ML20137V595
| ML20137V595 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1985 |
| From: | Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8602190628 | |
| Download: ML20137V595 (45) | |
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' TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION November 1, 1985 - November 30, 1985 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 I
LICENSE NUMBER DPR-79 i
Submitted by:
P. R. Wallace, Plant Manager l
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1 TABLE OF CONTENTS I.
Operational Summary Page 4-Performance Summary 1
Significant Operational Events-1-2 Fuel Performance and Spent Fuel Storage Capabilities 2
PORVs and Safety Valves Summary 3
Licensee Events and Special Reports 3
Offsite Dose Calculation Manual Changes 4
II. Operating Statistics A.
NRC Reports Operating Data Reports 5-6 Unit Shutdowns and Power Reductons 7-8 Average Daily Unit Power Level 9-10 B.
TVA Reports Nuclear Plant Operating Statistics (November 1985) 11 Unit Outage and Availability 12-13 Reactor Histograms 14 III. Maintenance Summary Electrical Maintenance 15-21 Instrument Maintenance 22-24 Mechanical Maintenance 25-32 i
Modifications 33-36 IV.
Outage Schedule 37-42
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Optritien3 Summary November 1985 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.
Unit 1 The unit remained in the cycle three refueling / modification outage the entire month. The present schedule has the unit prepared to return to service on January 26, 1986. Actual start-up is dependent upon NRC review of the Sequoyah Startup Readiness Plan. The unit has been off-line for 100 days.
Unit 2 The unit remained in the administrative shutdown the entire month due to documentation concerns relating to the environmental qualification of various electrical equipment (NUREG 0588). Outage related maintenance and modifications are being performed. The present schedule has the unit prepared to return to service on January 22, 1986.
Actual start-up is dependent upon NRC review of the Sequoyah Startup Readiness Plan. The unit has been off-line 101 days.
Significant Operational Events Unit 1 Date Time Event 11/1/85 0001C The reactor was in mode #6. Cycle 3 refueling /
modification outage continued.
11/4/85 1030C Core on-load began 11/12/85 1605C Core on-load completed.
11/13/85 1713C The reactor head was set in place.
11/18/85 0537C The reactor entered mode #5.
11/20/85 1537C The reactor re-entered mode #6. While reviewing the instruction package for tensioning the reactor head, it was determined that six bolts did not meet the acceptance criteria.
11/22/85 1540C Entered mode #5.
The bolts were tensioned and *he acceptance criteria verified.
11/30/85 2400C The reactor was in mode 5.
Cycle 3 refueling /
modification outage continues.
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Significant Operatienni Evrnts (cont.)
Unit 2 Date Time Event 11/1/85 0001C The reactor was in mode #5. Administrative shutdown continued due to NUREG 0588 concerns.
11/30/85 2400C The reactor was'in mode #5.
Administrative shutdown continues due to NUREG 0588 concerns.
F Fuel Performance Unit 1 The core average fuel exposure accumulated during November was 0.00 MWD /MTU.
The cycle 3 core reload of 193 fuel assemblies ccmmene,ed on November 4, 1985, at 1033 CST. The core reload was completed on November 12, 1985, at 1605 CST.
Fuel handling operations on reloading the core were delayed due to a number
'of mechanical breakdowns. These included the manipulator crane breakdown, 4
the fuel transfer system's counter malfunction, and residual heater i
removal system (RHR) pump motor inoperability. These mechanical problems caused an estimated 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> of downtime.
Upon completion of fuel handling operations, verification of fuel orientation by serial number (TI-45:
Physical Verification of Core Load prior to Vessel Closure), was performed on November 12, 1985, commencing at 1900 CST. This was ' conducted by two separate parties from plant Field Quality Engineering j
(FQE) with support assistance from plant Reactor Engineering Unit personnel who were not directly involved in the fuel movement. As the videotape recording was made, a core position map was prepared in accordance with TI-1.
After' the completion of core verification, plant FQE personnel verified 4
this core position map against the Westinghouse Sequoyah Unit Core Loading Plan Cycle 4 (Drawing 1763E26). No discrepancies were observed.
A spent fuel pit inventory was conducted on November 15, 1985, commencing 0800 CST. This was conducted by Reactor Engineering Unit personnel.
As the videotape recording was made, a spent fuel pit position map was prepared only on the affected discharged 72 bundles. No discrepancies were observed.
Unit 2 The core average fuel exposure accumulated during November was 0.00 MWD /MTU with the total accumulated core average exposure of 8097.51 MVD/MTU.
Spent Fuel Pit Storage Capabilities i
The total storage capability in the spent fuel pit (SFP) is 1,386. However, l
there are 'five cell locations which are not capable of storing spent fuel.
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Four locations (A10, All, A24, A25) are unavailable due to a suction strainer conflict and one location (A16) is unavailable due to an instru-
. mentation conflict. Presently, there is a total of 348 spent fuel bundles l
stored in the SFP. Thus, the remaining storage capacity is 1,033.
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. i PORVs and Safety Valves Summary No PORVs or safety valves were challenged in November 1985.
Licensee Events and Special Reports The following licensee event report (LER) was reported to the Nuclear Regulatory Commission in November 1985.
LER DESCRIPTION OF EVENT 1-85039 At 1300C, October 10, 1985 a containment ventilation isolation (CVI) occurred when an instrument mechanic went to the wrong radiation monitor to run a test.
1-85040 On October 9, 1985, at 1807C, during residial heat removal (RHR) pump swapover, indications showed that possible cavitation occurred resulting in a loss of both RHR trains. This problem was due to the low level of the reactor coolant system (RCS) in which the RHR pumps take their suction from loop #4.
1-85041 While aligning IB-B diesel generator (D/G) for standby operation, an inadvertent start (ESF actuation) occurred at 1010C, October 9, 1985, when the fuse cover was lifted for a fuse inspection.
1-85042 A containment ventilation isolation (CVI) occurred from a false high-level radiation indication on "B" train purge air exhaust radiation monitor (1-RM-90-131) at 0715C, October 20, 1985.
The impeller pump vanes were dislodged causing the monitor's recirculation pump motor to fail electrically.
1-85043 On October 23 and 24, the IA-A and IB-B centrifugal charging l
pumps were tested and "as found" failed to meet the acceptance criteria of technical specification 4.5.2.h.2.a.
Surveillance Instruction (SI)-260.2; " Bit Cold Leg Injection Flow Balance, Pump Performance and Check Valve Test", requires the sum of the injection line flow rates, excluding the highest line flow must be greater than or equal to 346 gpm.
The IA-A and IB-B pumps tested at 338 and 328 gpm respectively.
The most probable cause is attributed to observed degradation of the pumps wh'ich has been documented as an industry-wide problem and is describe in Westinghouse Technical Bulletin No. NSD-TB-80-11.
This test is performed every refueling outage.
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Licenste Events and Sp: ciel Repsrts DER DESCRIPTION OF EVENT (cont.)
1-85044 The IA-A and IB-B safety injection pumps were tested on October 28 and November 8,1985, and "as found" failed to meet the acceptance criteria of Technical Specification 4.5.2.h.1.b. Surveillance Instruction (SI)-260.3, " SIS Cold Leg Injection Flow Balance, Pump Performance and Check Valve Test" requires a total flow of less than or equal to 660 gpm. The IA-A and IB-B pumps were tested at 671 gpm and 664 gpm respectively.
Both pumps were retested using calibrated Rosemounts.
"As found" flow for IA-A was 665 gpm and "as found" flow for IB-B was 664 gpm.
A review of the previous performance reveals that both pumps had been left with a total flow rates in excess of 660 gpm.
The apparent reason for this deficiency was confusion of test personnel over which instrumentation could be used for determining technical specification compliance. This test is performed every refueling outage.
1-85045 At 0950C, October 31, 1985, an event occurred that resulted in a diesel generator (D/G) start and A & B train auxiliary building isolation (ABI). A defective racking mechanism on the alternate feeder breaker for the IB start bus caused a loss of that bus when a normal transfer was attempted. This resulted in an undervoltage on the IA-A shutdown board which started the D/Gs. The "B" train Auxiliary building isolation occurred on the loss of power because the "B" train spent fuel pool radiation monitor had been previously, inadvertently connected to a nondivisional power source.
The IB start bus alternate feeder breaker racking mechanism was found to haw a bent racking lever which prevented the breaker from being fully racked in.
2-85011 A high radiation alarm was actuated at 0136C, October 10, 1985, which caused a containment ventilzation isolation (CVI) to occur. A voltage spike occurred as a result of electro-magnetic interference (EMI) which was spuriously generated by the low flow alarm switch in one incident. The source is unknown in the two other incidents.
Special Reports The following special report was transmitted to NRC in November 1985.
85-08 The steam generator tube inservice inspection was completed on unit 2 November 4, 1984. The results of this inspection were submitted to NRC by November 4, 1985.
O_ffsite 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 l '
DOCKET NO. 50-327 DATE' DECEMBER 9,1985 COMPLETED BY D.C.DUPREE TELEPHONE (615)S70-6544 OPERATING STATUS 1.
UNIT NAME:.SEQUOYAH NUCLEAR PLANT, UNIT 1
NOTES:
2.' REPORT PERIOD: NOVEMBER 19G5 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, G I VE REASONS: -_---------_
- =-----------------------------------------
- 9. PGWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):--__----
a10. REASONS FOR RESTRICTIONS,IF ANY:____-__-
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THIS MONTH YR.-TO-DATE CUMULATIVE fil. HOURS-IN REPORTING PERIOD 720.00 3016.00 38737.00 jl2. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 3797.25 24444.91
!!3. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 j l.. HOURS GENERATOR ON-LINE O.00 3762.13 23871.13 4
.;15. UNIT RESERVE-SHUTDOWN HOURS 0.00 O.00 O.00 1
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,18.
NET ELECTRICAL ENERGY GENERATED (MWH)
-2333.00 4061303.00 24942933.00
- 19. UNIT SERVICE FACTOR O.00 46.93 61.62 l20. UNIT AVAILABILITY FACTOR O.00 46.93 61.62
!21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 44.13 56.09 i22. UNIT CAPACITY FACTOR (USING DER NET)
O.00 44.13 56.09 123. IINIT FORCED OUTAGE RATE O.00 12.33 17.45 l24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
'25. ~ JF SHUTDOWN AT END UF REPORT PERIOD, ESTIMATED DATE OF S UP:
Jinuary 19& P.MdjDg_N_RC_ retviey_of__Sequoyah, Nuclear Plant _St_artup {ARJiness Plan.
ea NOTE THAf THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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OPERATING DATA REPORT,
\\s DOCKET NO. 50-328
'DATE DECEMBER 9,1985 COMPLETED BY D.C.DUPREE s
TELEPHONE (615)S70-6544 OPERATING STATUS,
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UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2
NOTES:
- 2. REPORT PERIOD: NOVEMBER 1985 3.
LICENSED l THERMAL _ POWER (MWT):
3411.0\\n 4.
NAMEPLATE RATING'(GROSS'MWE):
1220.A 5.
DESIGN ELECTRICAL RATING (NET MWE):
V1148.0 i
6.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
1103 9 7.
MAXIMUM DEPENDADLE CAPACITY (NET MWE):
1148.0
,O.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:____________
___________________________________________________h____
9.
POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):________
- 10. REASONS FOR RESTRICIIONS.IF ANY:._________.________[._
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THIS MONTH NN.-TO-DALE CUMULATIVE 1
- 11. IlOURS IN REPORTING PERIOD 720.00 8016.00 30697.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00
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5289.42 21984.54
- 13. REACTOR RESERVE SHUTDOWN HOURS O.00 O.00 0.00
- 14. HOURS GENERATOR ON-LINE O.00 5224.24 21494.42
- 15. IINIT. RESERVE SHUTDOWN HOURS O.00 0.00 0.00
- 16. GRO9S THERMAL ENERGY GENERATED (MWH) 0.00 17128966.35 69127977.22
.1 7.- GROSS ELECTRICAL ENERGY GEN. (MWH)
O.00 5845100.00 23536780.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-3544.00 5615045.00 22636053.60
- 19. UNIT SERVICE FACTOR O.00 65.17 70.02
- 20. UNIT AVAILABILITY FACTOR O.00
,65.17 70.02
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 61.02 64.23
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 61.02 64.23
- 23. UNIT FORCED OUT AGE RATE 100.00 34./8 16./1
'2 4. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DAIE, AND DURATION OF EACH):
- 25. IF SHUTDOWN AT END OF REPORT PERIOLi, ESTIMATED DATF OF STARTUP:
_d{nuary_1_9,h _pendin6 NRC_revig _of_Seguoyal 8
L ucle,ar__ Plant __ Star,tu g ead_iness Plan.
N NnTE THAT THE THE Y R. --T O-II AT E AND CitMULATIVE VALUES HAVE BEEN UPDATED.
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UNIT SlIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-327 UNIT NAhE c,,... _.. a.
n_. _
DATE 12/4/85 COMPLETED BY n
- c. nunro, REPORT ?!0NTl!
MOVDtBr.R 1985 TELEPHONE (615) 870-6544
.c w
o c
Cause & Corrective gg oyg Licensee go, g*n, N
g Action to Ma.
Date g
gg 73m Event ug gg o
gu Prevent Recurrence g-g gus Report //
>, o oo u
- v c:
o.cf m u, o
n 6
350822 S
720 C
4 Refueling outare continues 4 Exhibit G-Instructions 3tlethod:
2 Reason:
IF:
Forced S: Scheduled A-Equipment Failure (Explain) 1-ttanual for Preparation of Data B-!!aintenance or Test 2-flanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restrict. ion 4-Cont. of Existing (NUREG-0161)
E-Operator Trainin3; & License Examination Outage F-Administrative S-Reduction SExhibit I-Same Source' G-Operational Error (Explain) 9-Other ll-Other (Explain) 7 i
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UNIT Sl!UTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-328 UNIT NAME seauovah Two DATE 12/n/As COMPLETED BY p. c. nunree REPORT !!0NTli NOVEMBER 1985 TELEPHONE (61si R7n_6saa m
E w
o Cause & Corrective gg Q
y aj Licensee g -3, g*n i
o Action to No.
Date g
,j g g
gjg Event gg gg Prevent Recurrence g
2g g
jgM Report Il gU gu 5"
?N5 S
j 9
850821 F
720 D
4 NUREC 0588 Documentation concerns I
4 Exhibit G-Instructions 3Hethod:
2 IF:
Forced Reason:
S:
Scheduled A-Eijuipr!cnt Failure (Explain) 1-!!anual for Preparation of Data B-!!aintenance or Test 2-!!anual Scram.
Entry Sheets for Licensee 3-Automatic Scram.
Event Report (LER) File C-Refueling 4-Cont. of Existing (NtfREG-0161)
D-Regulatory Restriction E-Operator Traininn & License Examination Outage F-Ailmini s t ra tive 5-Reduction S
G-Operational Error (Explain) 9-Other Exhibit I-Same Source' ll-Other (Explain) 8
SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : ONE DATE : DECEMBER 9, 1985 COMPLETED BY :
D. C. DUPREE.
TELEPHONE :(5153870-6549 MONTH NOVEMBER 1985 l
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l
DAY (MWe Net)
DAY (MWe Net) 01 0
17 0
02 0
18 0
03 0
19 0
04 0
20 0
05 0
21 O
06 0
22 O
07 0
23 0
08 0
24 0
09 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
20 0
15 0
31 15 0
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SEQUOY.;H NUCLEAR PLANT f.UERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : DECEMBER 9, 1985 COMPLETED BY :
D. C. DUPREE TELEPHONE :(6153870-6544 MONTH NOVEMBER 1985 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)
DAY (MWe Net) 01 0
17 O
O2 0
18-0 03 0
19 0
04 0
20 0
05 0
21 O
06 0
22 O
07 0
23 0
08 0
24 0
09 0
25 0
10 0
26 0
11 0
27 0
12-0 28 0
13 0
29 0
14 0
30 0
15 0
31 16 O
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_ ',rvh iss2a toree.au NUCLEAR PLANT OPERATING STATISTICS SEQUOYAll NUCLEAR Plant 85 NOVEMBER 39 Period Hours 720 Month Item No.
Unit No.
UNIT ONE UNIT WO 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
8 5
Gross Electrical Gen., MWh 0
0 0
5 6
station use. MWh 2,333 3,544 5,877 h
7 Net Electrical Gen., MWh
-2,333
- 3,544
-5,877 h
S Station Use, Percent N/A N/A N/A 9
Accum. Core Avg. Exposure, MWD / Ton!
0 8,098 8,098 10 CTEG This Month,106 BTU 0
0 0
11 SGTEG This Month,106 BTU 0
0 0
12 13 Hours Reactor Was Criticai 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 I t, Turbine Avail. Factor, Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 0
18 Turbogen. Avail. Factor, Percent 0.0 0.0 0.0 IE+
Reactor Avail. Factor. Percent 0.0 0.0 0.0 2
20 Unit Avait. Factor. Parcent O.0 0.0 0.0 21 Turbine Startuos 0
0 0
22 Reactor Cold Startuns 0
0 0
23 g
24 Gross Heat Rate. Btu /kWh N/A N/A N/A j
25 Net Heat Rate, Btu /kWh N/A N/A
'j / A 26 U
27 y
28 Throttle Pressure, psig N/A N /A N/A ct 29 Throttle Temperature. 'F N/A N /e\\
N/A j
30 Ex haust Pressure, inHg Abs.
N/A N/A N/A g
31 Intake Water Temo.. 'F N/A N/A
_ N/A b-32
- /A N /.g N/A 33 Main Feedwater. M lb/hr N/A N/A N / <\\
34
[
35 36 37 Full Power Capacity, EFPD 404.86
- 363.65 763.31 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 p
39 Oil Fired for Generation, Gallons 1782 2
40 Oil Heatina Value. Btu / Gal.
I18,000 41 Diesel Generation. MWh 27 4?
Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor, %
3 43 N/A 5/A N/A N/A N/A N/A Remarks If or BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
l 2(t) indicates Thermal Energy.
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- Approxinately
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DJte subrmtted Date Rened
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Plant Superintendent
( TVA 6S60C (PP 3-761
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t UNIT OUT AGE AND AVAILABILITY SEQUOYAH Nuclear Pla.it Lkennd Reactor Power 3'II MW(th)
Unit No.
ONE 1220.5 Gerwator Ratmg MW(e)
Month / Year WVNM UD IIO3 Design Gross Electrical Ratmg MW Perend Hma,s 720 Unit
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METHOD OF UNIi Tenw unit A.aiiante Tong Not A.a.lable COHHLCIIVL ACIION Totar Gen.
Not used furthne Gen.
Reac tor Unit Ou in N
DURI G O
Dev ms ' u.a ms ' uin ms i u.a me i u.n as l u.n as ' u.n ee.s lu.n ~j u.n e,s '_ uen REACTOR OUTAGL ms 1
C3 i OO 00 ;00 24 l 00 24 00 24 iOO 24 400 herueling outage contsnues ri/ A ggg, g 2
00 ! OO 00 iOO 24:00 24 ;00 24 iOO 24 50 0 e
i 3
00 ' 00 00 *00 6
24 i 00 24 iOO 24 300 24,00 24e00 24 *00 24 300 4
00 i 00 00joO 24800 24 l 00_. 24j 00 iOO e
e 24_Too 00 80Q_.jQaQQ_
24 e
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6 00 800 00 800 e
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3 9
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11 00000 00 '00 l
24800 24,00 24 500 24 100 i
12 00 8 00 00 l00 t
24j o0_. 24 ! OO E00 24 600 a 2]4 13 00 !00 00 iOQ_
24?00 24 ' 00 24 iOO 2
00
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24800 24 600 24 l00 24 100 i
i 16 00 : 00 00 '00 a
24 : 00 24 i OO 24 !OO 24 100 e
a 17 00000 00 ;00 24 ; 00 24 !00 24100 24 300 t-i 18 00!00 00 i0g_
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19 00 00 00 600 e
24 i 00 24 100 24 iOO 24 LOO ~ 7~7~
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_20_. 00 i 00 AQMQ_
24! 00 24!00 24 !00 24 e00 21 00i00 00 n00 24i00 24i00 24 [00 24 000 un the reictor head (1172T/85) ~
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26 00i00 00 800 4
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SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -
90 -
H 80 -
5 0
70 -
5 60 -
5y 50 -
k 40 -
O O
30 -
6 m
20 -
10 -
O
-10 O
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12 16 20 24 28 32 NOVEMBER 1985 SEQUOYAH TWO REACTOR HISTOGRAM 100 90 -
80 -
70 -
5 5
60 -
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l NOVEMBER 1985 l
14
12:28:43 12-04-85 ELECTRICAL MAINTENANCE 19mR.Y REPORT FOR IWWEFBER PAE 1 DATE....
(I)WDENT.....
FAILURE DESCRIPTION......
CAUSE OF FAILlRE.........
CORRECTIVE ACTION,.......
19.90..
01-25-85 1-MTRB-30-455A MOTOR TERNALS OUT AFTER MOTOR WAS PtLLING REPLACED PET (R H A521886
-A RESET Als START EXCESSIVE CLRRENT CECNED F(R PRWER OPERATI(M 09-10-85 2-INVB-250-GU-
- 1 FAN MOTOR WOILD HOT FAN MOTOR BLRED UP DUE REPLACED #1 VITAL A542188 G
RUN TO NORMAL EAR IMUERTER FAN MOTGt 09-19-85 1-BKRB-201-DM BREAKER CLOSING SPRING 1-LS-201-DM/58-9 SPRING CLEAED M ADJJSTED A333783
/58-B DID NOT RECHARGE WEN RECHARGE LIMIT SWITCH WAS LIMIT SWITCH TEM CECNED BREAKER WAS CLOSED DIRTY AND OUT OF FOR PROPER WERATION OF ECHANICAL ADJUSTENT BREAKER PREVENTING LIMITS FROM MAKING UP 09-20-85 2-INVB-250-GU-FAN FAILURE ALARM FAN POSSIBLY HAD REPLACED 2-IV VITAL M'4A'**2 G
FLASHING DEFECTIVE FLOW SWITCH INUERTER FAN M CEENED FOR PROPER WERATION 09-24-85 1-RLY-202-PMB REPLACE TIMER WHICH CAN TIER DEFECTIVE REPLACED TIrER ADO RESET A5445/7
-GT NOT BE ADJJSTED TIE PER SI-220.1 09-24-85 1-RLY-201-XD20 REPLACE CRYDON RELAY FOR POSSIBLY RELAY COIL HAD REPLACED CRYD(M RELAY A005180 87 1-PN-62-C-1 OPENED DUE TO NORMAL EAR 10-11-05 2-FCV-001-0150 VALVE FAILED SI-166.6.
LN(NOWN ADJUSTED LIMIT STRINERS A536872 TE LOCAL M REMOTE ON VALVE SHAFT TO ALLOW STRIKE TIES WERE GREATER TE LIGHT ACTUATION TO THAN 1 SEC. APART.
OCCUR WITH VALVE CL(Bits 10-13-85 2-INVB-250-GP-VITAL INVERTER 2-II FAN VITAL INVERTER RELAY CLEAED Ate REPAIRED A536101 E
FAILtRE ALARM WOULD NOT CONTACTS ERE DIRTY RELAY CONTACTS Ate RESET AT INYERTER PREVENTING CONTACTS FROM CECKED ALL FAN FLOW MAKING UP SWITCES FOR PROPER OPERATIDH 10-13-05 2-AHU-061-0024 FAN urn n NOT RlN WITH HA60 SWITCH WIRES ERE CHANGED WIRES (M A334240 15 4
i 12:28:43 12-04-85 ELECTRICAL MAINTENANCE FDITILY REPORT FOR NDYEfBER PAGE 2 DATE....
(IINOENT.....
FAILURE DESCRIPTION......
CAUSE OF FAILtRE.........
CORRECTIVE ACTION........
IR.te..
B 2-HS-061-0434 IN NORf%L CDPMECTED TO NORMALLY MAPDSWITCH FR(M DERft4LLY POSITION BUT RUNS WEN IN CLOSED CONTACT CLOSED CONTACT TO ON POSTION HORMALLY OPEN CONTACT 10-13-85 2-AHU-061-0026 FAN WOULD HOT RlN WITH HA>DSWITCH WIRES ERE CHANGED WIRES ON A534241 B
2-HS-61-454B IN HORMAL CONNECTED TO NORMALLY HA>DSWITCH FROM NORMALLY POSITIDH BUT RLMS IN ON CLOSED CONTACT CLOSED CONTACT TO POSITION NORMALLY (PEN CONTACT 4
10-18-85 1-ZS-030-0020 LIMIT SWITCH IPDICATES LAN HOLDER BURNED OUT OR REPLACED IPDICATIDD LAN A536411 CONSTANT OPEN POSITION DEFECTIVE HOLDER IN MDt 10-18-85 2-FSV-062-0085 VALVE INDICATCR LIGHTS SOLEHOID VALVE WAS REPLACED 2-FBV-62-95 A527141
-B SHOW BOTH OPEN A>D CLOSED DEFECTIVE CAUSING SOLEHOID VALVE ADD BRONEN 4
POSTION WHILE VALVE IN EXCESSIVE AIR TO ESCAPE NIPPLE MD CECKED FDR OPEN POSITION T}5t00GH BY-PASS PORT PROPER VALUE IDDICATION l,
10-18-85 2-RLY-072-2A29 REPLACE DEFECTIVE CRYDON POSSIBLY RELAY COIL HAD REPLACED RELAY A116737 i
4 RELAY 2A2-94 FOR TSC OPENED DE TO NORMAL EAR i
POINT 2-PN A-A 10-18-85 2-RLY-072-2829 REPLACE DEFECTIVE CRYDON POSSIBLY RELAY COIL HAD REPLACED RELAY A116738 i
4 RELAY 2B2-94 FOR TSC OPENED DUE TO NORMAL WEAR POINT 2-PN B-B i
10-18-85 2-RLY-074-2829 ' REPLACE DEFECTIVE RELAY POSSIBLY RELAY COIL HAD REPLACED RELAY A116739 i
6 2B2-96 FOR TSC POINT OPENED DE TO NORMAL WEAR 2-Pff-74-B-B 10-18-85 2-RLY-63-2A298 REPLACE DEFECTIVE CRYDON POSSIBLY RELAY COIL HAD REPLACED RELAY A116740 RELAY 2A2-98 FOR TSC OPENED DE TO NORMAL EAR l
POINT 2-PN-63-A-A i
10-20-85 1-BKRC-082-TT/
REPLACE 125U DC BREAKERS LH040WN REPLACED 4 20 Alf A546199 2-A IN DISTRIBUTION PAEL FOR BREAKERS IN TE 125V DC l
D/G ENGIE CONTROL PAEL, DISTRIBUTI(M PAEL #D l
16
12.28:43 12-04-85 ELECTRICAL MAINTENANCE NONIHLY REPORT FOR NOVEMBER PAGE 3 DATE....
CDMPONENT.....
FAILURE DESCRIPTION......
CAUSE OF FAILURE.........
CORRECTIVE ACTION........
FR. HO..
GEN PROTECTIVE RELAYS, DC CLEANED OIL OLIT OF PAEL LLEE DIL PUMPS, EXCITATION PANEL, AND BATTERY CHARGER 10-22-85 1-CRN-079-JN REPLACE THE LS-6 LIMIT SUITCH HAD STRUCK REPLACED LIMIT SWITCH A551209
/9El ACTUATING ARM AND CHECK HN40 RAIL BOLTS ACTUATOR EAD IHE SWITCH AND REPLACE IF DAMAGED 10-23-85 1-CR N -0/9-JN LS-16 IS NOT WORKING DEFECTIVE LEVEL SWITCH REPLACED LEW L SWITCH 16 A545515
/9El PROPERLY WITH LEVEL SWITCH FR0r1 UNIT 2 MANIPULATOR CRANE 10-24-85 1-B AT B-002-LfB-CORRECT EXCESSIVE BOLT. NUT AND WASERS HAD REPLACED BOLT, HUT #4D A518211 A
CONNECTIDH RESISTANCES ON DETERIOR ATED DUE TO UASHER. CLEAED 1A-A DIESEL GENERATOR EXCESSIVE ACID CONNECTIONS APO COATED BATTERY WITH NO-0X 10-25-85 2-CEN8-082-OOO REPLACE TE ELECTRICAL DEFECTIVE ELECTRICAL REPLACED ELECTRICAL A539669 2A-A UIRING HARNESS ASSEMBLY WIRING HARNESS ASSETELY WIRING HARESS BETWEEN THE ENGINE CONTROL CABINETS AND THE HYDRAULIC GOVERNORS 10-28-85 2-LOCL-013-Z37 ZONE 3748 TROUBLE ALARN BAD FIRE DETECTOR HEAD REPLACED FIRE DETECTOR AS46142 E
IN Aeo WILL NOT CLEAR EAD AND RAN SI-234.7 A>0 CHECKED FOR PROPER OPERATIDH 10-28-85 1-8 KR C-202-kE BREAKER WOULD NOT CLOSE 1-BKRC-202-KE/201-A RELAY CLEAED RELAY CONTACTS AS46227
/201-A 30RX CONTACTS WERE DIRTY AND CHECKED FOR PROPER PREVENTING LIMITS FR0n OPERATIDH MAKING UP 10-30-85 FFCV-001-0032 BOTH RED AND GREEN LIMIT SUITCH TRIP BAR UAS A0 JUSTED LIMIT SUITCH A549039 l7
12:28:43 12-04-85 ELECTRICAL MAINTENANCE 11CN1HLY REPORT FOR NOVElWER PAGE 4 DATE....
CDnP O NENT.....
FAILURE DESCRIPTION......
CAUSE OF FAILURE.........
CORRECTIVE ACTION........
fWt.NO..
ACTUATOR lit iT5 WERE ON DUT OF ADJUSTMENT TRIP BAR UHILE VALVE IN CLOSED POSITION 10-30-85 1-FCV-061-0193 VALVE WOULD HOT OPEN ELECTRICAL COIL UAS REPLACED COIL AS43868 UHILE HANDSUITCH IS HELD DEFECTIVE DLE TO NORMAL IN OPEN POSITION UEAR 10-30-85 1-BDB -201-OK-A REPLACE 480V / 120V BAD POTENTIAL TRANSFCRnER REPLACED TRANSFORER A>0 A119571 POTENTIAL TRANSFORMER OH VERIFIED VOLTAGE ETER 480V SHUTDOUN BOARD 1A2A READING CORRECTLY 10-31-85 0-nTR B-311-003 BATTERY R00n EXHAUST FAN FAN MOTOR B HAD BAD MOTOR REPLACED T10 TOR BEARINGS A533952 4
MOTOR BEARINGS WERE BAD BEARINGS DUE TO NORf1AL AND RETERf1IHATED F10T09 WEAR 11-02-85
} nTR B-030-007 FLEX FEEDING FAN MOTOR IS PERSONNEL CLIr1BING ON REPAIRED FLEX AND JOINTS A126916 7-A BROKEN AT BOTH ENDS FLEX CAUSING IT TO BREAK EXPOSING CONDUCTORS AT BOTH ENDS 11-03-85 I-PMD-067-0436 ERCU PUNP K-A WOULD NOT DIRTY PELAY CONTACTS CLEANED CONTACTS OH 1L A536032 START FROM CONTROL ROOn CAUSIt1G LATCHING 30X, 3CRX Ato REWORNED HANDSUITCH MECHANISn NOT TO WORK LATCH ON 30RX PROPERLY 11-03-85 2-FCV-062-0072 VALVE HAS DLOUN FUSES RELAY KSIA HAD A BAD REPLACED REALY KSIA WIIN A560063 RELAY COIL CAUSING FUSES A SPARE RELAY FR0t1 SAME TO BLOW CABINET 2-R-54 11-03-85 2-FSV-062-0074 VALVE WAS BLOUING CONTROL 120V DC COIL UAS BAD IN REPLACED REALY KS1C IN A534072 A
POUcR FUSES WHEN OPENING KSIC RELAY RELAY CABIET 2-R-54 FRON CLOSED POSITION 11-03-85 2-f CV-62-72 VALVE HAS BLOUN FUSES RELAY KSIA fBD A BAD COIL REPLACED RELAY KS1A UITH A560063 TUICE IN ONE SHIFT CAUSING FUSES TO BL0u A SPARE RELAY FR0n IS
12:28:43 12-04-85 ELECTRICAL 11AINTENANCE f10HTHLY REPORT FOR HOVENBER PAGE 5 DA TE....
QV190NENT.....
FAILL7.E DESCRIPTION......
CAUSE Or FAILURE.........
CORRECTIVE ACTION,.......
f1R.NO.
CABINET 2-R-54 11-04-85 1-t1V0 P-0.70-001 VALVE WOULD NOT VALVE TORGUES OUT PRIOR ADJUSTED TORG E SUITCN A534194-
&A ELECTRICALLY CLOSE TO TO REACHING FULL CLOSED FULL CLOSE POSITION POSITIGN 11-05-85 1-FCV-074-0012 SUSPECT BAD GEARS ON FLOU MOTOR WAS BAD REPLACED CAM, TRIPPER A545028 CONTROL VALVE. VALVE TECHANISM Af0 f10 TOR UOULD NOT OPEN 11-06-85
&MTR B-079-HC f10 TOR BACK SPINS AflER PIVOT PIN OUT OF KEYWAY PUSE0 PIVOT PIN BACK A536036
/681 TORGUE SUITCH OPENS INTO POSITICH AND CECKED FOR PR0PER [PERATIDH OF MOTOR-11-07-85 1-BCTA-202-CL/
MECHANICAL TRIP FREE ARM MECHANICAL TRIP FREE ARM REPAIRED TRIP FREE NtM A541276 1416 UOULD NOT CONTINUALLY WAS BENT AND FUNCTIONALLY CECKED LOCK INTO PLACE WHEN BREAKER BREAKER WAS RACKED ONTO THE BUSS,11ARING itE BREAKER INOPERABLE 11-07-85 2-AHU-061-0023 AIR HANDLING UNIT WOULD RELAY WAS DEFECTIVE REPLACED DR REALY AtO AS43803 A
NOT CO INTO DEFROST CYCLE CHECKED FOR PROPER AUTOMATICALLY OR MANUALLY OPERATION 11-00-85 2-PNL S-082-TV-BATTERY DISTRIBUlION METER WAS DEFECTIVE REPLACED AffETER A547975 A
PANEL AMr1ETER WOULD NOT UORK 11-08-85 1-r1V0P-003-006 REBUILD LIMITORGUE OPERATOR HAD MIXED CREASE REBUILT OPERATOR AND RAll A299992 7
OPERATOR AND INTERNAL RUSTING 110 VATS TEST 11-10-85 2-XI-068-03400 VALVE WAS SHOUING OPEN LIMIT SUITCH UAS OUT OF ADJUSTED LIMIT SUITCH A534212 POSITION WHILE THE ADJUSTMENT STOP CONTROLLER WAS IN lHE 19
12:28:43 12-04-85 ELECTRICAL NAINTENANCE rKNTHL( REPORT FOR NOVEMBER PAGE 6 DATE....
CDnP O ENT.....
FAILURE DESCRIPTION......
CAUSE OF FAILURE.........
CORRECTIVE ACTION,.......
MR.NO,.
CLOSED POSITION 11-11-85 1-FCV-026-0240 VALVE WOULD NOT OPEN VALVE YOKE WAS ROTATING TIGHTENED SETSCREWS AND A545012
-A ELECTRICALLY FROM FULL DUC TO SETSCREUS CLEANED INTERLOCK CLOSED POSITION, ALSO VIBRATING LOOSE CONTACTS ON CONTACTOR VALVE BODY HAD EXCESSIVE MOVEnENT UHEN OPENING VALVE WITH HANDuMEEL 11-12-85 FCENB-082-000 ANNUNCIATOR UOULD N01 FIELD CONTACT UAS CLOSED REPAIRED POINT CARD A561105 M-A CLEAR ON 0-n-26 UINDOU 15 CAUSING ANNUNCIATOR TO CLEARING AN>tMCIATOR AS REQUIRED BY SI 102 STAY ON 11-13-85 1-CENB -082-000 REPLACE THE ELECTRICAL UNKNOWN INSTALLED GOVERNOR CABLE A539671 18-B UIRING HARNESS ASSEnBL Y ASSEMBLY OH 18-1 AND 18-2 BETWEEN THE ENGINE DIESEL GEERATOR 4
CONTROL CA8INETS AND GOVERNORS ECA-BPS 11-14-85 1-PNL A-082-TT-1A-A BATTERY DISTRIBUTION Anr1ETER WAS DEFECTIVE REPLACE 0 AMETER A522732 A
PANEL Anr1ETER WOULD NOT ADJUST PER MI-10.2, PM 1357-082 11-15-85 2-CENB-082-000 GOVERNOR ACTUATOR TDC RELAY UAS DEFECTIVE REPLACED TDC RELAY A561101 2A-A DIFFERENTIAL 00ULD NOT WORK AS REGUIRED BY SI-102 11-17-85 1-INVB-250-GL-FLOU SUITCH FAILED TO CONTACTS WERE STICMING ON REPLACED IIRL8 RELAY AFTER A545025 D
OPERATE RELAY NRL8 TROUBLE SHOOTING TFE ENTIRE COOLING CIRCUITS l
AND ALARN CIRCUITS 11-19-85 1-CEN8-082-000 REPLACE ELECTRICAL ulRING UNKNOWN REPLACED WIRING NARESS A539670 1A-A HARNESS ASSEMBLY BETWEEN 20
=
12:28:43 12-04-85 ELECTRICAL 11AINTENANCE FO4TR.Y REPORT FOR N0VErBER PAGE 7
,7 DATE....
Q] lip 0ENT.....
FAILURE DESCRIPTION......
CAUSE OF F.;ILURE.........
CORRECTIVE ACTION........
Mt. M)..
THE ENGINE CONTROL CABINETS AND THE EGB-BP 11-23-85 0-BKR D-202-KC/
6.9 KV BREAKER FOR BAD 110 TOR Ate CONTROL REPLACED PETGt AM)
A594570 202 SERVICE BUILDING t1AlH DEVICE CONTROL DEVICE BOARD BUS B HAD A BN)
CHARCING r10 TOR 48 records listed.
I
.l 1
i 4
4 21 i
INSTRUMENT MAINTENANCE Unit 1 Completed installation of new automatic level controllers for the main feedwater bypass valves. This modification was authorized by ECN-6173 and performed on workplan 11786.
Rescaling and recalibration of the Reactor Vessel Level Indication System (RVLIS) electronics was performed by workplan 11841 and Westinghouse procedure NSID-EIS-85-07. A preliminary post-modification test was performed by the Systems Engineering Section to compare the train B RVLIS upper plenum indication with the actual level (as determined from the tygon tubing used during filling and venting operations). All readings taken on the RVLIS indicator were satis-factory (within 12% of actual level). The official post-modification test will be performed during startup.
During performance of SI-90.2, a main feedwater flow bistable, 1-FS-3-90B, was found inoperable (PRO-1-85-348). The bistable had failed in the energized state. A maintenance request was initiated and the problem traced to a shorted transistor. The failed component was replaced and the bistable recalibrated.
Unit 2 Completed Westinghouse modification RVLIS circuit cards per FCV-TENO-40558A.
This was necessary to eliminate seismic drift problems identified with the associated electronics.
Completed installation of new automatic flow controllers for the n.ain feed-water pump mini-flow recirculation line valves.
This modification was authorized by ECN-6017 and performed on workplan 11489.
Common Completed workplan 11703 to change the setpoints on the diesel generator soak-back oil pressure switches (ECN-5451).
Provided engineering support for the environmental qualification program.
Performed field verifications, reviewed and prepared comments on pre-liminary QMDS requirements, and began scoping of additional work activities /
modifications required to ensure equipment qualification.
22 x
INSTRlt1ENT MAINTENANCE MONTKLY StrnARY 12-05-85 PAGE 1
~
COMP MR. COMP U FUNC SYS ADDR ESS. DATE.... DESCR IP T ION............................. CORRECTIVE ACTION.......................
~
A299300 2 Pn 030 310 11/05/85 2-PN-030-310,TROLELE SHOOT LOOP TO SIGNAL CABLE SHIELD NOT GROLDOED A CE DETERMINE PROSLEn WITH DRIFTING TSC END. RETERMINATE L&EN TERrFORAY CABLE POINT IS REMOVED.
A300823 1 PS 082 164 11/22/85 1-9S-082-164, min Y100203 DN 1 SI 102 SWITCH OUT OF CALIBRATION. RECALIBRAT DG 1AA STEP 5.3.1.1.4 LOW AIR PRESS SWITCH.
ALARn AT 188 PSI SHOULD BE 200 +0R-10 A324904 2 FI 003 1634 11/25/85 2-FI-003-163A, MNPRDW FLOW IND IS LOW FLUID REFERE>CE LEG. Br.CK FILL READING.70 CPM W/LCV CLOSED Ato AUX REFERENCE FOUTR pnp GFF A335812 0 Rn 090 102 11/26/85 0-Rn-Ov0-102. RELAY VKAR 6 DID HOT HIGH RAD SIGNAL GIVEN TD f10NITOR SO ENERGIK ON HI RAD SIGNAL FROM 0 Rn 90 RELAY WOLA_DH T NOVEDELETE REpY SI 83.
102 DURING SI 83 1 R 73 RQ% h AS GGn delthd tren 0.W A336026 0 Rn 090 103 11/04/85 0-En-090-103, als RAD MON 90-103 PLUGGED MONITOR PLUGGED INTO NON-DIVISI(NAL PLLE INTO tD4 DIVISION /L PLUGn0LD IN CAB IN CABINET. PLUG IONITOR INTO TRAIN CORRECT B/ PLUG f10LD.
A336346 0 RM 090 122 11/07/85 0-Rn-090-122, CLEAN CUT DETECTOR BACKGROUND RADIATION CAUSING FALSE POUSING. BACFGROUt0 TOO HIGH READINGS. CLEAN OUT DETECTOM M USING TO LOWER BACKGROUPO READING.
A538645 1 FT 003 489 11/04/85 1-F T-00 t-@B, HICH SIDE DRN VLV STOPPED INSTALL NEW HIGH SIDE DRAIN VALVE bP A339518 2 099 11/13/85 2--099-. atMGu INSPECT BARTON LOT 2 NONE. INSPECT BARTON LOT 2 TRAMMITTERS XnTRS f n9 HARDWIRED PIN CONNECTORS FOR HARDWIRED PIN CONNECTIONS.
A339526 2 LT 003 42 11/29/85 2-LT-003-42,HARD WIRE PIN CCtf4ECTOR FOR PIN C0!*ECTCR EED HARDWIRING PER Sn!
BARTON LOT 2 XnTR TO MAINTAIN 2-317-23.
HARDWIRE PIN Cat #ECTS Ato GUALFICMIONS PER SMI 2 317 23 RECALIBRATE TRANSNITTER.
AS41094 0 FE 090 122 11/20/85 C-FS-090-122, aIn FL0u SU NOT PICKING UP DEBRIS IN FLOWSUITCH. CLEAli OUT SWITCH-AND GIVING LIGHT (R AUDIBLE ALARf1 AFO VERIFY OPERABILITY.
i A541281 ) PS 077 liv 11/25/85 0-PS-077-119, min PRESS SW WOMT ALLOW 0 NO PROBLEM FOLDO, NOME FCV 77 119 TO BE (FEN AS46144 0 F3 065 31 A/B 11/18/85 0-FS-065-31 A/B,t4EED TO CLEAN 1 CHECK READ JUST REFEREEE BALAtO RESISTANCE RELIABILITY OF CONTACTS TO TE PR OPER VALVE A548863 1 FI 062 1 11/26/85 1-FI-062-1-A, aNDRDn #1 RCP SEAL FLOW IND AIR IN TRANSnITTER SENSIPC LIES. VENT INDICATLS APPROX 7 GPM FL0u WHEN ALL AIR FR0t1 LINES SEAL F10W IS ISOL AS48864 1 F1 062 27 11/26/85 1-FI-062-1/-A,mHPRDs 883 RCP SEAL FLOW VENT AIR FROM SEEING LIES. AIR IN "O ItOICA1ES APPROX 411/2 GPn FLOW WEN TRANSnITTER SENSING LIES ALL SEtt FLOW IS ISCL A548904 1 PDT 030 11/07/85 1-PDT-030-,INSP THE AnAPLIFIER CARD IN NONE, INSPECT Arp CARD FOR EG PROECT THE TRANSMITIER PER THE ATTATCHED VERFICATION.
F0YCORO NOTICE A348906 1 PDT 030 4311/07/85 1-PDT-030-43,INSP ATLIFIER CARD IN THE NONE, INSPECT arf CARD PER EQ PROECT 23 i
INSTRLMENT MAINTENANCE MONTHLY
SUMMARY
12-05-85 PAGE 2 COnP MR. COMP U FUNC SYS ADDR ESS. DATE.... DESCR IP TION............................. CORRECTIVE ACTION.......................
TRANSMITTER PW NEGED FOR EG PROJECT VERIFICATION.
VERIF A549040 2 LT 003 97 11/01/85 2-LT-003-97, +=uNPRDu RE CALAIBRATE SENSE LIES EED BACKFILLING. BACNFILL OTHERS READ 24% THIS ONE READS 33%
SENSE LIES.
A350568 1 TE 068 RCPI 11/26/85 1-TE-068-RCPI. REPAIR AND REPLACE WIRING BAD LUGS ON RTD'S. REptAct LUGS ON (JD LUGS ON RTD'S FOR RC Pnp 1 RTD/S A559802 1 LS 087 21 11/22/85 1-LS-037-21.NEASWE REFER LEG NONE. MEASURE REFERENCE LEC.
A359803 1 LS 087 22 11/22/85 1-LS-087, MEASWE REFER LEG NONE. NASURE REFERENCE LEG.
A359804 1 LS 087 23 11/22/B5 1-LS-087-23, nEASWE REFER LEG NDE. NASURE REFEREEE LEG.
A559806 1 LS 087 24 11/22/85 1-LS-087-24. NEASWE REFER LEG NONE. EASURE REFERENCE LEG.
A561107 2 PS 092 240 11/13/85 2-PS-082-240,00r:PR 1 DID NOT START AT PRESSURE SUITCH OUT OF CALIBRATION.
200 +0R-PSI D/G 2AA BLDG RECALIBRATE PRESERE SUITCH, A594001 2 Pn 030 311 11/05/85 2-Pn-030-311,TRCLELE SHOOT LOOP TO SIGNAL CABLE NOT GRolNCED AT DE E@.
DETERMINE PROBLEM UITH DRIFTING TSC RETERMINATE LEEN TENORARY CABLE POINT REMOVED.
2 A394002 1 PM 030 310 11/05/85 1-PM-030-310, TROLELE SHCOT LOOP TO SIGNAL CABLE NOT GROUPOED AT DE E@.
DETERMINE IF PROBLEM EXISTS ON TSC POINT RETERMINATE LAEN TENORARY CABLE REMOVED.
A394003 1 Pn 030 311 11/05/85 1-Pn-030-311, TROLELE SHOOT LOOP TO SIGNAL CABLE NOT GROLDOED AT DE E@.
l DETERMItE IF PROBLEM EXISTS WITH TSC RETERMINATE LAEH TENDRARY CABLE POINT REMOVED.
A594005 1 FT1 068 3310 11/13/85 1-Fn-068-381D, CARD DRIFTS REPLACE CARD BAD MODIFIER CARD. INSTALL E U CARD.
U/NEW CARD S/N A12972 27 records listed.
24
c..'
Mech'tien1 Maiettna*ca Section a'
November 1985 Unit 0 (1) Completed 5 year inspection on 2AA lube oil cooler.
(2) Completed monthly inspection on 2BB diesel generator.
Unit 1 (1) Completed all
'J' Tube work.
(2) Preparing reactor coolant pump #2 for starting.
(3) Machined threads off RER pump IB to detecmine weld procedure.
(4) Loaded 21 fuel bundles into core.
(5) Replaced solenoid on 1-LSV-3-174.
(6) Completed handholes on steam generator #1.
(7) Removed low pressure seals in seal table for ferrule inspection and installed new fi'ttings.
(8) Completed reroll on stean generator #1.
(9) Placed 1-VLV-63-635 back in service.
(10) Retrieved dropped bolt from steam generator #4 and closed up.
(11) Installed oil deflector on main turbine.
Unit Two (1) Adjusted main steam dump drain header.
(2) Completed SI-107.
(3) Welding completed on 2A RFP suction.
(4) Repaired MTOT Head Leak.
(5)
Inspected all but one of LP turbine explosion diaphragms, all cracked so far.
25
rECHANICAL HAINTENANCE MONTHLY EurinARY 12-05-85 PACE 1
~
MR.00rp U FUNC SYS ADDR ESS. DATE.... DESCR IP T I ON............................ CORRECTIVE ACTION.......................
A525607 1 t0R 062 1CVCH152 11/08/85 1-HGR-062-1.NCH152, REPLACE BOLT D AS BOLT D IS TO SHORT FGt REe'D TtREAD INDICATED LN SMR 0 317 21 ENGAGEE NT PER SMI O 317 21. IDETALLED EW BOLT A525608 1 10R 063 163SIH28 11/07/85 1-HGR-063-163SIH29, REPLACE BELT ' A' AS REPLACE BOLT 'A'PER SMI 0 317 21.
INDICAlED ON SMI O 317 21 INSTALLED NEW BOLT A525612 1 FCR 062 1CVCH863 11/07/85 1-HCR-062-1CVCH863, BOLT D IS TOO SHORT BOLT D TO SHORT TO FOR REe'D TMtEAD FOR REG'O THREAD ENGAGEMENT APO HAS ENGAGEFENT PER SMI O 317 21. IDEIALLED DAnAGED IHREADS NEW BOLT A528101 2 FLT 062 97 11/12/85 2-FLT-062-9/, SEAL WTR INJ FILTER HAS FLTR P4 HIGH DELTA P READIPC. REPLACED HIGH DELTA P REPLACE FILTER FLTC.
A532705 2 FCV 065 9 11/22/85 2-FCV-065-9, mHPRDu REBUILD ACTUATOR AND HA CHANGE GREASE A532706 1 FEV 065 10 11/22/85 1-FCV-045-10, nNPR0m REBUILD ACTUATOR in AND Ctur0E GREASE A532707 2 FCV 065 29 11/22/85 2-FCV-OS5-29,aNPRDs REBUILD ACTUATOR NA AT CHANGE GREASE A532722 2 FEV 030 47 11/22/85 2-FCV-030-47,mHPRDu REBUILD ACTUATOR HA CHANGE GREASE A532723 1 FIN 030 48 11/22/85 1-FCV-030-48,PHPRDn REBUILD ACTUATOR NA A536965 1 FEU 003 67 11/12/05 1-FCV-003-67,
UNESTICATE WHY VLV HA STICKING OPEN A541263 1 QtD 082 180 11/04/85 1-EMP -082-180, COMPR UNLOADER IS REPLACED DOET & DISCHARE VN.VES HYD 3
LEAKING IT IS ALSO LIFTING BOTH RELIEF UtLODER GOVERNOR REPLACED 0 RDC AN PtR9 VLVS AND WILL BUILD HOT ENOUGH PRESS SHAFT DtLY GDES TO 190 PSIG BEFORE LIFTING A543881 1 PCV 001 12 11/26/85 1-PCV-001-12,WHERE THE Tuo HALVES OF INSTALLED E W DIAPMtAGM TtE DI AP CONTROLLER BOLT TOGETTER TERE IS AN AIR LEAR A345233 0 01p 032 86 11/20/85 0-CnP-032-86, INSPECT COMPR APO REPLACE HA INTAKE VLVS AND DISCHARGE VLVS A545912 2 EFG 082 2A2 11/18/85 2-ENG-082-2A2, REPLACE THE 3/8 AIR HOSE REPLACED AIR LIES ON ALL 4 AIR START BETUEEN THE AIR HOTORS AND THE SUPPLY MOTORS HEADER AS46355 2 FLT 062 96 11/12/85 2-FLT-062-96,DP > 30 CHANGE OUT FILTER CHANGE OUT FLTR.
AS49803 1 t0R 015 11/19/85 1-tCR-015-,DETERnINE L' HETER HUTS ARE HA UELDED BEHIND THE BASEPLATE RATHER THAN THE BOLT BED 0 ANQiDRED INTO THE COHCRETE AS49805 1 10R 030 1 AffJ301 A 11/01/85 1-HCR-030-INU301 A,DETERMIE WHETHER DETERMIE L4ETER MJTS ARE FLDED TOTS ARE WELDED BENIND TE BASEPLATE BEHIlO TE BASEPLATE RATER 1 NAN SEDC RAltER Tt%H THE BOLT BEING ANCHORED ANCHORED IN TE CIMCRETE PER El9LOYEE u
- ]
nECHANICAL MAINTENANCE MONTHLY SUMARY 12-05-85 PACE 2 e
CC#1P nR.COnp U FUNC SYS ADDRESS. DATE.... DESCR I P T I ON............................. CORRECTIVE ACTION.......................
~
INTO THE CONCRETE. INVESTICATION OF CONCERN XX 85 031 001. NO FIJT FPC EnPLOYEL CONCERN XX 85 031001 CHARGE BEHIND BASEPLATE BOLTS A B C ARE 2.75" TO E661 LONG D IS 2.5 " LONG AS49808 1 FOR 074 1RHRH465 11/04/85 1 HGR-0/4-1RHRH465,DETEFnINE WHETHER DETERMIE WHETER HUTS ARE WFLDED FRITS ARE WELCED BEHIND THE BASEPLATE BELIND TE BASEPLATE RATER THAN BEIE PATHER TIGN THE BULT BEING ANCHORED ANCh0 RED IN TE CONCRETE PER ENLOYEE INTO lit CONCRETE. INVESTIGATION OF C0tCERN XX 85 031 001. Ba.T A IS 1.9" E MPLOYE E CONCERN XX 85 031 001 CHARGE LONG B IS 2.2" LONG C IS 2.1" LOPE D 10 E661 IS 2.0 " LONG A549809 1 FOR 072 1CSH449 11/04/85 1-HCR-072-105H449, DETERMINE WETHER HA Nuts ARE UELDED BEHIND THE BASEPLATE RATHER THAN THE BRT BEING ANCHORED INTO Tit CONCRETE.ItWESTICATION OF EMPLOYEE COM_ERN XX85031 CHARGE TO E661 A349810 1 FOR 063 658A4-14 11/01/85 1-HGR-063-658A4-14, DE TERMINE WHETHER DETERMINEWHETHER PR.lTS ARE WFLDED BEHDO teUTS ARE WELCED BDi!NE THE BASEPLATE TE BASEPLATE RATER THAN BEDC PATHER THAN INE BRT BEING ANCHORED INTO ANCHORED IN TE CONCRETE PER ENLOYEE THE CONCHETE INVES OF EMPLOYEE CONCERN XX 85 031 001. BG.TS C APO D XX-OSS 031-001 CHG TO E ARE 1.8" LONG B IS 1.7" LONG A IS 1.6" LONG A349811 1 t0R 063 ISIH444 11/01/85 1-HGR-063-ISlH444,DETERnlNE WHETHER DETERMIE WETER PRJTS ARE WLDED NdlS ARL UELCED BEHIND THE BASEPLATE BEHD0 TE BASEPLATE RATER TNAN BEDC PAHER ltMN THE BOLT BEING ANCHORED INTO ANCHORED IN TE CONCRETE PER ENLOYEE ThE E0rOETE. lNVEST.0F EMPLOYEE CONCERN CONCERN XX 85 031 001. >0 NUT FPC 48531001 LIMRGE TO E 661 BEHIND BASEPLATE BOLTS A C D F G H ARE 2.5 " LONG B IS 2.125" LONG E IS 2.4" LONG AS49812 1 FOR 074 H63539 11/01/85 1-HCR+74-H63537, DETERMINE WFETHER NUTS DETERMIE W>ETER PUTS ARE WFLDED AkE LELDED BEHIND TIE BASEPLATE RATHER BEHIND TE BASE PLATE RATHER THAH TreN THE COLT FEING ANCHORED INTO THE ANCHORED IN TE CONCRETE PER EWLOYEE C0tCRElt. ItNEST.0F EMPLOYEE CONCERN C0tEERN XX 85 031 001. BASE PLATE n05031001 EtMRGE TO E661 THICKESS AT BOLTS B AhD C IS 3/4" TE REST ARE 7/8".1/8" GAP AT H01 E H BETWEEH BASEPLATE ADO COERETE AS49814 1 t0R 062 1H34154 11/04/85 1-t:CR+2-1H34154,DETERMItE WETHER DETERMINE WHETER PRJTS ARE WFLDED t.UIS ARL WELEE D BEHIto THE BASEPLATE BEHIND TE BASE PLATE RATER THAN BEDE RATHER OMN lHE BRT BEING ANCHORED INTO ANCHORED IN TE CINCRETE PER ENLOYEE 1HE L0rk'kETE. IPNEST.0F EMDLOYEE C0tCERN CONCERN XX 85 031 001. BOLT A WAS FE o 8503IOO! CHARCE TO E661 1/8" TO SHORT REPLACE Sm.TA PER r5t A525606 A349815 1 FLR 062 1H34-152 11/04/85 1-tCR-O t.!-1H34-152, DETERMINE UHETHER HA 27
1
~
rECHANICAL MAINTENANCE MONTHLV SU@ARY 12-05-85 PACE 3 Corp MRoCurp U FlNC SYS ADDR ESS. DATE.... DESE R IP 110N............................. CORRECTIVE ACTION.......................
NUIS ARE WELDED BEHIND THE ASEPLATE RADIER 1HAN THE B1T BEING ANCHORED INTO THE C0rCRETE AS49816 1 10R 063 1-SIH-28 11/04/85 1-HGR-063-1-S1H-28, DE1 ERMINE WHETER DETERMIME WETER MJTS ARE WFLDED tiUIS ARE UELDED BENIND THE BASEPLATE BEHIND THE BASE PLATE RATER THAN BEllC PATHER THAN THE BOLT BEING ANCHORED INTO ANCHORED IN KTE CSCRETE PER ENLOYEE ThE CONCRE1E CONCERN XX 85 031 001. BOLT A IS 3/16" TO SHORT REPLACE PER FR A525608 NO MJT FND BEHDO BASEPLATE A349817 1 FCR 068 1-L-330 11/04/85 14 GR-Oo8-1-L-360, DETERMINE WHETHER DETERMINE WETER MJTS ARE ELDED BEHIle td1S ARE WEl_DED BEHIND THE BASEPLATE TE BASE PLATE RATER THAN BEDC PATHER THAN THE BOLT BEING ANCHORED INTO ANCHORED IN TE CONCRETE PER EFFLOYEE THE CONCRETE INVES OF EnDLOYEE CONCERN CONCERN XX 85 031 001 XX-85-031-001 C A349819 1 FOR 067 47A450 2 11/04/85 1-tGR-067-4/A450 2, DETER UHETHER HUTS DETERMIE WTERH MJTS ARE ELDED BEHDO ARE UEt DED BEHD4D THE BASEPLATE RATHER THE BASE PLATE RATER THAN BEIE IHAN ltC BOL1 BEDC ANCHORED INTO THE ANCHORED IN THE CONCRETE PER EFFLOYEE CONCRElt. INVES OF EMPLOYEE CONCERN CONCERN XX 85 031 001.NO HijT F)O BEHIle XX-85-031-001 CHARG BASEPLATE BOLTS A Ale C NO D Ale B TYPE 55D BOLT A IS 4.0" B IS 4.2" C
AND D ARE 4.1" LGC A349820 1 FOR 063 ISIH-806 11/04/83 1-HCR-Oo3-IS1H-806. DETERMINE WHETHER UHETHER HUTS ARE ELDED BEHDO TE FU1S ARE WELCED BENINE THE BASEPLATE BASEPLATE RATER THAN BEING ANCMRED IN RAitlER THAN DE BC1.T BEING ANCHCRED INTO TE CONCRETE PER EFFLOYEE CONCtRN XX 85 THt CONCRETE INVES OF ENDLOYEE CONCERN 031 001. NO Hiji F)O BEHUO BASEPLATE
- Xr-85-031-001 C BOLT C 3/8" TO SM]RT REPLACE PER FR A525609 A549821 1 FCR 063 HCR11355 11/04/85 1-t01-Oo3-HCR11355, DETERMINE WHETHER DETERMINE LAETER MJTS ARE WFLDED HUTS ARE WELDED BEHIND THE BASEPLATE BEHIND TE BASE PLATE RATER THAN BEING RATHtT IHAN THE BRT BEDC ANCHORED INTO ANCHORED IN TE CONCRETE PER ErPLOYEE THE C M PElE. INVEST. OF EMPLOYEE CCHCERN CONCERN XX 85 031 001. NO MJT Fle XX BEHIND BASEPLATE BOLTS A B C ARE 1.8" 65031001 CHARGE TO E661 LONG BOLT D IS 1.5" LOHG A549822 1 FCR 063 ISlH 110 11/04/85 1-tCR-033-ISIH 110. DETERMINE WHETHER DETERMINE WETER MJTS ARE WFLDED huts AHL WEL DED BDilNE THE BASEPLATE BEHIND THE BASEPLATE RATER THAN BEIls RAIMER THAN THE BRT BEING ANCHORED INTO ANCHORED IN TE CONCRETE PER EFFLOYEE ltE COWR' TE INVES OF EMPLOYEE CONCERN CONCERN XX 85 031 001. NO NJT F)O t
XX-85-031-001 C BEHIND BASEPLATE BOLT C IS 5/8" DIA TE REST ARE 1/2" BOLTS A AM) B ARE 2.2" L0t0 C IS 1.9" LDMG 28 i
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F1ECHANICAL FIAINTENANCE f10NTFLY SumARY 12-05-85 PACE 5 COMP MR. CON U FLNC SYS ADDRESS. DATE.... DESCR IP T 10N............................. CORRECTIVE ACTION.......................
A549831 1 FOR 062 1CVCH-86 11/19/85 1-HCR-062-1CVCH-86, DETERMINE WETER NA MUTS ARE WELDED BEHIND THE BASEPLATE RATHER THAN THE Ba.T BEING ANCHORED INTO THE CONCRETE A547834 1 t0R 067 11/04/85 1-HCR-067,CETERMINE WHETHER HUTS ARE DETERMINE L&ETER DRITS ARE WFLDED UELDED BEHIND THE BASEPLATE RATER THAN BENIND TE BASE PLATE RATER THAN SEIDE THE BOL.T BEING ANCHORED INTO THE ANCHORED IN TE CONCRETE PER EWLOYEE CONCRETE.ItEEST.0F EMPLOYEE CONCERN CONCERN XX 85 31 001. BOLTS A APG B ARE XX85031001 CHARGE TO E661 4.3" LONG. BOLTS C AND D ARE 4.4** LODE A550569 1 FCV 062 177 11/07/85 1-FCV-062-177,VLV LEAKS AND WTR SPRAYS VLU LEAKS DUE TO WWIN DIAP. INSTALLE0 OUT OF THE SEAL NEU DIAP A561756 1 RV 067 50EA 11/17/85 14'LV-067-50BA, INSPECT VLV IN REMOVED VLV IN ACCORDAEE W/SI 166.37 ACCORDANCE U/SI 166.37 FOR ENGRG TEST TO CECK (56175/ 1 RV 067 513A 11/17/85 14tV-067-513A, INSPECT VLV IN REMOVED VLV IN ACCORDAE E U/SI 166.37 ACCCRDANCE U/SI 166.37 FOR ENGRG TEST TO CECK A561761 2 RV 067 512A 11/17/85 2-VLV-067-512A, INSPECT VLV IN INSPECT VLV PER SI 166.38 ACCORDANCE U/SI 166.38 A561763 2 RV 067 517A 11/17/85 24tV-Oo7-517A, INSPECT VLV IN INSPECT VLV PCR SI 166.38 ACCORDAFEE U/SI 166.33 44 records lasted.
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i 30 3
TECHANICAL FIAINTENANCE f10HTHLY Strt1ARY 12-05-85 PAGE 1 C0rF r1R. HIST U RNC SYS ADDR ESS. DATE.... DESCR IP T I ON............................. CORRECTIVE ACTI(M.......................
AS49033 0 R.V 026 1036 11/12/85 0-VLU-026-1034. DRIP CK VLV IS LEAKING VLV LEAKING TIRU OtE TO LOIN INTERNALS.
TINU AND HANDLE IS ftISSING INSTALLED EU ULV On2 record listed.
31
.f FIECHANICAL riAINTENANCE f10NTHLY SUIT 1ARY 12-05-85 PACE 1 conp FR 2.... U RJNC SYS A00R ESS. DATE.... DESCR IN 10N............................. CORRECTIVE ACTION.......................
A521089 1 R.V 067 566C 11/02/851-VLV-067-566C RV LEAKING TFRU. REPAIR LEAKING T)RU DLE TO DIRTY INTERNALS.
CLEAED INTERNALS RETLRe TO SERV.
A521092 1 RV 062 505 11/01/85 1-(tv-062-505.5ET ULV AT 220 PSIG PER SET VLV AT 220 PSIG PER SI 164 SI 164 INST CHANGE 85 1213.VLV UAS SET AT 150 PSIG PER rR A521090 1 HA3 NOT BEEN RETT @NED TO ERV. ERROR IDENTIFIED CN dug 47u811-1 A533170 0 RV 078 11/17/85 0-ttV-078-.RErKNE VLV. TEST APO REPAIR REf10VE VLV TEST AM) REPAN. LAPPE0 THIS r1UST BE WORKED UHILE THE SPENT FLEL SEATSACLEAED INTERNALS;!ET EV AT 30 PIT CATE IS OUT.CINTACT tin f1ASSEY e PSIG 6869 UHE'l READY TO UORK 3 recorJs listed.
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32
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SUMMARY
OF WORK COMPLETED MODIFICATIONS NOVEMBER 1985 NUREG 0588 ECN 6231 - Remove Interferences ERCW hangers and piping located in the annulus were removed for access to the motor operators.
Efforts were lettiated with OE to redesign the supports and piping configuration.
See attached listing.
APPENDIX R ECNs 5265, 5435, and 6343 - Fire Doors The postmodification test was performed with excess leakage found around the door latch and corners. Resolution is continuing.
ECN 6235 - Reroute Various Cables Work is on hold for the nine workplans previously in work.
Workplan writing is on hold.
ECN 6305 - Elevation 714 Fire Barrier Framing and penetration work is near completion.
Installation of fire board has not begun.
ECN 6311 - Operator Extension on PORV Installation work was started on both units.
ECN 6315 - Replace fuses No work was performed this month.
ECN 6319 - Fire Protection Piping Installation of piping and hangers was resumed.
OTHER ITEMS ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steet Unit I upper compartment cooler work was completed.
Prefabrication activities for unit 2 work in the same area were started.
The auxiliary air compressor piping changeout was completed. An additional hanger is being installed.
33
OTHER ITEMS (Continued)
/
ECNs 5034, 5713, and 5743 - Various Platforms in Lower Containment
' Platform work between Nos. I and 4 steam generators was completed, and the application of protective coating was begun. Prefabrica-tion and installation activities between Nos. 2 and 3 steam generators continue. Work will be discontinued during CILRT.
ECN 5198 - Technical Support Centet SPDA consoles were installed in accordance with ECN 6152.
ECN 5200 - Postaccident Sampling Facility 7
No work was performed this period.
ECN 5202 - Fifth Diesel Generator The tape coat was satisfactorily tested. The workplan was approved for backfilling, which will begin in early December. Workplans are being prepared for electrical interface work.
ECN 5237 - Laundry Facility No work was performed this. period.
\\.
ECN 5252 - Label Node Voltages in Manholes No progress on this job this period; four manholes remain.
ECN 5347 - Replace Doors C-49 and C-50 (Electrical Portion) g
\\
s This work in on hold until door C-50 passes the leak test.
ECN 5373 - Condensate Demineralizer Air Compressor The decision was made to modify the existing system tie-in points
(
'or the air. OE is working on the revised design.
Installation will follow.
ECN 5620 - Ad.1 Instrumentation for Auxiliary Feedwater Pump Work is on hold.
ECN 5645., Replacement of Flow-Control Valve 2-329
(
The vendor representative is expected the first week of December to modify the valve.
s ECN 5657 - Installation of MSR Drain Valves N
s The unit 2 workplan to t istall approximately 150 drain valves is
.c in the approval cycle. Qnsulationreinstallationonunit I still remains incomplete.
34 s
's
7 OTHER ITEMS (C:ntinued)
ECN 5795 - Field Services Building Fire detection system work is on hold for materials.
ECN 5914 - Improve Reliability of Steam Dump Conduit is complete; valve remains to be wired in.
ECNs 5938 and 6506 - Feedwater Heater Replacement Installation activities are continuing on unit 1.
All large piping has been completed on unit 2.
Installation of miscellaneous small piping continues, and insulation work on unit 2 continues.
ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced.
ECN 6147 - Airlock Packing Nut The-installation of the antirotation devices on the unit I airlock shaft packing nuts was completed.
ECN 6152 - SPDS ASE consoles have been installed. One console in each horseshoe has been installed.
ECN 6196 - Pressurizer Hangers and Valves All hangers except one have been completed.
Insulation work has been completed as far as possible until ECN 6495 has been completed.
- The remaining work will be completed af ter CILRT.
ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete. A technical specification change to place the circuits in operation has been received.
ECNs 6251 and 6532 - Waste Disposal Hangers OE has determined that a review of an additional support was requited on each unit. The unit I work was completed.
OE is preparing a unit 2 drawing for issue. Workplan preparation will continue upon receipt.
ECN 6259 - Motsture Separator Reheater Tube Bundle Heplacement SECO completed their work and left the site. The reinstallation of the doghouses was started.
Insulation work was begun.
35
OTHER ITEMS (Cutituad)
ECN 6263 - Feedwater Hangers Lower Containment One support was completed, and work continues on the others.
ECN 6352 - Fire Protection Isolation Valves No work was performed this period.
ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation The unit 1 piping is complete through the second valve, allowing sweep and vent activities to continue. The remaining piping will be completed after CILRT.
ECN 6417 - Install Alternate Seal Water for Pwnps, CDWE Electrical drawings remain to be issued.
ECN 6491 - ERCW Supports The reanalysis of the ERCW support scheme was completed with approximately 47 supports requiring modification. Workplans were written, approved, and placed in work status for 20 supports.
Workplan preparation continues for the remaining supports.
ECN 6494 - ERCW Pipe Replacement at CCW Heat Exchangers All piping work has been completed. The changeout of the deterio-rated valve is scheduled to be performed when the CCW heat exchanger retube work is performed.
ECN 6495 - Modification of Pressurizer Pots This workplan was approved and placed in work status. The root valve has been replaced, the core drills made, and the piping work started. This work will be discontinued during CILRT.
36 i
Dets: 12/3/55
,[
Estimated Date of Completion SCR No.
Description Nemo ECN lasued Drawings Entineer Workplan No.
U-!
U-2 Comments EQP 8501 Disconnect 1- & 2-HS-62-61 9/18 6524 Yes
!!/29-30 12/31 12/24 Drawings issued.
EQP 8502 Replace penetrations 23, as 9/13 6490 Yes Yes Peters 11801, 18802, 12/8 12/8 Termination of cables is impacting 11810, 18811 schedule.
EQP 8503 Relocate RE-90-273, -274 9/25 6500 Yes Yes Peters
!!810, !!811 12/8 'N/A REs are relocated. Functional test is constrained by penetration work.
EQP 8504 Splice methode not correct 10/2 N/A N/A N/A Stockton
-C j:
Verifylag completion.
10/11' N/A N/A N/A N/A N/A N/A N/A l
EQP 8505 Drawing EQP 8506 Seal catet isolation valve 10/17 6514 Yes.
Yes Kinsey 12/20 12/15 Writing workplan.
EQP 8507 Rew!re MOV 10/29 N/A N/A N/A Rutledge 12/31 12/23 Rewired-55. Functioned-1. HOV ATS ___.
EQP 8508 JB weepholes (press) 10/17 6523 12/12 12/24 12/17 EQP 8509R1 Conduit seals 11/6 6529 11/29 12/17 12/19 12/12 EQP 8510 Disconnect local hand-
!!/12 6527 12/8 1/4 12/29 switches EQP 8511 Submerged JB inside catet 11/13 No longer an issue.
I EQP 8512R2 Rewire JB N/A N/A N/A N/A Amburn 12/24 12/16 U-2 58/83. U-l 1/91.
EQP 8513 Weep holes (motsture)
!!/14 6547 !!/29 12/12 12/23 12/16 EQP 8514 Motor insulation 74-1, -2 11/14 6540 12/3 N/A 12/24 Motors espected 11/28.
EQP 8515 Replace 2-FDT-30-43 11/15, 6546 12/8 N/A 12/30 This ECW will resolve 8514 and 8529.
EQP 8516 Replace 2-LT-3-174
!!/15 N/A Instrument.
M/A 12/5 To be done by HA.
Maintenance 31
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Dota 12/3/e5 e
P2g1 2 EIt1 mated Date of f*
Coseletion Memo ECN lasued Drawings Engineer Workplan No.
U-l U-2 Comments SCR No.
Description N/A 12/30 12/5 Fatture evatustion.
i EQP 8517' ABCTs humidity control 12/31_ 12/31 38/ unit. Writing workplans.
11/15 6533 11/27 1,l/27 EQP 8518 Submerged cables 11/22 N/A N/A N/A Electrical 12/23 12/23 22/23.
EQP 8519 Tee draine Maintenance 1/13 1/13 5 cables / unit.
11/22 6553 12/5 12/12 I
EQP 8520 Expired cables 12/26 12/26 EQP 8521 Delete T8 and rework splices !!/22 6550 12/11 12/17 12/17 Writing workplan to cover 5522, 8523,
!!/26
- Stockton and 8527.
EQP 8522 Rewire local panels N/A
'N/A N/A N/A Stockton 12/20 12/20 Wrlting workplan to cover 8522, a223, 4
and 8527.
EQP 8523 Missing bolts and washers i
(MR) and misplaced brackets 12/24 12/24 11/26 6551 12/6 12/13 instrument
.EQP 8524 Change setpoints Haintenance i
EQP 8525 Reterminate hydrogen N/A N/A N/A N/A Electrical 12/20 12/20 Maintenance (MR) recombiner 12/30 EQP 8526 Replace FSVs. U-l 1. U-2 11 11/26 6552 12/11 LQP 8527 Coat 18. U-l 3 U-2 8 N/A N/A N/A N/A Stockton 12/9 12/9 Writing workplan to cover 8322, 822),
and 8527.
(MR) 12/10 12/10 Work in progress.
lastrument EQP 8528 Solder strain gauge Barton 11/2s IM1 Maintenance transmitters.
12/30 12/30 i
EQP 8529 PDT-30-42. -43 capacitor 11/26 6546 12/8 EQP 8530 Casket, Namco L/S N/A N/A N/A N/A Electrical 12/15 12/15 38 MRs written.
Mai *enance (MR) 1
\\x N.
O I
I
l O
Pc 3 3 Data: 12/3/85 i.,
Estimated Date of Completion SCR No.
Description Memo ECN lesued Drawlags Engineer Workplan No.
U-l U-2 Comments EQP 8531 Delete HOV heaters 6544 !!/27 12/9 Rutledge 12/31 12/23 Incorporated in Hov rewire workplan.
Drawings are FCR'd.
EQP 8532 Delete L/S 1. 2-43-201
-202. -207. and -208 EQP 8533 Delete dual voltage splice N/A N/A N/A Rutledge 12/31 12/23 Incorporated in H0V rewire workplan.
EQP 6534 Respace valve positioner 3-174 ar.J -175 EQP 8535 Replace limit switches. U-l 10 U-2 12.
4 I
I
'NN N\\
S I
e Piss 6 Dets: 12/3/85
~
Estimated
' ~
Date of 6
I Completion
=
SCR No.
Description Memo ECN issued Drawings Engineer Workplan No.
U-!
U-2 Comments N/A Move surge suppression N/A 5773 Yes Yes Kinsey 12/6 12/6 Workplan in approval cycle 12/3/85.
network for PORV i
EEB 8523 Penetration overcurrent 6204 Yes Yes Legg 12/31 12/31 6204 and 6219 are complete. Writing protection 6219 workplan on 6452. Material expected 6452 12/16/85.
N/A Work FCR to delete 1 N/A 5883 Yes Yes Hall 11/27 11/27 Instrument Maintenance calibrating.
2-PS-3-160A, -1608. -165A.
and -1658 N/A Replace X-FT-t-3A, -35,
. N/A 6347 Yes Yes Instrument
?
N/A
-10A, -105, s21A, -218 Maintenance
-28A. -288 i
NEB 8510 Relocate LT-68-320, N/A 6439 U-!
U-l Carrasquillo 32/20 12/31 U-1 conduit in progress.
PY-68-323; -320 U-2 Peters U'-2 in submerged cable workplan.
Remount 63-71,68-308 N/A 6496 Yes Yes Legg 18865 11/27 12/5 U-I 63/71 complete.. Making brackets for others.
Replace LS-65-4, -5 N/A 6504 Yes.
Yes Legg 11865 11/27 12/b ME8 8410R3 Replace LS-77-127
!!/22 6525 Yes Yes Legg 11865
!!/27 12/5 Delete brakes FCV-62-61 6521 Yes 12/3 12/31 12/23 Notor onstte. dears on way.
Expected delivery date was 11/27/d5.
e e
40 f
\\
s
\\.
- e I
I
' l '." y SEQUOYAll NUCLEAR PLANT FUEL' CYCLE DESIGN BASIS INFORMATION SHEET Unit 1 Cycle 3 Cycle 4 Cycle 5 Cycle 6 Cycle 7 Operating Cycle Length (Days) 492 501 503 502 499 00perating Capacity Factors 76 85 85 85 85 Scheduled Mid-cycle Outage Days 37 17 17 17 17 Estimated Coastdo'.m Days 1
6 3
2 0
Core Full Power Days 345 405 410 410 410 Unit 2 Cycke6 Cycle 7 Cycle 3 Cycle 4 Cycle 5 Operating Cycic Length (Days) 576 510 502 501 506
- 0perating Capacity Factors 64 85 85 85 35 Scheduled Mid-cycle Outage Days 0
17 17 17 17 Estimated Coaatdawn Days 5
9 2
1 o
Core Full Power Days 364 410 410 410 410 ATP:CCM 12/03/S5 41
SEQUOYAM NUCLEAR Pl. ANT DATE
SUMMARY
OF UPCOMINC OUTACES Start Duration Finish Unit 1
[
Date (Days)
Date Initial criticality 07/05/80 Ul, C3 08/22/85 158*
01/27/86*
Surveillance /lce 03/13/87 17 03/30/87 U1, C4 06/12/87*
50 08/01/87*
Surveillance / Ice 09/23/88
'.17 10/10/88 Ul, C5 12/16/88*
51 02/05/89*
Surveillance / Ice 03/09/90 17 03/26/90 Ul, C6 06/22/90*
75 09/05/90*
Surveillance / Ice 09/27/91 17 10/14/91 U1, C7 01/17/92*
45 03/02/9;*
Start Duration Finish Unit 2 Date (Days)
Date t
Initial Criticality 11/05/81 U2, C3 07/25/86*
50 09/13/86*
Surveillance / Ice 09/18/87 17 10/05/87 U2, C4 02/05/88*
51 03/27/88*
Surveillance / Ice 03/10/89 17 03/27/89 U2, C5
-08/11/89*
45 09/25/89*
Surveillance / Ice ~
09/28/90 17 10/15/90
-U2, C6 02/08/91*
75 04/2?/91*
Survictlance/ Ice 03/27/92 17 04/13/92 U2, C7 09 /11/ 9'!*
45 10/26/92*
NOTE: The unit 2 schedule assumes a 01/23/86 return-to-service from the forced outage thdt began on 08//l/85.
- Denotes changes since last update.
ATP:CCM 12/03/85 42
- f..
. ;u TENNESSEE VALLEY. AUTHORITY Sequoyah Nuclear. Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 December 13, 1985-Nuclear Regulatory Commission Office of Managemenc-Information
.and Program Control
. Washington,-DC. 20555' Gentlemen:
~
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - NOVEMBER 1985 Enclosed is the November 1985 Monthly Operating Report to the NRC for Seitoyah Nuclear Plant.
- Ver, atly yours, TENNESSEE VALLEY AUTHORITY l
JL- ~
P. R.~Wallace Plant Manager
. Enclosure
-cc (Enclosure):
- Director, Region II INP0 Records Center Nuclear-Regulatory Commission Suite 1500 Office of Inspection and Enforcement 1100 Circle 75 Parkway 101 Marietta Street Atlanta,'GA 30339 (1 copy)
Suite 3100 -
Atlanta,'GA 30323 (1 copy)
Director, Office of Inspection and Enforcement-Nuclear Regulatory Commission Washington, DC'(12 copies)
Mr. A. Rubio, Director
-Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 (1 copy)
- Mr. R. C. Goodspeed MNC 461.
- Westinghouse Electric Corporation Pittsburgh, PA 15230 (1 copy)
Mr. K. M. Jenison, Resident NRC Inspector Sequoyah Nuclear Plant
' i 1983-TVA SOTH ANNIVERSARY An Equal Opportunity Employer
_L: