ML20211G445
| ML20211G445 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/31/1987 |
| From: | Dupree D, Nobles L TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8702250387 | |
| Download: ML20211G445 (64) | |
Text
4 F
TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT
. - / ?.
MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION
" JANUARY 1987" 5
UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:
L. M. Nobles, Acting Plant Manager
$00CK050goog, 87 870131 D
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4 TABLE OF CONTENTS Page
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Operational Summary 1
Performance Summary 1
Significant Operational Events 2
Fuel Performance and Spent Fuel Storage Capabilities 2
PORVs and Safety Valves Summary 2
Special Reports 2
Licensee Events 3-6 Offsite Dose Calculation Manual Changes 7
II.
Operating Statistics A.
NRC Reports Unit One Statistics 8-10 Unit Two Statistics 11-13 B.
TVA Reports Nuclear Plant Operating Statistics 14 Unit Outage and Availability 15-16 Reactor Histogram 17 III. Maintenance Summary Electrical Maintenance 18 Instrument Maintenacne 19-29 Nechanical Maintenance 30-33 Modifications 34-44 IV.
Environmental Qualification (EQ) Summary 45-51 0288f
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4 OPERATIONAL
SUMMARY
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t PERPORMANCE SUffUutY January 1987 The following summary describes the significant operational activities for the month of January.
In support of this summary, a chronological log of f_-
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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 527 days. Unit 2 has been off-line 528 days.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 01/01/87 0001E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.
i 01/31/87 2400E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration j
control updating and resolution of significant employee concerns continues.
l Unit 2 Date Time Event 01/01/87 0001E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration l
control updating and resolution of significant l
employee concerns continues.
l 01/31/87 2400E The reactor was in mode 5.
The administrative j
shutdown due to design control review, configuration l
control updating and resolution of significant employee concerns continues.
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FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during January was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
1 Unit 2 The core average fuel exposure accumulated during January was O MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.
SPENT FUEL PIT STORAGE CAPABILITIES The total storage capability in the spent fuel pit (SFP) is 1,386.
- However, l
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
SUMMARY
No PORVs or safety valves were challenged in January 1987.
SPECIAL REPORTS The following special report was submitted to NRC in January 1987.
86-09 Fire door A-10 to the containment spray pump (2A-A) pump room was not returned to functional status as required by Technical Specification (TS) 3.7.12.
Personnel noticed that the door would not adequately close during inspection. Due to frequent use, the backup plate for i
the upper hinge had broken, causing misalignment. The root cause of the failure was an improperly installed doorframe. This condition caused excessive force on the backup plate when the door was in use.
A WR was written for repairs; however, due to an implementation delay of an administrative instruction for quality materials, door A-10 was not placed in functional status within the required time.
The door was returned to functional status on January 12, 1987.
This event occurred at 1530E, December 20, 1986.
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LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in January 1987.
LER Description of Event
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1-86057 A deficiency was found during an analysis for the Design
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Baseline Verification Program in the design of two hand switches that control tornado dampers. Sequoyah failed to comply with TS LCo 3.7.7 as the result of this deficiency. A failure, causing the closing contacts of either switch to be "made-up,"
would result in a common mode total isolation of the control room emergency ventilation system. The cause of the single failure criteria requirement not being met was determined to be a personnel error by TVA's design organization. Circuit breakers were opened to maintain the dampers in their normal open positions and Abnormal operating Instruction (AOI) 8,
" Tornado Watch / Warning," was changed to restore power to the controls when manual isolation of the dampers is required.
1-86058 While maintenance personnel were performing work in the IA-A diesel generator board room, the CO2 system for that room was removed from service for safety precautions by operations and a continuous firewatch was established. LCO 3.7.11.3 was entered and, upon completion of maintenance in IA-A diesel generator board room, operations was notified that the CO2 system could be returned to service. At 1525E, the maintenance foreman observed Operations personnel checking the CO2 system and assumed the system was being returned to service and at 1545E, he discontinued the firewatch. During shift turnover at 2300E and review of the activities of the previous shift, the status of 1A-A diesel generator board room was questioned. Personnel were dispatched to determine the status of the system. The system was found out of service and no firewatch was present.
It was determined that a firewatch was not performed for approximately eight hours. This event was caused by a lack of communication between the maintenance foreman and Operations.
Also, a sign stating "out of service" had fallen from the panel i
and this may have contributed to the firewatch removal. The CO2 system was returned to normal and LCO 3.7.11.3 was exited at 2342E.
This event occurred December 18, 1986.
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LER De'cription of Event 1-86059 On December 31, 1986, at 0745C, it was determined that eight fire dampers in the diesel generator building were not being verified operable by visual inspection every 18 months as required by TS SR 4.7.12a.
This requirement should have been met by the performance of SI-233.3, " Visual Inspection of
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Penetration Fire Barriers-Fire Dampers." This error was discovered as a result of reviewing the flow diagram for the diesel generator building heating, ventilation, and air-conditioning system. During a system verification walkdown, the cause of this condition was personnel failure to incorporate the dampers in SI-233.3.
The instruction was changed to include the dampers in question.
1-86060 A CRI occurred after Operations personnel replaced the chart paper and closed the door to the main control room air intake radiation monitor recorder 0-RM-90-125.
An investigation by means of a WR revealed a loose connection on a wire lead of a filter capacitor for the 120V ac power supply to the RM recorder. When the recorder door was closed, the wire lead on the capacitor most probably made electrical contact and the vibiration from the door closing jarred the loose wire that produced EMI.
The appropriate maintenance was performed and all systems were returned to normal status.
This event occurred December 29, 1986 at 0905C.
1-86061 On December 30, 1986, the auxiliary building vent radiation monitor (0-RM-90-101) was declared inoperable due to erratic indications, and LCO 3.3.3.10 was entered at 0708C. A temporary sampler was installed by Chemical personnel after notification by Operations.
It was discovered that the sampler flow rate was not being estimated every four hours as required by LCO 3.3.3.10.
This event was the result of several personnel errors:
- 1) Lack of communication between Operations and Chemical personnel.
- 2) Operations personnel failed to ensure ccepliance with Action 41 of the LCO.
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- 3) The cancellation of SI-470.5, " Auxiliary Building Iodine i
Sampler Flow Estimation," used to estimate the flow rate.
The Chemical Group and Operations each assumed that the other group was taking the flow rate.
A WR was issued to repair the monitor. SI-470.5'has been reinstated for estimating flow rates. Personnel have been I
counseled on meeting the requirements of the LCO. Training l
instructions will be issued, and a night order was issued on the importance of communications to ensure compliance of TS.
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o LER Dercription of Event 2-86010 While performing IMI-99, " Reactor Protection System," RT-16.7,
" Response Time Test Procedure of Containment Pressure Channel III (P-935)," a containment "B" isolation ESF actuation occurred.
RT-16.7 calls for the simulation of a containment high-high pressure signal. However, this occurrence was caused
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by a deficient procedure that uses bistables to make up the ESF logic and does not place both trains of the solid state protection system (SSPS) in the " TEST" position to prevent the containment phase "B" isolation signal from causing an actual isolation. This procedure was revised to address ESF actuations during testing. These tests are performed only when a unit is in mode 5.
This event occurred on December 3, 1986 at 2311C.
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ABBREVIATIONS 1.
- Radiation Monitor (RAD Monitor) 2.
LCO
- Limiting condition for operation 3.
S/G(s)- Steam Generator (s)
-5
_y Engineered Safety Feature 4.
ESP 5.
IMI
- Instrument Maintenance Instruction 6.
SSPS Solid State Protection System 7.
ERCW - Essential Raw Cooling Water 8.
DCR Design Change Request 9.
D/G(s)- Diesel Generator (s) 10.
TS Technical Specification 11.
SR
- Surveillance Requirement 12.
SI Surveillance Instruction 13.
CVI Containment Ventilation Isolation 14.
WP Workplan 15.
CRI
- Control Room Isolation 16.
ABI
- Auxiliary Building Isolation 17.
- Electromagnetic Interference 1
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OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah offsite dose calculation manual during the month.
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OPERATING DATA REPORT
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DOCKET NO. 50-327 DATE FEBRUARY 5, 1987 COMPLETED BY D.C.DUPREE TELEPHONE (615)B70-6544 OPERATING STATUS
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UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1
NOTES:
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2.
REPORT PERIOD: JANUARY 1987 3.
LICENSED THERMAL POWER (MWT):
3411.0
- 4. NAMEPLATE RATING (CROSS MWE):
1220.6 i
5.
DESIGN ELECTRICAL RATING (NET MWE):
1148.0 j
6.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
1183.0 i
7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0 C.
IF CHANCES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS I
3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):
i
- 10. REASONS FOR RESTRICTIONS. IF ANY:
i THIS MONTA YR.-TO-DATE CUMULATIVE:
- 11. HOURS IN REPORTING PERIOD 744.00 744.00 48985.00~
- 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, 4
i
- 17. GROSS ELECTRICAL. ENERGY GEN. (MWH) 0.00 0.00 25776386.OC!
j
- 18. NET-ELECTRICAL ENERGY GENERATED (MWH)
-3433.00
-3433.00 24899126.OOr
- 19. UNIT SERVICE FACTOR O.00 0.00 48.73!
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 48.73;
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 44.2E
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 44.2E
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 38.33
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
1 l
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, j
CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT i
EMPLOYEE CONCERNS.
l NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327
-[fli UNIT : DNE DATE : FEBRUARY 5, 1987 COMPLETED BY :
D.C. DUPREE TELEPHONE :C6153870-6544 MONTH: JANUARY 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWe Net)
DAY CMWe Net) 01 0
17 0
02 0
18
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03 0
19 0
04 0
20 0
05 0
21 O
06 0
22 O
07 0
23 0
08 0
24 O
09 0
25 0
10 0
26 0
11 0
27 0
.i 12 0
28 0
13 0
29 0
14 0
30 0
15 -
0 31 0
16 0
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-327 UNIT NAME sequoyah one i
DATE February 5, 1987 COMPLETED BY D. C.
Dupree REPORT MONTH JANUARY 1987 TELEPHONE (615)870-65A4 j
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Cause & Corrective gg oyu Licensee gg go, g
'No.
Date g
gg ygg Event ug g]
Action to o
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Report #
gu gu Prevent Recurrence i
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851220 F
744 F
4 Design Control, Configuration Updating, and 1
Enployee Concerns.
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3Hethod:
Exhibit G-Instructions 1F:
Forced Reason:
S:
Scheduled A-Equipment Failure (Explain) 1-itanual for Preparation of Data B-!!aintenance or Test 2-flanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File i
D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same, Source II-Other (Explain)
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k OPERATING STATISTICS (NRC REPORTS)
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OPERATING DATA REPORT
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DOCKET NO. 50-328 DATE FEBRUARY 5, 1987 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6544 OPERATING STATUS 1.
UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 2
NOTES:
2.
REPORT PERIOD: JANUARY 1987 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (GROSS MWE):
1220.6 5.
DESIGN ELECTRICAL RATING (NET MWE):
1148.0 6.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0 8.
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 CUMULATIdE'
- 11. HOURS IN REPORTING PERIOD 744.00 744.00 40945.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE O.00 0.00 21494.42
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 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)
-6388.00
-6388.00 22561135.60
- 19. UNIT SERVICE FACTOR O.00 0.00 52.50
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 52.50
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 48.00
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 48.00
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 40.39
- 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:
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.
NOTE THAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED..
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SEQUOYAH NUCLEAR PLANT 4
AVERAGE DAILY POWER LEVEL DOCKET NO. :.50-328
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UNIT : IWO T
3 TCRUARY 5, 1987 DATE :
COMPLETED BY :
D.'C.
DUPREE
/
TELEPHONE :CS15)B70-6544 s
MONTH: JANUARY 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWe Net)
DAY (MWe Net) 01 0
17 0
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02 0
18 O
03 0
19 0
~
t 04 0
20 0
~
05 0
21 O
06 0
22 O
J' e
07 0
23 0
08 0
24 0
1 09 0
25 0
1 10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
r 14 0
30 0
15 -
0 31 0
16 0
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e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-328 UNIT NAME Sequovah Two DATE February 5, 1987 COMPLETED BY D.
C. Dupree REPORT MONTH JANUARY 1987 TELEPHONE (615)S70-6544 4
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' No.
Date g
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$55 R
9 850821 F
744 F
4 Design Control, Configuration Updating, and Employee Concerns.
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4 2 Reason:
Method:
Exhibit G-Instructions 8F:
Forced S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Ilaintenance 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 (NUREG-0161)
E-Operator Training & License Examination Outage F-Aelministrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Sam, Source II-Other (Explain)
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..~ e OPERATING STATISTICS (TVA REPORTS) l
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TVA M82A (Dr@+80 NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant 744 Month JANUARY 19 87.
Period Hours Item No.
Unit No.
UNIT ONE UNIT TWO PLANT ^'
1 Averace 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
5 5
Gross Electrical Gen., MWh 0
0 0
5 6
Station Use, MWh 3,433 6,388 9,821 h
7 Net Electrical Gen., MWh
-3,433
-6,388
-9,821 b
8 Station Use, Percent N/A N/A N/A 9
Accum. Core Avg. Exposure, MWD / Ton 1 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 y
16 Turbine Avail. Factor. Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 g
C 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 0
20 Unit Avail. Factor. Percent 0.0 0.0 0.0 21 Turbine Startuos 0
0 0
22 Reactor Cold Startuos 0
0 0
23 g
24 Gross Heat Rate, Btu /kWh N/A N/A N/A 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 I
34 35 36 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416
.Q 39 Oil Fired for Generation, Gallons 1.980 2
40 Oil Heatina Value. Otu/ Gal.
138.000 41 Diesel Generation. MWh 30 47 Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor %
3 43 N/A N/A N/A N/A N/A N/A Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.
j 2(t) indicates Thermal Energy.
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s TVA 6%0C (PP-3 76)
UNIT OUTAGE AND AVAILABILITY SEOUOYAH Nuclear Plant Licensed Reactor Power. 3411 MW(th)
Unit No.
ONE Generator Ratingl220.5 MW(e)
Month / Year JANUARY 1987 Design Gross Electrical Rating 1183 MW Period Hours 744 F
UNIT Time Unit Available Time Not Available CORRECTIVE ACTION Time Time SHU NO
^W OUTAGE CAUSE TAKEN TO PREVENT Total Gen.
Not thed Turtune Gen.
Reactor Unet Out in DOWN DURING REPETITION Day Mrs l Men Mrs ! Min Mrs ! Men Hrs i Man Mrs l Min Hrs l Min Mrs lMm Mrs ! Min Hrs ! Mm REACTOR OUTAGE Design Control, Configuration N/A Mode 5 1
00 i OO 00 l00 l
24800 24800 24 iOO 24 s00 i
i 2
00 ! OO 00 t 00 t
24 ' 00 24l00 24 t00 24 !00 8
Updating, and Employee Conceris 3
00 l 00 00 800 e
24 00 24100 24 300 24 ;00 4
00 i OO 00 l00 l
24800 24 ' 00 24 !00 24 800 I
e 5
00000 00 100 i
24 8 00 24l00 24 l00 24 !OO I
6 00000 00 000 1
24' 00 24500 24 !00 24 iOO 7
00 ! 00 00 '00 24l 00 24!OO 24 l00 24 000 I
8 00 l 00 00 '00 l
24s 00 24 i OO 24 soo 24 IOO e
9 00 l 00 00 i OO i
24 ! 00 24 8 00 24 ! OO 24 800 I
10 00500 00 800 1
24 00 24 l 00 24 500 24 !00 II 00800 00 00 l
24 8 00 24100 24 100 24 iOO t
3 12 00 8 00 00 l00 1
24! 00 24!00 24 l 00 24 100 t
i l
13 00!00 00 i 00 24' 00 24l00 24 i OO 24 !OO i
1 14 on ; nn on 8 no 24 l nn 24 i nn 24 8 00 24 lOn i
24 8 00 24 ' 00 24 l 00 24 100 t
i 15 0n : 00 00 !00 i
16 on t on 00 ! 00 i
24 00 24500 24 !OO 24 f00 I
17 008 00 00 l00 24 00 24!00 24 l00 24 !00 t
18 00!00 00 s00 l
24! 00 24l00 24 8 00 24 l00 s
19 00l 00 00 100 e
24 i 00 241 00 24 iOO 24 iOO 20 no nn 00 1 00 8
24! 00 24! 00 24 !00 24 800 i
l 21 00 i 00 00500 l
24l 00 24t00 24 l00 24 100 e
i 22 001 00 00100 i
24 3 00 24 ! OO 24 s00 24 !00 t
23 00! 00 00100 8
24 ! 00 24i 00 24 IOO 24 500 8
24 00 l 00 00 !00 24 t 00 24 ! 00 24 i OO 24 t00 a
25 00;00 00 #00 t
24' 00 24l00 24 '00 24 800 i
26 On i 00 00000 1
24l 00 24s00 24 l00 24 100 t
i 27 on 6 nn 00 ! no l
24 8 00 24Ino 24 800 24 !00 t
i 28 00 0 00 00000 e
24! 00 24!00 24 l00 24 l00 29 00! 00 00!OO I
24 0 00 24 00 24 ? 00 24 i00 30 nn ; on on i on l
24 l 01 241 00_JOQ_,1 I Q i
e i
31 00s 00 00 s00 i
24i 00 244 00 24 !OO 2
00
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i Total 00800 00 {00,
7444 00 744! 00 744 j00 7_A4 l00 XXXX Z
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TX
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J TVA 6560C (PP-3 76)
UNIT OUTAGE AND AVAILABILITY SEQUOYAH Nuclear Plant Ucensed Reactor Power _JEMW(th)
Unit No.
TWO Generator Rating 1220.5MW(e)
Month / Year ' JANUARY 1987 Design Gross Electrical Rating 1183 MW Period Hours 744
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METHOD OF UNIT CORRECTIVE ACTION Terne unet Available Time Not Available SHUTTING STATUS Teme Tm OUTAGE CAUSE TAKEN TO PREVENT Totar cen.
Not Uwd Turtune Gen.
Reac tor Unit Out in DOWN DURING REPETITION DAY Hrs ! Man Hrs ! Man Hrs ! Man Hrs i Min Hrs l Min Hrs [ Man Hrs ! Min Hrs ! Min Hrs I Men REACTOR OUTAGE I
00i 00 00l 00 I
24' 00 24' 00 24i 00 24s00 i
e Desian Control, ConfiRuratior N/A Mode 5 2
00 00 00i 00 1
2 4 ', 00 24l 00 246 00 24 ! 00 3
Updatina, and Employee Concerns 3
3 00 00 00* 00 24; 00 24i 00 248 00 24 ; 00 l
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00i 00 00; 00 24: 00 248 00 24! 00 24 00 i
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MAINTENANCE
SUMMARY
(INSTRUMENTATION) h 6
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INSTRUMENT MAINTENANCE MONTHLY REPORT FOR JANUARY 1987 COlm0N 1.
Initiated Software Change Request SQ-87-P250-001 to revise scaling on P250 computer log point F2701 (1-F-30-150) and F2701 (2-F-30-165).
This change is in accordance with ECN-5125 (unit 1) and ECN-2824 (unit 2)
-([ l that changed the present flow range of 0-10,900 CFM to a new flow range of 0-9,000 CFM.
2.
Responded to Regulatory Licensing regarding questions raised by NRC during the inspection on WP-ll554. This workplan replaced transmitters 1-and 2-PDT-30-44, and -45 in accordance with ECN-6369. All questions were answered and the open items closed.
3.
Received all nine Barton 764 transmitters order on Requisition No. 371523. These transmitters are required to replace all four containment sump level transmitters on unit 1 before unit 1 startup.
All nine transmitters have the modified double 0-ring style differential pressure unit as recommended for this application. Transmitters were in place in nonconformance status because of insufficient information on the Vendor Quality Release.
4.
Revision to SI-196, " Periodic Calibration Of Upper Head Injection System Instrumentation (18 months) - Units 1 And 2," was issued to begin 30-day performance for upper head injection (UHI) valve response time. This is to verify operability and gain system confidence.
5.
DCR 2302 has been submitted to replace the current commercial grade Masoneilan 8005A motor-driven auxiliary feedwater control level modifiers with fully qualified nuclear grade Masoneilan level modifiers. These modifiers are being removed from the 10 CFR 50.49 harsh environment list, but are still IE electrical devices and are required to be purchased QA Level I.
6.
PRO 87-041 was initiated to determine if response time testing of the emergency gas treatment system fans discharge flow control valves is necessary. The initial evaluation by Instrument Maintenance determined that the total system response time is measured, therefore, the response time of the valves is not necessary. Additional investigation will be coordinated with the Plant Operations Review Staff.
7.
The Qualified Maintenance Data Sheet requirements for Tobar transmitters (IpT-001) were implemented and verified for EQ Binder SQNEQ-IPT-001.
i i
8.
The Eberline technical representative completed requirements of service contract 87NLE-38311 by assisting in placing Eberline post accident radiation monitoring system in working order.
i 9.
Category "D" FCR-5045 was submitted to correct the detector and radiation analyzer range discrepancy on 1, 2-RM-90-280 (post accident sampling room area radiation monitor).
l l
- w INSTRUMENT MAINTENANCE MONTHLY REPORT FOR JANUARY 1987 UNIT 1 1.
The static-O-ring UHI switches were returned to Sequoyah after factory modification and calibration in accordance with IE Bulletin 86-02.
These switches will be installed prior to unit 1 startup.
'r_-
2.
During the performance of SI-227.1, " Post Maintenance Response Time Test Of Reactor Trip Breakers RTA And RTD, Units 1 And 2," an inadvertent reactor trip was generated. PRO l-87-032 was initiated and evaluated.
The root cause determination was a personnel error.
i UNIT 2 1.
Special reports on investigations and corrective actions were submitted on the following:
A.
Refueling water storage tank wide range level transmitters -
failures during heavy rainfall on December 9, 1986.
B.
Reactor vessel level instrumentation system - misplaced circuit card 1 *
- -L.
_.. _ _ _ ~
IN;TRUMEET h4IhiENANCE 30HTHLt StdMARY 02-04-97 PACE 1 CCHP cR COMP U FUNC SYS ADDRESS. DATE.. DESCRIPTION............
...... CURRECTIVE ACTION....
[11c124 2 FJS 003 174 G1/09/C7 2-P03-003-174-B,E*NPRDx],NEED HIGH TEMP UNKNDWN. INSTALLED NHIGli ten? CASKET CASKET WHERE RELAY MOUNTS TO POSITIDhER.
P/M 06018S-015-678 0116925 2 FUS 003 175 01/08/07 2-P03-003-175-A ENNPRDx],NEED HIGH TEnP UNKNOWN. INSTALLED HIGH TEMP GASKET E413 GA3 VET WHERE RELAY MOUNTS TO POSITIONER UPDATE !! WITH WR B212956 00TH PERf02nED P/M 060188-015-678 AT THE SAME T!nE 0120149 0 TC 234 SN 1333C 01/23/e7 0-TC-234-3N 13338, CONTROLLER HAS UNKNOWN. BEYOND REPAIR. TRA3NED.
INTERMITTER SWITCHING PRCOLEn. REPAIR OR WRIC-120149.
REPLACE AS NECESSARY 0120515 0 TC 234 003 01/21/87 0-TC-234-003,TC RED ON LAMP IS IN-DP DEFECTIVE GREEN AND RED LAMP. INSTALLED REPAIR / REPLACE. FOUND DURING PEr Dr PHI SPARE CONTROLLER. REPAIRED ORIGINAL AND 234 PLACE IN STORAGE. WRIC-120515.
[120517 0 TC 231 010 01/21/07 0-TC-234-010,TC RED LAMP I: IN-OP DEFECTIVE RED AND GREEN LanP. INSTALLED REPAIR / REPLACE FOUND FURING PERf 0F Pnl SPARE CONTOLLER. REPAIRED ORIGINAL AFD 234 PLACED IN STORAGE. WRt1250517.
0120510 0 TC 231 011 01/23/S7 0-TC-234-011,TC GREEN OFF LAMP IN IR-UP DEFECTIVE GREEN LAMP. INS TALLED 3 PARE.
REPAIR / REPLACE FOUND DURING PERf Of PMI' REPAIRED ORIGINAL AND PLACE IN STORAGE.
234 WRID-120518.
E120520 0 TC 234 014 01/21/C7 0-TC-234-014,TC WILL NOT CHANGE STATES DEFECTIVE RED AND GREEN LAMP 3.
3 REPAIR / REPLACE FOUND DURING PERf 0F Pn! INSTALLED SPARE CONTROLLER, REPAIRED 234 ORIGINAL AND P, LACED IN STORAGE.
WRfB-120520.
1120650 0 P!PG 025 01/27/87 0-PIPG-026-, REPLACE BROKEN 1/2" PUC ACHORMAL STRESS. INSTALLED NCW SWITCl!
NIPPLE SCH 80 IN BOTT0n Dr SWITCH DN DELUGE ULU 0-26-1088 E123849 0 TC 234 0112 01/27/C7 0-TC-234-0112-3,TEnP CONTROLLERS RED DEFECTIVE RED LAMP. INSTALLED NEW LAMP II FLASHING REPAIR OR FEPLACE CONTROLLER CEPAIRED ORIGINAL AND PLACCD IN STORAGE 0125762 1 X:
092 000?4 01/27/E71-Xn-092-5003A,THE SOURCE RANGE N-31 IS N0!!Y LOM UDLTAGE POWER SUPPLY. REPLA:ED ERRATIC AND UNRELIABLE POWER SUPPLY P126869 0 TC 234 60 01/27/C7 0-TC-234-80,CVC NEAT TRACE DIST PNL UNKNUWN. AFTER TROUCLESH00 TING WROTE TO POINT 16 CET 80 TEMP INDICATOR - 128 ELECTRICil nAINTENANCE DEGREE F $HOULD SE 145 DEGREE F C121625 0 TC 234 0053 01/27/67 0-TC-234-0053-3, TEMP CONTROLLER RED LAMP DEFECTIVE RED AND GREEN LAMP. INSTALLED IS BURNED OUT REPAIR / REPLACE NEW DEUICE REPAIRED GRIGINAL AND.PL9CED IN STORAGE C127626 0 TC 231 c222 01/23/97 0-TC-234-0222, TEMP CONTROLLERS-RED LAMP DEFECTIVE RED LAMP AND REL AY.
INSTnLLED FLASHES SPARE. REPAIRED ORIGINAL AND RETURMED 10 STORAGE. WR80129626.
li B129629 0 TC 234 0117 01/23/E7 0-TC-234-0117-5, TEMP CONTPOLLER WILL NDT DEFECTIVE GREEN LAnP AND RELAY.
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SWITCH DN GREEN LAMP DN REPAIR / REPLACE INSTALLED SPARE. REPAIRED ORIGINAL AND r
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SUMMARY
02-04-87 FACE 3 COnP
~
- R. COMP U FUNC STS ADDRESS. CATE... DESCRIPTION.........
............. CURRECTIVE ACTION.....................
LIGNT! REPAIR GR REPLACE AS HECE!!aRY RECALIBRATED ORIGINAL AND PLACED IT IN SPARE STATUS E203171 0 TC 234 '
663 01/27/67 0-TC-234-663, CONTROLLER HAS NO RED CR DEFECTIVE TEMP CONTROLLER. REPLACED WITH GREEN LIGHTS REPAIR OR REPLACE AS 3 HOP 3 PARE NECESSARY i
E203173 0 TC 234 563 01/27/G7 0-TC-234-523, CONTROLLER HA3 NO RED OR DEFECTIUE CONTROLLER. INSTALLED 3HO?
GREEN LIGHTS REPAIR OR PEPLACE A3 SPARE NECESSARY E205952 0 IC 234 40 01/23/67 G-TC-234-40-3, RED LIGHT DN FRONT DF DEFECTIVE RED LAMP, C4 CAPACITOR ANS C0HTROLLER !$ FLASHING REPAIR AS RELAY. INSTALLED SPARE CONTROLLER.
NECESSARY REPAIRED ORIGINAL AND PLGCE IN STORAGE.
WRIC-205952.
1205953 0 TC 234 64 01/27/C7 0-TC-234-64-3, RED LAMP DN FRONT OF CEFECTIVE RED LAMP. INSTALLED NEW CONTROLLER WILL NOT LIGHT REFAIR AS DEU!CE. REPAIRED ORIGIN.1L AND PL ACE 0 IK NECESSARY STORAGE E200002 0 TC 234 117 01/13/97 0-IC-234-117-P, GREEN LIGHT !! GN UNKNOWN. SPARE WAS INSTALLED. GRIGINAL CONTROLLER WILL NOT CHANGE STATES
- WA3 TESTED AND NO PROCLEn W43 FOUND.
PLACED IN STORACE. URfD-208002.
],
L208003 0 TC 238 190 G1/27/67 0-TC-234-190-P. GREEN LIGHI UN FRONT CF DEFECTIVE CAPACITOR AND EEALAY. REPLACED l
[j CONTROLLER IS ON CONTROLLER WILL NOT CAPACITOR AND RELAY AND PLACED IN EHANGE STATES STORAGE INSTALLED SPARE IN ITS STATE E20E005 C TC 234 0046 01/21/C7 0-TC-234-0046-3, TEMP CONTROLLER WILL NOT DEFECTIVE C14 CAPACITOR AND RELAY. I SWITCH SREEN COMP STAY 3 ON REPLACED CAPACITOR AND RELAY IN ORIGINAL. INSTALLED 3 PARE IN THE CIRCUIT. URIB-200005.
E20802; O F3 065 5SA/D 01/27/87 0-FS-065-55A/E-A,FOUND SWITCH 3 DEFECTIUE CIRCUIT BOARD. REPLACED INOPERATIVE POWER SUPPLY ON CIRCUIT CIRCUIT BO4RD RECALIERATED BOARD FAILED.
0203353 2 FE 0 30 0196 01/27/07 2-FE-030-0196-B, FLOW SWITCH IS NOT SETP'0 INT'FOUND AT 579 MILLIVOLTS WHICH WORKING PROPERLY, REGAUR PAIR OR REPLACE IS OUT OF INSTRUDENT TOLERANCE BUT A3 NEEDED WITHIN TDLERANCES DUTLINES IN 3ECTION 6.0 0F SI 195 0209337 0 TR 082 5036/3 01/14/87 0-TR-002-5036/3-A,00E3 NOT APPEAR TO BE BROKEN CONTACT BRUSH ASSEMBLY. REPLACED SEEING INFUT SIGNAL CONTACT BRUSH ASSEMBLY 020?339 0 P3 082 270 01/10/37 0-P3-022-270,FIX COMPRE30R FAILS TO A 3 CREW WAS LOGED IN THE SWITCN AUTO START 250 PRIG X PRE 35UR MAY EE AT MECHAN!!M. REMOUED 3 CREW RECALIBRATED FAULT 021009~ 2 Tn 068 380E 01/27/67 2-TM-068-3SOE, CARD WILL NOT CALIBRATE DEFECTIVE CARD. INSTALLED NEW C ARD.
WRSC-210092.
C210099 2L 068 3718 01/14/C7 2-Ln-068-3718-E,!03PECT A3 PE!!! TOR UHKNOWN. INSTALLED CURRECT RESISTOR R294-0 13 WRONG ULU REPLACE WITH 50 K d, t, i
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6 MAINTENANCE
SUMMARY
(MEC11ANICAL)
O w
i MECHANICAL MAINTENANCE MONTHLY REPORT FOR JANUARY 1987 COlWON 1.
Continued Grinnell valve diaphragm replacements.
2.
Completed walkdown of instrument line clamps.
3.
Repacking "NB" ERCW pump - replacing sleeve.
4.
Developing action plan for repairing control building roof.
5.
Continued rebuilding "B" waste gas compressor.
6.
Resolving hanger bolt tightening deficiencies.
7.
Rebuild "B" station service air compressor (preventive maintenance).
8.
Installed crankcase pressure detector baffle in IA2 diesel generator.
UNIT 1 1.
Began steam generator row 1 tube U-bend stress-relieving.
2.
Inspected feedwater piping as a result of Surrey incident.
3.
Replaced IB stator cooling water pump.
UNIT 2, 1.
B'.gan glycol outage - various valve repairs.
2.
Inspected feedwater piping as a result of Surrey incident.
3.
Continued Grinnell valve diaphragm replacement.
4.
Continued procedure review / revision for restart.
5.
Continued operational readiness review activities.
6.
Replaced 0-rings in 2AA containment spray pump.
I n
l i
l,
ECHAllICE CINTDMCE lEBITEY Sl5ElARf
$2-02-87 PAGE 1 CIBF O. CMP U FUE SYS ADDK33. ME.... K3CRIPTHN............................. COMECTIVE ACTIIBl.......................
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, B210i?S 2 PCY 001 M2312/12/84 2-PCY401-M23-A,CmHPRDu3,EPAN LEAK! IINN DIAPilRAGil DE TD HEAT MD AGE.
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I B21097d 2 PCY 001 M1212/12/84 2-PCY-0014012-B,CmMPilDu], REPAIR LEAK! 11121 DIAPHRAGil DUE TO EAT MD AGE.
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RECHAllIQll CINTENANCE IDITRY 315EINY
$2-02-87 PAGE 2 Cgy
[Q. CBF U FUK SYS ADDEst. DATE.... K3CRIPTHN............................. C MRECTIYE ACTIml.......................
E DIAPIBM F YALUE. EPLACE R A04ti INSTELD NEU DIAPHRACH, PDFW8ED PACKIIIC AllD GREASE STEM 31-144.4 B21M77 2 PCY M1 M1212/1V84 2-PCY-401-M12-B,EuMPRDu),RY SIG IS PACKING TD TIGitT. AD.RISED PACKING, STICKING LIBRICATED STEM Ale AD.Rl!TD SPRING TENSI51. PEEDRED 31-144.d AB ETIINED
'g TO 3 GYICE.
B211055 1 PHP M2 000181A 01/05/971-PIF-002-0001814 -B.CulrRDu3,TinD SDAK DUT F EIGIEElli.
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INSTELD NG YAE3 $
AS E M SSARY BELTS B214621 0 RY 047 072dA 01/27/97 6-RY-047-072dA-A,EuMPRDN3,RY It l1551 lHINGS Am MAT. CLEAED STUD 3 AND LEAKIllG THERIGli BAD LEAKIliG ET THE SEATE AIS IllSTAllD EN 3GL RIIIG BACK BOTTDM PLATE EPAIR liHEN K-A Puff SHAFT UP SEAL AW 200G CARET CIECKD FM
.I! EPLACED LEAKS AIS ETURED TO SERVIE B218771 1 RY 042 1043 01/27/871-RY-042-1043-A, HAND UHEEL TURN EL TE 11121 INTERES. INSTRLED N01 D-RING AND li4Y TO RY BUT EY lim'T DPEN DIAPHRAGN.
21 records listed.
"B202120" not found.
4
KCiNI0t. CINTDIAllCE lEBITRY Si3IIARY 02-02-87 PACE 1 Cw CRti U fullC SYS A00K33. DATE.... KSCRIPTION............................. CDERECTIYE ACTIN.......................
B202120 0 EV 002 0501-2A1 W17/84 0-RY-002-0501-2A1-A.CalFR0m],nIn RELIEF EV ON llAlle F 0/C AIR COMPRESSR 2A1 LIFT! 1801 KCEIER PRES $1NIE IS 2850 the record listed.
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'T21M7d" not found.
'9210 77" not found.
'9210915" not found.
'9212438" not found.
'921;;73" not found.
'9214305" not found.
'9211055" not found.
'S20d220" not found.
'121 '72" not found.
'T205011" not found.
'11240'I2" not found.
'1120A3" not found.
'12004A" not found.
'1120d%" not found.
'1120A2" not found.
"B1231%" not found.
'?209585" not found.
'9218711" not foun4.
'1202150" not found.
'S214d21" not found.
'9201334" not found.
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MAINTENANCE
SUMMARY
(MODIFICATIONS) l i
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SUMMARY
OF WORK COMPLETEb n', s 3
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MODIFICATIONS - CURRENT STATUS 4
- s%., ~.,
JANUARY 1987 N.x r,
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']p APPENDIX R ECN 6300 - Additional Sprinklers and Draft Stops 6
3 The draft stop workplan continues in work, and the s i
workplan has been approved with work just 'snrtiris!' prinkler e,
Workplans for the electrical portion being rewritten.
'. j' m,
ECN 6311 - Operator Extension on PORV
~'
3 This work has been completed except for final cycling at startup.
,,, x ECN 6319 - High-Pressure Fire Protection Rework
(
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Workplan is in work.
c OTHER ITEMS
'i 5
.N
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~-
ECN 5435 - Fire Doors s.,
The installation of weatherstripping continues as resotirees. permit:s
,w s
ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of unit 1 isolation valves is s
approved. Some insulation activities remain incomplete.
ECNs 5034 and 5743 - Various Platforms in Lower Containment J
Because of new weld inspection requirements, Modifications Group B is waiting on DNE to furnish inspection requirements on tack welds to hold down grating. Additional safety gates are to be installed on unit 2.
The workplan for this is in the approval cycle.'
ECN 5111 - Remove Power From Old Carpenter Shop at Dry Active Warte Building Modifications Group C is holding the completion of this ECN until the completion of the Dry Active Waste Building.
Power is needed for construction power. -
a
e ECN 5111 - Provide permanent power to manholes 42-46.
Electrical conduit and wiring installation for manholes 44, 45, and 46 complete per Workplan 12262. Manhole 42 and 43 held for information from DNE
-r.*
on power cable routing and terminations.
ECN 5599 - Conduit Supports for Fifth Vital Battery and Waste Disposal Area Workplan 12186 in hold for fifth vital battery area supports.
Information needed from DNE on flex conduits. Workplan for waste disposal area held for issue of ECN by DNE to include FCR 4753.
ECN 5609 - Air Compressors Makeup Water Treatment Plant Air compressors and mechanical piping complete except for tie-in to headers which is held for issue of electrical drawings.
ECN 5609 - As-Construct Makeup Water Treatment plant Drawings per SQ-DR-86-03-61R Complete.
~
ECN 5626 - Containment Ladders Unit 1 Workplan being written to 1ncorporate this ECN.
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. Signs have been installed in all areas except high radiation areas, and coordination with HP continues to gain access to these. Work continues on unit 1 wall supports.
ECN 5713 - Various Platforms in Lower Containment The remaining trollies have been shipped to the vendor for modification. Work will continue when the trollies are returned.
ECN 5724 - CVCS/RHR Supports Final inspections remain incomplete for last hanger on unit 1.
! a
ECN 5743 - Ladders In Containment A workplan to insure additional safety gates was prepared and placed in the approval cycle.
ECN 5855 - Replacement of Doors A56/A57 The workplans remain in the review cycle.
ECN 5880 - UNID Tags for Class IE Fuses Fleid verification of Class 1E fuses and penetration cable protection is approxmately 95 percent complete. DNE to issue fuse listing and drawings before remainder of the work completed.
ECN 5935 - Correct Power Block Lighting Deficiencies Workplan initiation held for release of drawings by DNE.
ECNs 5938, 6305, and 6571 - Replace Feedwater Heater and Eroded Pipe Modifications Group B is supporting postmodification testing (PMT) on heaters 1 and 2 on both units as requested.
Insulation work on unit I continues.
Installation of the monorail on unit 2 continues in preparation for the changeout of feedwater heaters 3 and 4.
Structural steel reinforcement continues on unit I heaters 3 and 4.
ECN 6014 - Replacement of ERCW Pump Bearing Piping PMT requirements have been resolved and work is ready to resume.
ECN 6057 - Cable Tray Covers This work on hold pending evaluation of cable tray efforts with respect to cable ampacity.
ECN 6147 - Airlock Packing Nut 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 PMT is incomplete sad scheduled for startup.
. o i
ECN 6204 - Electrical Penetration 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 Work was completed for unit 2.
ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement cleanup and reinsulation is continuing.
ECN 6380 - Replacement of Barton Pressure Transmitters The unit I workplan continues in the approval cycle.
ECN 6357 - ERCW Roof Access and Rails for Security Equipment Workplan 12238 held for DNE approval of FCR showing installation details. DNE has promised 2/20/87 to release FCRs.
ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan 12223 in process pending safe access to current transformers.
ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation In-service tests will be performed when the system is brought up to temperature and pressure.
ECN 6455 - Upgrade CU-3 Box Battery Packs Workplan in approval cycle.
Engineer attempting to locate material purchased by DNE several years back.
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 Road
- Work is being held pending the release of drawings from DNE. -
a
ECN 6556 - Replace Solenoid Hangers and Limit Switches Fieldwork is complete. Lack documentation only.
FCR to complete
~T unit 1 workplan.
ECN 6601 - Removal of Unit 1 EGIS Backdraft Dampers PMT remains to be completed by the Engineering Test Section.
ECN 6610 - Modify Air Return Fan Supports Unit 1 work is incomplete.
ECN 6661 - Upgrade of ERCW Piping Piping was reworked. NDE is required for existing welds. This will be completed upon receipt of DNE information.
ECN 6687 - Additional Office and Medical Facility Modification to medical facilities complete except lead lined doors for x-ray room. Vendor having problem obtaining material for doors.
ECN 6687 - South Central Bell Environmental Unit (SCBEU)
Complete.
ECN 6689 - Relocation of Mainsteam PORV Functional test and final calibration held for installation of positioner due 2/24/87. Additional mechanical work for unit 2 is.
required since the original design would not work. This work will begin upon receipt of design information.
ECN 6698 - Repull 120-Volt Cables All cables have been pulled. Workplan on terminations has been on hold due to availability of manpower.
i ECN 6701 - Modify Foxboro Recorder Latches l
Fieldwork is on hold. Completion delayed due to material which is on order.
ECN 6706 14 Support Enhancement l
Fieldwork completed on unit 2 and in progress on unit 1.
Initial l
- inspections for unit 1 lack approximately 100 supports from completing. Unit 1 evaluations are continuing.
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ECN 6707 - Replace System 74 Flow Switches First train is installed. Calibration equipment has been returned to vendor for rework. Estimated return of calibration equipment is
~f now unknown.
ECN 6715 - D/C Random Loads Train B is complete. Train A is on hold due to availability of equipment.
ECN 6717 - Stub Bus Fuses Workplan is in work.
ECN 6719 - Volumetric Intrustion Detection Systems Workplan 12186 in work for civil and architectural features.
Workplan 12278 approved for conduit installation only. Excavation and grading approximately 90% complete. Material received.
ECN 6720 - Crane Consistency Program Initiation of workplans holding for design and/or vendor information. Only 29 of 59 drawings for polar crane modification received.
ECN 6739 - Alternate Analysis Work is in progress. There are 248 supports out of 271 on unit 2 completed. Additional support modifications ere expected.
ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits Workplan is being worked in parallel with ECN 6698.
ECN 6746 - Install Fuses Workplan is in approval cycle.
ECN 6749 - Replacement of Bussman KAZ This ECN will be superseded by ECN 6854. Wordplan 12152 will be closed and Workplan 12328 will be written to replace KAZ to MIS-5 to FLAS 5 Fuses. Awaiting DNE drawings and new fuses.
ECN 6752 - Modification of P.D. (Anchor Problems)
Mechanical fieldwork is complete. Some conduit rerouting remains incomplete.
~
ECN 6757 - Ice Condenser Valve Supports This work was completed.
._,,- {_:
ECN 6758 - HVAC Supports Work is complete for both units.
ECN 6761 - EVR Blowout Panels The workplan for unit 1 continues in the approval cycle.
ECN 6762 - Modify Hanger NCR CEB8615 The workplan was written and placed in the approval cycle to modify one hanger.
ECN 6763
. Add Fuses to Flow Switches Workplan is complete.
~
ECN 6768 - Rework Cable Tray Hangers Workplan is being written. Drawing delivery is holding up completion of workplan.
ECN 6769 - Auxiliary Air Compressor Traps Fieldwork was ccmpleted on one compressor. Work on the remaining compressor is being held for material delivery unassociated with-this modification.
ECN 6783 - Replace Motor on 2-MOV-70-87 This ECN is superseded by ECN 6858 which will resear the MOV instead of replace the motor.
ECN 6787 - Inspection and Eeplacement of Solenoid Valve Supports Field work is in progress.
ECN 6790 - Medium Energy pipe Break The spare penetrations have been sealed. Work has not started on others.
I ECN 6802 - Modify EGTS Filter Housing Work was started on the first housing and is continuing.
ECN 6805 - Replacement of Filters in Control Building and Auxiliary Building Gas Treatment System Fieldwork completed. DNE will issue EQ radiation drawings later.
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ECN 6808 - Conduit Seals Workplans being written to incorporate this ECN.
ECN 6809 - MSVV Insulation The workplan for insulation was approved and work started. The screen design was cancelled and a new modification on the doors was started.
ECN 6810 - Rework Category "C" Devices First workplan is in work; second workplan is in approval cycle.
ECN 6811 - Replace Breakers Writing workplan held for issue of ECN and drawings.
ECN 6812 - Backup Control Room Cable Reroute Writing of workplan held for issue of drawings by DNE.
ECN 6820 - Reset Breakers Workplan being written to incorporate this ECN.
ECN 6821 - Screens for RCPs The workplan was approved and work started.
ECN 6822 - Add Fuses to Flur Mapping System Workplan is in approval cycle.
ECN 6823 - MSV7 Hot Pipe Remedy All cable removed. Workplan for replacement is in work.
ECN 6824 - Replace PS and TS SYS 32 Workplan issue for approval held for drawing issue by DNE..
ECN 6826 - Ice Condenser Drains
~ 'i The workplan was written and placed in the approval cycle.
ECN 6829 - Modify Control Building Fire Dampers Writing the workplan is just beginning.
ECN 6835 - Ampacity First two cables are pulled.
ECN 6853 - Installation Of Curbs And Drains For Containment Recirculation No design has been received.
However, Modification Engineers are working with DNE to ensure adequate design.
ECN 7000 - Addition of Support to Main Steam Dump Header Field work is complete except final inspections during heat up.
ECN 6848, 6851 - Thermal Movement of Civil Structures Preliminary design received. Writing of the workplan has started.
ECN 7078 - Install Hangers - Main Steam Piping No design available. However, Modification Engineers are working with DNE to ensure adequate design.
Dry Active Waste Building (DCR 1898)
Available work complete. Remaining work held for release of ECNs and drawings.
Storage Building at Power Operations Training Center Complete.
ADP Additional Lights to Parking Lot No. 2 (DCR 2260)
Workplan 12208 written, but held for design drawings.
Procedure Revisions Many manhours were spent revising procedures (M&AI's).
9.
Rework Hut 23 for Office Complex Complete.
,_ _.- i Control Room Bullet Resistivity - DCE 2268 Workplan initiation held for issue of ECN and drawings.
Startup Activities List SAL Closure - Many manhours spent closing these items. More comments from Mike Harris.
O W
e 1.
O MODIFICATIONS COMPLETE ECN DCR SYS UNIT DESCRIPTION L5565 D0795 244 0
Inplant repeaters and common plant antenna system.
~1. -
L6597 D0972 030 2
Add vent line on static-O-ring temperature switches 1-TS-30-186, -187, and unit 1 and 2 TS-30-194, -195, -196,
-197, -201, and -202.
L6645 F4264 090 2
Change the range on unit I and 2 radiations monitors RM-90-275, -276,
-277, and -278 from 10-10.5 mr/hr to 10.1-10.4 mr/hr.
L6702 D2259 067 2
ERCW change physical drawings to show TVA Class B valves 2-67-579A, -579B, -579C, and 579D.
L6737 F4541 014 0
Changeo:.t of NRWT flow to cooling tower blowdown indicator 0-FI-14-466 with a flow indicator with range of.55 to 5.5 gph and documentation changes.
L6797 D0972 991 2
Back out splices for ECN-L6729 and replace the existing TB (2-TB-991-1505) with a qualified TB.
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o ENVIRONMENTAL QUALIFICATION (E.Q.)
SUMMARY
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Estimated Date of Coneletion SCR No.'
Description ECN Engineer Workplan No. U-1 U-2 Comnents EQP 8501 Disconnect 1-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
Conplete 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.
EQP 8504 Splice methods not correct N/A Stockton 80 MRs EQP 8505 Drawing N/A N/A N/A N/A N/A EQP 8506 Seal containment isolation 6514 Kimsey 11880 C
C valve
'u EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C
EQP 8500 JB weepholes (press) 6523 Alas 11898 C
C Conplete QIR submitted.
EQP 8508R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C
EQP 8509R2 Conduit seals 6615 N/A N/A N/A No fieldwork remaining.
EQP 8510 Discorinect local handswitches 6527 Peters 11901 C
C I
EQP 8511 Submerged JB inside 6549 Peters 11901 C
N/A containment l.
Iy
.),
Estimated Date of Completion SCR No.'
Description ECN Engineer Workplan No. U-1 U-2 Connents EQP 8512R2 Rewire JB N/A Mburn 11855, 11856 C C
All boxes rewired.
EQP 8513 Weep holes (noisture) 6547 Alas 11898 C
C Conplete QIR submitted.
EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C
'C Complete QIR submitted.
EQP 8514 Motor insulation 74-1, -2 6540 Branham 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 Instrtsnent N/A N/A C
Maint.
EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C
E EQP 8518 Submerged cables 6533 Various/6 various C
C i
EQP 8519 Tee drains N/A Electrical N/A C
C Conplete QIR submitted.
Maint.
i EQP 8520 Expired cables 6553 Gonzalez 11902 C
C EQP 8521 Delete TB and rework splices 6550 Stockton 11914, 11915 C C
s EQP 8521R1 Delete TB and rework spilces 6551 I
l EQP 8522 Rewire local panels N/A Stockton 11914, 11915,C C
1 i
EQP 8522R2 Rewire local panels N/A Instrument 12016 C
C
{
Maint.
i l
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'l
. tit.
Estimated Date of Coneletion SCR No.
Description ECW Endneer Workplan No.
U--I U-2 Connents EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C
and misplaced brackets EQP 8524 Change setpoints 6551 Instrurnent 11916 C
C Maint.
EQP 8525 Rotenninate hydrogen N/A Electrical N/A C
C Conpleted by Electrical Maint.
reconbiner (M)
Maint.
EQP 8526 Replace FSVs, U-1 1 U-2 11 6552 Mechanical 11897 C
C Mods.
EQP 8527 Coat TB, U-l 3, U-2 8 N/A Stockton 11914, 11915 C C
(MR)
!E ly EQP 8528 Solder strain gauge Barton IMI Instrument N/A C
C QIR submitted 1/24.
transmitters Maint.
EQP 85?9 PDT-30-42, -43 6554 Legg 11912 C
C EQP 8530 Gasket, Namco L/S N/A Electrical N/A C
C (m)
Maint.
EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C
3 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
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d Estimated Date of Concletion SCR No.
Description ECW Engineer Workplan No. U-1 U-2 Coments 1
EQP 8534 Resplice valve positioner N/A Maxwell MR C
C Couplete QIR submitted.
3-174 and -175 3
l EQP 8535 Replace limit switches, 6556 Stockton 11927, U-2 C
C j
U-1 10, U-2 12 11928, U-1 i
EQP 8536 Valve roan submergence 6561 Mechanical 11939 C
C Cap drains 6632 Mods.
C C
EQP 8536R1 Valve room submergence 6612 Electrical C
C Mods.
4 EQP 8537 Rebuild or replace JB 3078 6579 Anburn N/A C
i 4
EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C
?
FCO-31-475, -476 a
EQP 8539 Replace capacitors N/A Instrument C
C
- Maint, EQP 8540 Replace pigtails to Target 6649 Peters C
C l
Rock solenoid valves EQP 8541 Delete brakes 6582 Branham 11980 sC N/A EQP 8542 Replace unqualified cables 6680 Hall 3/30 N/A Two cables will be replaced in accordance with a new issue.
EQP 8543 Replace JB wire N/A Anturn 11855, 11856 C C
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Estimated Date of Concletion SCR No.
Description ECW Engineer Workplan No. U-1 U-2 Consnents l
EQP 8601 Replace 1, 2-PT-1-2A, -27A; 6588 Elkins 12014 C
C l
upgrade 2-PT-1-28, -278 i,
EQP 8602 Reroute control cables for A"a a """a n a a"a "a a a a a a a a a a " a a a a a a """ a No longer an issue.
1, 2-FCV-70-87, -89 j
EQP 8603 Replace portion of PP711B 6627 Kimsey N/A C
EQP 8604 Cable 1PL3241A not goalified
" " " " "aaaa" "a"aaa"a" " "a"au naaaaa No longer an issue.
EQP 8605 1, 2-TS-74-43, -44, -45, 6589 Branham C
C
-46 not qualified EQP 86%
Undervoltage concern on 6611 Rutledge 3/30 C
In work.
feedwater isolation valve 6676 i
brakes
's EQP 8607 Delete TB for 1, 2-PT-1-2A, 6626 Instrument 12014 C
C
-27A Maint.
EQP 8608 Enable / disable MOV brakes 6621 Rutit @
C C
6622 6665 6666 EQP 8609 Replace cable IV79738 6618 C
N/A EQP 8611 JB has weephole in top N/A
/hburn N/A C
EQP 8612 Replace zone switches 6669 N/A C
8,,
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4 Estimated Date of Coneletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Comnents 4
EQP 8614 Weep holes in JB 6652 C
C EQP 8615 Replace FT-72-13, -34
+
EQP 8617 Junction box internal wiring Ant > urn C
C 1
i EQP 8618 Relocate arc suppression 6795 C
C network EQP 8619 Valve room submerged cables 6808 6/30 3/1 l
EQP 8620 Relocate steam generator Instrument Will roll transmitters 1800, i
level transmitters Maint.
I e
EQP 8621 Resolve conduits and fittings 6808 3/30 3/30 Holding for corrective action that may be submerged in determination.
Auxiliary Building EQP 8622 Replace terminal blocks with 6779 3/30 3/1 Workplan is in writing.
spliced cables t
l EQP 8623 Replace limit switch on
- AA m m AAAAAA"aaaa"a m AAAAAAA"AA No longer an issue.
FCV-3, -21 l
l
\\
EQP 8624 Junction box 2145 may be
- " " m aAA"Aaaa"AAA"A"A"AA"Aa m AAaaaa No longer an issue.
submerged, unit 1 EQP 8625 6.9-kV nondivisional cables Holding for drawings, in trained trays 1
s i.i k
jlf f q
e Estimated Date of Concletion SCR No.
Description FCN Engineer Workplan No. U-1 U-2 Conenents 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, i
and -1658 l
N/A Replace 1-FT-1-3A, -3B, -10A, 6347 Instrument N/A C
N/A
-108, -21A, -218, -29A, -28B Maint.
NEB 8510 Relocate LT-68-320, 6439 Carrasquillo Various C
C PT-68-323, -320 Peters Remount 63-71,68-308 64 %
Legg 11865 C
C l
J Replace LS-65-4, -5 6504 Legg 11865 N/A C
MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C
Delete brakes FCV-62-61 6521 Branham 11905 C
C 1
EEB 8517 Replace pressure transmitter 6488 Branham 11931 C
C PDT-65-80, -82, -90, and -97
]
N/A Raycheni splice rework Peters Various nas 6/30 3/15 I.
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-e THIS PAGE INTENTIONALLY LEFT BLANK h
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u
i TENNESSEE VALLETAUiHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 February 13, 1987 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPEnATING REPORT - JANUARY 1987 Enclosed is the January 1987 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY U
L. 17.
o les h Acting Plant Manager Enclosure cc (Enclosure):
Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, Georgia 30323 (1 copy)
Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20355 (10 copies)
Mr. T. Marston 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 v
j O&PS-2, Sequoyah Nuclear Plant 11 An Equal Opportunity Employer