983, OPEN LIMIT SWITCHES WERE OUT OF THE VLV 1-FCV-72-40 FAILED SI-166.6 ADJUSTMENT CAUSING VALVE TO FAIL STROKE TIME. REPAIR AS NEEDED TO SHORTON SURVEILLANCE STROKE TIME. RESET OPEN STROKE OPEN TIME LIMIT SWITCHES AND MOVED VALVE FROM 8 TURNS TO 13 TURNS OFF BACKSEAT. WR B-119812.
B120937 1 BATB 082 UB 11/14/86 1-BATB-082-UB-Ar[*NPRD*], DIESEL CORROSION DUE T0' ELECTROLYTE SPILL GR GENERATOR BATTERIES D/G 1A-A D/G 722.
ACID BUILDUP. REPLACED BOLTS AND MUTS ON REPLACE COR0DED BOLTS ON CELL 4 16 22 CELLS'4, 16 1 22. CLEANED CORROSION FROM CLEAN CORROSION ON. CELLS 25_37 49 -
CELLS 25, 37 AND 49 RETURNING BATTERY TO SERVICE. WR B-120937.
B127283 0 BCTB 313 DO /5D 11/10/86 0-BCTB-313-D0 /5D-A,[*NPRD*],BKR IS STRIPPED BOLT AND NUT ON LEVER ASSEMBLY.
STUCK IN TEST REMOVED BREAKER AND REPLEED CONTACTS AND MECHANISM LEVERING DEVISE. PERFORMED MI-10.5 FOR ADJUSTMENTS THEN CHECKED FOR PROPER OPERATION. WR B-127883.
B132462 0 BATB 250 GV 11/11/86 0-BATB-250-0V-D,[tNPRD*], EQUALIZE BATTERY HAD LOST CHARGE FROM NORMAL BATTERIES FOR 7 DAYS WEAR. PERFORMED MI-10.44, PLACING BATTERY ON EQUALIZE CHARGE FOR 7 DAYS.
UR B-132462.
B132463 1 BATB 082 UC 11/11/86 1-BATB-082-UC-Be[*NPRD*], PLACE BATTERY BATTERY HAD LOST SOME CHARGE FROM NORMAL ON EQUALIZE FOR 7 DAYS WEAR. PERFORMED MI-10.44, PLACING BATTERY ON EQUALIZE CHARGE FOR 7 DAYS.
WR B-132463.
B132498 2 GENB 082 0002A 11/04/86 2-GENB-082-0002A-A,C*NPRD*],D/G 2A-A THE PROBLEM WAS FOUND IN THE GOVERNOR SI-26. D/G 722. TROUBLE SHOOT CAUSE OF ACTUATOR. WORK PEDUESTS WERE WRITTEN TO LCAD SWING DURING SI 26 REMOVE ACTUATORS AND SHIP TO UDODUARD GOVERNOR COMPANY TO BE REBUILT. WR B-132498.
B200155 ? BCTD 067 0065 11/04/86 1-BCID-067-0065-Br[*NPRD*],WEHN VALVE IMPRCFER CLEANER HAD BEEN USED ON THE REACHES THE FULLY OPEN POSITION, IT CONTACTS. REPLACED INTERLOCK SWITCH AUTOMATICALLY STARTS CLOSING AGAIN. ALSO ASSEMBLY ON ARROW-HART CONTACTORS AND IT APPEARS THE LIGHT INDICATION FOR THE RESET GPEN AND CLOSED MICR0 SWITCHES. WR OPEN POSITION IN THE MAIN CONTRCL ROOM B-200155.
IS NOT GIVING CCRRECT INDICATION.
B202555 1 AHU 061 0006A 10/29/86 1-AHU-061-000fA,CtNPPD*],AHU HAS ICE DRAIN PAN HEATER HAD BURNED OUT DUE TO ACCUMULATION IN POTOR COMPARTMENT NORMAL WEAR. REPLACED DRAIN PAN HEATER
_ AND REMOVED ICE. WR B-202555.
B202695 1 AHU 061 0029B 10/27/86 1-AHU-061-0029B,[*NPRD*],AHU HAS ICE DRAIN PAN HEATER HAD BURNED UP CAUSING ACCUMULATION IN MOTCR COMPARTMENT ICE ACCUMULATION IN MOTOR CCMPARTMENT.
REPLACED DRAIN PAN HEATER AND REMOVED ICE. WR B-202695.
B202697 2 AHU 061 0016B 10/03/86 2-AHU-061-0016B,[*NPRD*3,AHU HAS ICE THE DRAIN PAN HEATER HAD BURNED CUT DUE ACCUMULATION IN MOTOR COMPARTMENT PEMOVE TO AGE OR NORMAL WEAR. REPLACE 0 DRAIN Pi.-
ELECTRICAL MAINTENANCE M048MLY
SUMMARY
12-05-86 PAGE 2 COMP MR. COMP U FUNC SYS ADDRESS. DATE.... DESCRIPTION............................. CORRECTIVE ACTION.......................
ICE AND REPAIR PAN HEATER AND RETURNED TO SERVICE. WR B-202697.
B202711 0 BCTB 026 0001A 12/02/86 0-BCTB-026-0001A-A, CHARGING SPRING MOTOR MOTOR LOCK 0UT SPRINGS WERE BAD. REPAIRED KEEPSATTEMPTINGTOCbANGESPRING'WHEN SPRINGS ON MOTOR LOCK 0UT SWITCH AND BREAKER RACKED IN CHECKED FOR PROPER OPERATION. UR B202711.
B202765 0 HS 067 0436A 11/13/86 0-HS-067-0436A-A,UHEN THE HS IS PLACED ROTARY HANDSWITCH WAS BAD POSSIBLY DUE IN THE TRIP POSITIONi THERE SF0VLD EE NO TO NORMAL WEAR. REPLACED ROTARY
~ TIME DELAY HANDSWITCH IN CONTROL ROOM. UR B-202765.
B202876 2 BCTA 068 0341A11/18/862-BCTA-068-03MA-A,[tNPRD*3,PERHTRBRK POSSIBLY, THE RELAY C0ll PURNED UP DUE 0FF 2AA SD lid WILL NOT OPEN FROM MCR TO N,0JMAL WEAR. REftACED 30RX HAND SW WHEN BRK CLOSED ELECTROMAGNETIC RELAY AND CLEANED FUSES AND FUSE HOLDERS AND RETURNED BREAKER TO
~
-~ -,_.
SERVICE. WR B-202876.
B203501 1 BATB 032 UB 10/31/86 1-BATB-082-UB-A,[tNPRDt), PLACE PATTERY EATTERY HAD LOST SOME CHARGE FROM NORMAL CN EDUALIZE CHARGE PER MI10.44 WEAR. PERFORMED MI-10.44T PLACING BATTERY ON EOCALIZE CHARGE. UR B-203801-.
F206381 0 BATB 250 GX 10/31/86 0-BATB-250-GX-F,[*NPRDi],*I* VITAL PATTERY HAD LOST SOME OF ITS CHARGE FROM BATTERYS FAILED TO MEET ACCEPTANCE NCRMAL WEAR. PERFORMED MI-10.44, FtACING CRITERIA 0 SPECIFIC GRAVITY FATTERY ON EQUALIZE CHARGE. WR B-206381.
B206602 0 PATB 250 QW 11/08/86 0-BATP-250-0W-E,[tNPRD*], VITAL PATTERY BATTERY HAD LOST CHARGE FROM NORMAL II DID NOT MEET ACCEPTANCE CRITERIA IT WEAR. PERFORMED MI-10.44, PLACING UAS 1, 202 AND SHOULD PE 1.205 WHILE PATTERY ON EGUALIZE CHARGE. WR P-206602.
PERFORMING SI 100 17 records listed.
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SUMMARY
(INSTRUMENTATION)
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Vendor manuals in the EQ Binders were reviewed for maintenance A
requirements that were not listled in the Qualified Maintenance Data Sheet requirements. These maintenance requirements are being incorporated in Instrument Maintenance Instruction (IMI) 135 as recommended maintenance guidelines for 10 CFR 50.49 instrumentation.
2.
Received nine PROS during this reporting period on out-of,-tolerances on compliance instruments..Jhe instruments were recalibrated and returned to service.
f 3.
In continuation from October 3orkplan 12107 (ECN L6737), which replaced rotameter 0-FI-14-466, was field completed and documentation completed.
This was part of the corrective action on PRO l-86-104.
4.
Prepared and received approval on preventive maintenance procedures to check calibration of refuel water storage tank (RWST) level transmitters on a monthly basis. This is in response to Employee Concern Task Group Report 303.02SQN.
UNIT 1 1.
Flow transmitter 1-FT-3-48B was found out-of-tolerance for the third time in the last three calibrations. A work request (WR) has been initiated to replace the transmitter.
UNIT 2 1.
During recent walkdowns to verify as-constructed drawings, the inputs to transmitters 2-PT-3-168 and 2-PT-3-145 were found swapped. A drawing deviation report was initiated and a WR was written to correct the problem.
l 2.
Completed preparation of Special Maintenance Instruction 2-63-3 for l-replacing containment sump level transmitter 2-LT-63-177.
The procedure 1
is in the Qualified Individual Review cycle. The transmitter must be installed prior to startup.
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9 6 ..ll MAINTENANCE
SUMMARY
(MECHANICAL)
1 MECHANICAL MAINTENANCE MONTHLY REPORT FOR NOVEMBER 1986 COMMON 1. Continued hanger bolt tightening program - to date approximately 858 of 1,050 hangers are complete. 2. Completed approximately 30 Grinnell valve diaphragm changeouts. 3. Completed changeout of auxiliary building door A-38 (NRC committment). 4. Continuing work on the "B" waste gas compressor. 5. Began.6 year diesel outage; completed work on 1AA, IBB, and 2AA diesel generators. Work continuing on 2BB. 6. Began repair and inspection of auxiliary boilers. Formulating plans to allow work on one boiler while the other is running. Investigating possible retubing of "A" auxiliary boiler. 7. Completed mechanical seal changeout on the CDWE recirculation pump. 8. Continued inspection and repair of ERCW piping which contains microbiological-induced corrosion (MIC). Replaced 2-inch carbon steel line and 1-1/2-inch stainless steel line. Inspected 24-inch header and determined that it does not need replacing. 9. Completed auxiliary building damper repairs and determined future plan of action.
- 10. Repaired water jacket leak in the control air compressor.
- 11. Initiated CO2 PM and closed out CATS Item NCO860209002.
- 12. Began work on resolution of stop-work order for Class A, B, C, and D piping class components. Revising Maintenance Instruction (MI) 6.21,
" Repairs and Replacements On Section XI Equipment." UNIT 1 1. Completed unit 1 main condenser repair work. UNIT 2 1. Started work on MSIV spring testing. ~ OTHER 1. Participated in the annual REP drill. 22-s
MECHAM1Ull CINIENANCE nuMlHLY sunMARY 12-0.1-84 Pan 1 CWF M. CMP U FUNC SYS ADDESS. DATE.... DESCRIPTION............................ COMECTIVE ACTIN....................... A539078 1 FSU 001 VARIOUS 12/07/841-FSU-M1-VARIOUS, REPLACE SEALS IN LOOP PER 10CFR50.49. ADAPTER TO STEM THKADS 1 MS1U SEEED EJS CLASS 1E WEE CROSS THKADED. INSTALLED NG KOUIKIIENT PER MT IUES O-RINGS. INSTALLED E SEENDID. A53;79 1 FSU M1 UARIOUS 12/07/851-FSU401-UARIOUS, REPLACE SEALS IN LOOP PER 10CFR50.49. DSTELED E O-RHES. 2 MS1Y SEEED EYS CLASS 1E KOUIKET PER MT IUES A539000 1 FSU 001 UARIOUS 12/07/851-FSU-001-VARIOUS, REPLACE EEALS IN LODP PER 10CFR50.49. INSTALLED NEW 0-RINCS 3 MSIU SEEEID EUS CLASS 1E KOUIKETS PER MT IUES B1001M 2 FCU 047 03521U03/84 2-FCV-047-0352,ENNPRDn], ACTUATE AM STEM HUT WORKED LOOSE. APPLIED LOCKTITE HAS ROTATED AWAY FROM LIMIT SWITCH TO THREADS AND STAKED. TRMSFERRED TO CONTACTS ,J SMUEILLANCE INSTRUCTION 164.d MASTERLIST AND KTURMED TO SENICE B108129 1 FSU 048 0308 lu02/841-FSU-048-0308-B,En10CFR50.49u3,nNPRDM PER 100FR50.49. INSTALLED KH SOLENOID REPLACE E U COIL AND ELASTOMER ULY B108130 1 FSU 0?? OM9 lue2/841-FSU477-M09-B,En10CFR50.49m3,nNPRDn PER CFR50.49. INSTALLED KU SOLENOID ULY REPLACE EU CDIL AND ELASTOKR B108131 1 ISU 077 0018 lu02/841-FSU477-0018-B,EN10CFR50.49d3,nNPRDn PER 10CFR50.49. INSTALLED KU SDLENDID KPLACE EU COIL AND ELASTOKR ULY , B123154 1 DISC 042 019210/3V8d 1-DISC-0424192,KPLACE RUPTUK DISC B125749 0 EU 02d 135811/0d/84 0-EU-024-1358, HANDLE HAS BROKDi OFF OF UKNOWN. DSTALLED KU UALUE DE ULY B132555 0 PMP 042 0155 0V15/84 0-PMP-042-0155,DSPECT PUMP FOR KM P.M. KBUILD PUFF KPLACE KFECTIVE PARTS B201441 0 FCO 030 0122 lu03/84 0-FCD-030-0122-A, CONTROLLER ON 0-FCD-30-122 WAS FOUND LEAKING AIR B202909 1 AHU 313 %2d 11/03/841-AHU-313-%24, PRESSURIZING FM IS MAKING LOUD NOISES AND UIBRATING WHILE RURING B209221 1 ENG 082 0001A1 lu12/841-ENC-082-0001A1,KPLACE WATER PUMP SEALS AND ALL WORN PARTS B209225 2 ENC 008 0002A1 lu18/84 2-ENC-008-0002A1, REPLACE WATER PUMP SEALS MD ALL WORM PARTS l B209224 2 ENC 082 0002A211/18/84 2-ENG-082-0001A2, REPLACE WATER PUMP t SEALS AND ALL WOU PARTS 15 re<ords listed. l 1 l
4 gi. 6 A e s .s- .4 MAINTENANCE
SUMMARY
(MODIFICATIONS) l 6 I l l l .A e l l l
ga %~ SUf-NARY OF WORK COMPLETED MODIFICATIONS T NOVEMBER 1986 APPENDIX R ECN 5435 - Fire Doors,. ~ The installation of weatherstripping continueT'as resourcos permit. ECN 6300 - Additional Sprinklers and Draft Stops The draft stop workplan is in work, and the sprinkler workpYhn is in the approval cycle. Questions concerning the design had been raised by operations and have been resolved by DNE. A workplan for the electrical portion is in the approval cycle. ECN 6311 - Operator Extension on PORV This work has been completed except for final cycling at startup. ECN 6319 - High-Pressure Fire Protection Rework Workplan is in work. OTHER ITEMS ECNs 2783 and 5202 - Installation of Fifth Diesel Installation of the fifth diesel generator has been deferred indefinitely. ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of unit 1 isolation valves was approved. Some insulation activities remain incomplete. l ECNs 5034 and 5743-Various Platforms in Lower Containnent i i Because of new weld inspection requirements, Modifications Group B is waiting on DNE to furnish inspection requirements on tack welds to hold down grating. ECN 5111 - Remove Power From Old Carpenter Shop at Dry Active Waste Building 1 Modifications Group C is holding the completion of this ECN until the completion of the Dry Active Uaste Building. Power is needed for construction power. [ ECN 5198 - Installation of Check Valve in Floor Drains The workplan was written, approved, and work completed. l
t ECN 5111 - Provide permanent power to manholes 42-46. Workplan 12262 approved for manholes 44 46. Additional FCRs are in process 7 for manholes 42 and 43 and to provide sump pump for manhole 45. ECN 5599 - Conduit Supports for Fifth Vital Battery and Waste Disposal Area Workplan 12186 approved for fifth vital battery area. Workplan for waste disposal area heldIfor issue of ECN by DNE to include FCR 4753. ECN -5609 - Air Compre,ssors Makeup Water Treatmen Plant Air compressors and mechanical piping complete except for tie-in to headers which is held for issue of electrical drawings. e3 ECN 5609 - As-Construct Makeup Water Treatment Plant Drawings per SQ-DR-86-03-61R Held for release of five remaining drawings from DNE. ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete. ECN 5703 - Reinforcement of Block Walls DNE has added a requirement for signs to be posted in areas where block walls exist. This is in process. Work was resumed on unit 1. ECN 5713 - Various Platforms in Lower Containment The first trolley was modified by the vendor. Additional onsite testing is required. The remaining trollies are being prepared for shipment to the vendor for modification. Work will continue when the trollies are returned. ECN 5724 - CVCS/RHR Supports l One hanger and one notification of indication remains incomplete for l unit 1. Work is in progress. l ECN 5855 - Replacement of Doors A56/A57 I ~ The workplans were returned to the review cycle after being in holding. ECN 5550 - UNID Tags for Class 1E Fuses Field verification of Class 1E fuses and penetration cable protection is approxmately 85 percent complete. DNE to issue fuse listing and drawings before remainder of the work completed. l z. ,. ~ 9 [ (. s ECN 5935 - Correct Power Bleck Lighting Dsficiencies s I. Workplan initiation held far release of drawings by DNE. ECNs 5938. 6305, and 657); - Replice Feedwater.H1ater and Ecofed Pipe ModificationsGroupBis$supportingpostmodificationtesting(PM") on heaters 1-.and 2 on both units as requested. Insulation work on .,' unit 1 continues. Inctallationiof the monorail on unit 2 continues = in preparation for the changeout of feedwater heaters 3 and 4. F Structural steel reinforcement has begun gn unit 1 heaters.3 and 4'. 3 3-ECN 6014 - Replacement'of ERCW Pump Bearing Piping, i
- 9
/ L Work is continuing. + ECN 6057 - Cable Tray Covers 7 4 Approxinately 240 out of 290 cable tray covers have been remanufactured or replaced. Tho extent of cable tray cover requirements are being reevaluated by DNE. s ECU 6147 - Airlock Packing Nut I Final testing of the airlocks on unit 2 remains incomplete (prior to mode 4). ECN 6185 - Offsite' Paging System Functional tests of the remote mobile units remain to be completed. ECN 6196 - Pressurizer Hangers and Valves g, PMT is incomplete arad scileduled for startup. ECN 6204 - Electrical P.wetration Overcurrent Protection , Fuse replacement and fuse block installation are complete. ' Modifications Group A is waiting for a technical specification change to place the circuits in operation. ECN 6237 - Modify Snubbers WSek is continuing for unit 2. ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement l ,\\ l Closaup and reinsulation is continuing. i
Y ECN 6380 - Replacement of Barton Pressure Transmitters Unit 2 installation is complete. The unit 1 workplan was prepared-Land placed in-the: approval cycle. ECN 6357 -- ERCW Roof Access and Rails for Security Equipment -i. Workplan 12238 held for DNE approval of FCR showing installation details. h' ECN 6388 - 500-kVA Switchyard C rent Transformer Heaters Two heaters completed on Workplan 12005. Workplan 12223 for five b remaining heaters in approval cycle. Revised based on Operations I\\, f, and DNQA comments and resubmitted for approval. .Q, s -ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation. ~ j All work is complete. In-service tests will be performed when the system is brought up to temperature and pressure. ~ ECH 6459 . Upgrade CU-3 Box Battery Packs Workplan being written to perform work. k ECNs 6491 and 6534 - ERCW Supports All hangers for unit 2 (ECN 6534) have been completed. Six hangers remain for unit 1. Drawings are still to be issued for drawing-change-only workplan (ECN 6534). ECN 6543 - Install Public Safety Access Portals and Modify Entrance I Road f Work is being held pending-the release of drawings from DNE. ECN 6556 - Replace Solenoid Hangers and Limit Switches -) Fieldwork is complete. Lack documentation "aly FCR to complete [ unit 1 workplan. ECN 6599 - Unit 2 Shield Building Anchor Problem I Work is complete. i ECN 6601 - Remov 1 of Unit 1 EGTS Backdraft Dampers i PMT remains to be completed by the Engineering Test Section. i,, ECN 6610 - Modify Air Return Fan Supports Unit 1 work is incomplete. [ l I -
i ECN 6636 - Replace Cable in Valve Room l All unit 2 work is complett e, ) ECN 6661 - Upgrade of ERCW Piping During final closeout, it was discovered that additional work was required for thdsinstrumentation lines. This is currently in progress. 'ECN6687 - Additional Office and Medical Facility Modification to medical facilities in process. Fencing along ?' railroad area and west side held for installation of the South Central Bell environmental unit. ECN 6687 - South Central Bell Environmental Unit (CCBEU) Workplan 12251 in work. Building complete. Conduit installation in process from manhole 84 to manhole near CCBEU. ECN 6689 - Relocation of Mainsteam PORV i Reworking conduit and cable in process due to design errors. Relocation of controls is expected shortly. Unit 1 conduit is in progress. Mechanical work for unit 2 is complete except PMT. ECN 6698 - Repull 120-Volt Cables All cables have been pulled. Workplan on terminations is in approval cycle. ECN 6701 - Modify Foxboro Recorder Latches i Fieldwork is continuing. Completion delayed due to material which is on order. ECN 6702 - Upgrade of ERCW Valves Work is complete for. unit 2. ECN 6706 14 Support Enhancement Fieldwork continues on both units. Initial inspections for units 1 and 2 are complete. There are five unit 2 supports that lack field modifications and are in work. Unit 1 evaluations are continuing. ECN 6707 - Replace System 74 Flow Switches Workplan is ready for work. Work will start upon receipt of mounting screw nuts.
ECN 6715 - D/C Randon Loads Workplan is in work. ECN 6717 - Stub Bus Fuses Workplan is in approval cycle. ~ ECN 6719 - Volumetric Intrustion Detection Systems Workplan 12186 in work for civil and architectural features. Excavation is 75 percent complete and gravel installation is 50 percent complete. Completion of fence posts held for material receipt. Rework of gravel to perform microwave test in process. Results of test to determine further gravel rework. ECN 6739 - Alternate Analysis Work is in progress. There are 216 supports out of 228 on unit 2 completed. Approximately 30 additional support modifications are expected. ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits Workplan is in work. ECN 6746 - Install Fuses Workplan is in approval cycle. ECN 6749 - Replacement of Bussman KAZ Replacement with MIS-5 has begun. r ECN 6752 - Modification of P.D. (Anchor Problems) Fieldwork is complete. ECN 6758 - IIVAC Supports Work is continuing. ECN 6761 - EVR Blowout Panels Work is in progress. ECN 6768 - Rework Cable Tray Hangers Workplan is being written. t ECN 6769 - Auxiliary Air Compressor Traps Workplan was approved, awaiting material delivery. ECN 6770 - Water Spray Mechanical fieldwork completed. Writing electrical inspection criteria. ECN 6781 - Hanger-Pipe Clamps Fieldwork is in progress. ECN 6783 - Replace Motor on 2-MOV-70-87 Workplan is written. Motor delivery is expected first week of December. ECN 6'785 - Install Tee Crains Workplan is complete. ECN 6787 - Inspection and Replacement of Solenoid Valve Supports Variances submitted to DNE, awaiting their evaluation. ECN 6790 - Medium Energy Pipe Break Workplan continues in approval cycle. ECN 6805 - Replacement of Filters in Control Building and Auxiliary Building Gas Treatment System Final completion, awaiting the delivery of lock nuts. ECN 7000 - Addition of Support to Main Steam Dump Header Workplan implementation was begun. Completion is held due to DNE's inability to get ECN/ drawings issued. Dry Active Waste Building (DCR 1898) Available work complete. Remaining work held for release of drawings. Storage Building at Power Operations Training Center Building erection complete. Work in process for HVAC system. Fire protection piping held for design by POTC and material receipt. o .O ADP Additional Lights to Parking tot No. 2 (DCR 2260) Workplan 12208 written, but held for design drawings. Material Traceability Project Support was provided as requested. Procedure Revisions Many manhours were spent revising procedures (M&AI's). Rework Hut 23 for Office Complex Carpet installation scheduled for December 1 followed by cubicle installation and electrical to cubicles. Still held for material on HVAC system and smoke detectors. Control Room Bullet Resistivity - DCR 2268 Workplan initiation held for issue of ECN and drawings. Trailer Complex All electrical portable water and sewer piping complete for original 25 trailers. Work in process for cubicles and communications. Work also started on six additional trailers scheduled to arrive December 12, 1986. r
- .i D ~~
- ~._._ _ -. =.
e 9 ?? ENVIRONMENTAL QUALIFICATION (E.Q.)
SUMMARY
i l l l l t t l l e O'
e Data: 12/3/96 0041E Estimated Date of Coreletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Comments 4 EQP 8501 Disconnect I-and 2-HS-62 61 6524 Peters 11901 C C U-2 QIR submitted. EQP 8502 Replace penetrations 23 and 48 6490 Peters 11801, 11802, C C Complete QIR submitted. 11810, 11811 EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Conplete field verification sheets are in binder. No QIR needed. 1 EQP 8504 Splice methods not correct ,N/A Stockton 80 Nts C C Coglete QIR submitted. EQP 8505 Drawing N/A N/A N/A N/A N/A 4 EQP 8506 Seal containment isolation 6514 Kimsey 11880 C C valve EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C EQP 8508 JB weepholes (press) 6523 Alas 11898 C C Couplete QIR submitted. EQP 8508R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kineey 11903, 11904 C C EQP 8509R2 Conduit seals 6615 N/A N/A N/A No fieldwork remaining. j EQP 8510 Disconnect local handswitches 6527 Peters 11901 C C .l 1 EQP 8511 Submerged JB inside 6549 Peters 11901 C N/A containment c e -
r Data: 12/3/86 0041E Estimated Date of Concletion SCR No. Description ECN Engineer biorkplan No. U-l U-2 Comsments i EQP 8512R2 Rewire JB N/A Anburn 11855, 11856 C C All boxes. rewired. EQP 8513 bleep holes (moisture) 6547 Alas 11898 C C Complete QIR submitted. EQP 8513R2 bleep holes (moisture) 6565 Alas 11937 C C Conplete QIR submitted. EQP 8514 Motor insulation 74-1, -2 6540 Branhan 11906 N/A C Complete QIR submitted. EQP 8515 Replace 2-PDT-30-43 ,6554 Legg 11912 C C EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C Maint. EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C 4 i i l EQP 8518 Submerged cables 6533 Various/6 Various C C EQP 8519 Tee drains N/A Electrical N/A C C Conplete QIR submitted. Maint. EQP 8520 Expired cables 6553 Gonzalez 11902 C C EQP 8521 Delete TB and rework splices 6550 Stockton 11914, 11915 C C j EQP 8521R1 Delete TB and rework splices 6551 f EQP 8522 Rewire local pancis N/A Stockton 11914, 11915 C C i EQP 8522R2 Pewire local pancis N/A Instrument 12016 C C Maint. I i + l r
9 Date: 12/3/06 0041E Estimated Date of Concletion SCR No. Description ECN Engineer idorkplan No. U-1 U-2 Comunents EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C and misplaced brackets EQP 8524 Change setpoints 6551 Instrument 11916 C C Maint. EQP 8525 Retenninate hydrogen N/A Electrical N/A C C Completed by Electrical Maint, recatiner (MR) Maint. EQP 8526 Replace FSVs, U-l 1. U-2 11 'm52 Mechanical 11897 C C Mods. i 'e EQP 8527 Coat TB, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C (MR) EQP 8528 Solder strain gauge Barton IMI Instrument N/A C C QIR submitted 1/24. transmitters Maint. EQP 8529 PDT-30-42, -43 6554 Legg 11912 C C EQP 8530 Gasket, Namco L/S N/A Electrical N/A C C (MR) Maint. EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C EQP 8532 Delete L/S 1, 2-43-201, 6630 Alas N/A N/A No longer an issue. -202, -207, and -208 EQP 8533 Delete dual voltage splice N/A Rutledge 11866, 11853 C C
e Data: 12/3/96 0041E Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Comments EQP 8534 Resplice valve positioner N/A Maxwell fWt C C Complete QIR submitted. 3-174 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927, U-2 C C U-l 10, U-2 12 11928, U-l EQP 8536 Valve room submergence 6561 Mechanical 11939 C C Cap drains 6632 Mods. C C EQP 8536R1 Valve room submergence '6612 Electrical C C Mods. is EQP 8537 Rebuild or replace JB 3078 6579 Anburn N/A C e EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C FCO-31-475, -476 EQP 8539 Replace capacitors N/A Instrument C C Maint. EQP 8540 Replace pigtails to Target 6649 Peters C C Rock solenoid valves EQP 8541 Delete brakes 6582 Branham 11980 C N/A EQP 8542 Replace unqualified cables 6680 Hall 12/30 N/A Two cables will be replaced in I accordance with a new issue. EQP 8543 Replace J8 wire N/A Auburn-11855, 11856 C C s1
3 Data: 12/3/96 0041E Estimated l Date of concletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Consnents i l EQP 8601 Replace 1, 2-PT-1-2A, -27A; 6588 Elkins 12014 C C ) upgrade 2-PT-1-28 -278 1 EQP 8602 Reroute control cables for a "ea" "a AAAaa"a" "aaaaa****************** No 1onger an issue. 1, 2-FCV-70-87, -89 EQP 8603 Replace portion of PP7118 6627 Kimsey N/A C EQP 8604 Cable IPL3241A not qualified ,===========a====a========================a==== No longer an issue. 1 EQP 8605 1, 2-TS-74-43, -44, -45, 6589 Branhan C C e 4 ~46 not qualified EQP 8606 Undervoltage concern on 6611 Rutledge 12/24 C In work. feedwater isolation valve 6676 i M brakes i e i EQP 8607 Delete TB for 1, 2-PT-1-2A, 6626 Instrument 12014 C C l -27A Maint. EQP 8608 Enable / disable MOV brakes 6621 Rutledge C C 6622 6665 6686 j EQP 8609 Replace cable IV79138 6618 C N/A i EQP 8611 JB has weephole in top N/A Anburn N/A C i i EQP 8612 Replace zone switches 6669 N/A C I ,ei
3 Dats: 12/3/86 0041E Estimated Date of Coeletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Comments EQP 8614 Weep holes in J8 6652 C C i EQP 8615 Replace FT-72-13. -34 EQP 8617 Junction box internal wiring Mburn C C EQP 8618 Relocate arc suppression 6795 12/30 12/30 Workplan is in writing, network EQP 8619 Valve room submerged cables Holding for corrective action determination, it EQP 8620 Relocate steam generator Instrument Will roll transmitters 1800, level transmitters Maint. h EQP 8621 Resolve conduits and fittings Holding for corrective action that may be submerged in detennination. Auxiliary Building EQP 8622 Replace terminal blocks with Workplan is in writing, spliced cables EQP 8623 Replace limit switch on AA" Maaa"aaaaaaaaaaaaaaa******************** No longer an issue. FCV-3, -21 EQP 8624 Junction box 2145 may be aaaaaaaaaa" aaa*aaa aaaaaaaaaaaaaaaaaa "aaaaaa No longer an issue, submerged, unit 1 EQP 8625 6.9-kV nondivisional cables Holding for drawings, in trained trays l l t
e Date: 12/3/86 0041E Estimated Date of Coeletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Canunents N/A Move surge suppression 5773 Kimsey 11883 C C network for PORV EEB 8523 Penetration overcurrent 6606 Legg C C N/A Work FCR to delete 1, 5883 Hall C C Need SI-166. 2-PS-3-160A, -1608, -165A, and -1658 N/A Replace 1-FT-1-3A, -38, -10A,' 6347 Instrtsnent N/A C N/A -108, -21A, -218, -28A, -288 Maint. I4 NEB 8510 Relocate LT-68-320, 6439 Carrasquillo various C C PT-68-323, -320 Peters h Remount 63-71, 68-300 64 % Legg 11865 C C e Replace LS-65-4, -5 6504 Legg 11865 N/A C NES 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C Delete brakes FCV-62-61 6521 Branham 11905 C C EEB 8517 Replace pressure transmitte:- 6488 Branham 11931 C C POT-65-80, -82, -90, and -97 8 W
T O se '"TENTzongg y LEFT 8
7-1 f}:i 9 TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 December 15,.1986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC -20555 Centlemen: SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - NOVEMBER 1986 Enclosed is the November 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant. Very truly yours, TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Manager Enclosure cc (Enclosure): Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100 101 Marietta Street t.tlanta, Georgia 30323 (1 copy) Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copies) Mr. A. Rubio Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 (1 copy) INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 (1 copy) Mr. K. M. Jenison, Resident NRC Inspector O&PS-2, Sequoyah Nuclear Plant el t An Equal Opportunity Employer &}}