ML20236W150
| ML20236W150 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/31/1987 |
| From: | Nobles L TENNESSEE VALLEY AUTHORITY |
| To: | NRC |
| References | |
| NUDOCS 8712070302 | |
| Download: ML20236W150 (46) | |
Text
_ _ _ _ _ _ - - _
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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION "0CTOBER 1987" i
UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79
[
Submitted by:
U L. M. Nobles, Plant Manager 8712070302 871031 g
DR ADOCK 0500
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t TABLE OF CONTENTS Page I.
Operational Summary Performance. Summary-1 Significant Operational Events 1
Fuel Performance and Spent Fuel Storage Capabilities 2
Spent Fuel Pit Inventory 2
PORVs and Safety Valves Summary 2
Special Reports 2
Licensee Events 3-5 Offsite Dose Calculation Manual Changes 6
II.
Operating Statistics A.
NRC deports Unit One Statistics 7-9 Unit Two Statistics 10-12 B.
TVA Reports Nuclear Plant Operating Statistics 13 Reactor Histogram 14 Unit Outage and Availability 15-16 III.
Maintenance Summary Electrical Maintenance 17-18 Instrument Maintenance 19-26 Mechanical Maintenance 27 Modifications 28-40 0288f
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OPERATIONAL
SUMMARY
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PERFORMANCE
SUMMARY
October 1987 The following summary describes.the'significant operational activities for the month o,f October.
In support of this summary, a chronological log of-significant events is included in this report.
The units remained in an administrative shutdown the entire month due to design control review, configuration control updating, and resolution of significant employee concerns.
Outage related maintenance and modifications are being performed.
Unit l' has been of f-line 800 days.
Unit 2 has been of f-line 801 days.
Preparatations are underway for unit 2 alignment and mode 4 verification.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 10/01/87 0001E The reactor was in mode 5.
The adr.iinistrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
10/31/87 2400E The reactor was in mode 5.
The administrative shutdown due'to design control review, configuration control updating, and resolution of significant employee concerns continues.
Unit 2 i
Date Time Event 10/01/87 0001E The reactor was in mode 5.
The administrative j
shutdown due to design control review, configuration j
control updating, and resolution of significant employee concerns continues.
Preparations are underway for system alignment for mode 4 shakedown.
10/31/87 2400E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
Preparations are underway for system alignment for mode 4 shakedown.
l 1 ___ ___ _ _- _._-_____________ _ _-_ _
FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during October was 0 MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTV.
Unit 2 The core average fuel exposure accumulated during October was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTV.
SPENT FUEL PIT STORAGE CAPA8ILITIES The total storage capability in the spent fuel pit (SFP) is 1,386.
- However, there are five cell locations which are incapable of storing spent fuel.
'i 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
l No PORVs or safety valves were challenged in October 1987.
I i
SPECIAL REPORTS The following special reports was submitted to NRC in October 1987.
87-13 On September 22, 1987, two fire breach permits that were issued on September 15, 1987, for fire door C-23 (computer room) and turbine / control buildings fire wall penetrations exceeded the seven-day limit.
On October 3, 1987, the carbon dioxide fire suppression system for the computer room was out of service-greater than fourteen days.
(
LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear t
Regulatory Commission in October 1987.
Description of Event LER l-87048 This report was submitted as a " voluntary LER" to identify a potential problem with silicone rubber insulated cables.
An employee concern that originated at Watts Bar Nuclear Plant suggested that cable pulling practices could have damaged the cables and could result in failures.
General Construction Specification G-38, " Installing Insulated Cables Rated Up To 15,000 Volts," prescribed the materials and procedures for s
installing, terminating, splicing, and marking field-installed cables at both Watts Bar Nuclear Plant and Sequoyah Nuclear Plant.
Subsequently, high-potential cable tests were conducted to assess damage associated with pull-bys, jamming, and vertical cable supported by 90 degree condulets.
Favorable results were obtained from the tests with the exception of the vertical cables supported by 90 degree condulets.
On April 22,1987, 3 out of 16 conductors that wdre considered worst-case vertical drop cables failed the high-potential test. After laboratory testing, it was determined that the cables had not failed at the 90 degree condulets that supported the vertical cable (high-stress point).
However, it was discovered that silicone rubber cables were more susceptible to impact damage than expected.
A 10 CFR Part 21 Report was submitted on September 10, 1987, for silicone rubber insulated cables as additional failures occurred during testing.
The root cause of this nonconformance is unknown.
TVA has been unable to consistently correlate the test data to the nonconformance identified. Additional testing will be performed and evaluated to provide a level of confidence in the integrity of the cable.
1-87058 On September 26, 1987, the start of 2B-B 0/G was noted by the control room operator.
The generator started because Operations personnel failed to render the diesel physically inoperable before pulling the fuses in circuit C-3 on vital battery board IV that goes to 2B-B shutdown board logic panel.
The pulling of the fuses caused a loss of power. The cause of this event was personnel error due to inadequate preplanning.
Personnel were informed about the importance of preplanning for tagging and removing equipment from service.
1-87062 On September 11, 1987, at 1345E, an unplanned loss of tornado generator missile protection for cables associated with D/Gs 1B-B and 28-B was identified.
This condition resulted from the excavation of earth and the cutting of a hole in the side of manhole (MH) 78 for the installation of additional conduits as part of an approved modification.
It was also noted that the covers l
that were installed on MH 7B did not meet missile protection l
requirements.
This determination resulted in "B" train 0/Gs being j
inoperable. The modification was changed to require that a steei plate be placed over the hole in MH 78.
Following the installation j
of the permanent manhole covers, the 0/Gs were declared operable.
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Description of Event
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LFR l-87062 On October.2, 1987, it was determined that the excavated portion of (cont.)
the concrete wall for MH 7B did not provide adequate missile.
protection without an earth cover, and the temporary plate covering.
thq hole.was inadequate because of improper. mounting.
This finding did not require a change to 0/G status since both "B" train D/Gs l
were already inoperable for unrelated maintenance.
The missile l
protection deficiency was corrected by placing spare missile shields in front nf the' excavated section of MH 78.
This event was a failure to identify MH 78 as a Category-I. structure and the modification as a safety-related activity during design change
. preparation, compounded by a failure of the approval / review process to adequately evaluate the affect of the construction activity on the plant operability status.
A contributing factor was that the review process did not require changes to the modification workplan to receive a review equivalent to that of the original'workplan.
Modification procedures and programs are being evaluated for adequacy with respect to missile protection requirements.
1-87063 On September 24,1987, at-1057E, an inadvertent CRI was ' initiated by an diligator clip accidently coming in contact with two terminal points simultaneously during the performance of SI-82, " Functional Test For Radiation Monitoring System." This defeated the block function on monitor 0-RM-90-126, causing a high radiation signal.
The CRI was reset after determining the signal was invalid. An investigation was performed that verified that the high radiation signal was caused by an alligator clip making contact with two terminals. 51-82 will be revised to ensure no alligator clips are used for this procedure and will address all RMs.
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j ABBREVIATIOMF 1.
ABI
- Auxiliary Building Isolation 2.
- Auxiliary Feedwater 3.
A01 Abnormal Operating Condition
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4.
BAT
- Boric Acid Storage Tank 5.
BIT Boron Injection Tank 6.
CCS Component Cooling System
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CRI
- Control Room Isolation 8.
CREV - Cent.ol Room Emergency Ventilation System t _,
! w 9.
- Contairn, ent Spray System t
/
- 10. CVI
- Containment Ventilation Isolation h
11.
D/G(s)- Diesel Generator (s) 12.
- Detion Change Request 13.
- Division of Nuclear Engineering A '
1 14.
ECCS - Emergency Core Cooling Syst'em
/
15.
- Engineering Change _ Notice J
16.
EGTS - Emergency Gas Treatunt System p' j ',
17.
- Electromagnetic Interference s,-
18.
ERCW - Essential Rav Cooling Water
/
19.
- Engineeret Safety Feature
/,
8 20.
- Flow Control kalve (l"
21.
FSAR - Final Safety Analysis Report 22.
IMI
- Instrument Maintenance Instruction /
23.
LCO
- Limiting Condition for Operation
'?g 24.
LOCA - Loss Of Coolant Accident 25.
- Main Coatrol Room
[
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PORC - Plant Operation Review Committee
_p 27.
- Reactor Coolant System 28.
- Residual Heat Rem. oval 29.
- Radiation Monitor (RAD Monitor / RAD MON) 30.
RWST - Refueling Water Storage Tank 31.
- Significant Condition Report 32.
S/G(s)- Steam Generator (s) 33.
- Surveillance Instruction /or Safety Injection 34.
SON
- Sequoyah Nuclear Plant I
35.
SR
- Surveillance Requirement f
36.
SSP 5 - Solid State Protection System
}
37.
TACF - Temporary Alteration Control form 4
38.
TI
- Technical Instruction
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39.
TS(s) - Technical Specification (s) l
- 40. WP
- Workplan
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s'MTSITE 00$E CALCULATION MANUAL CHANGES y
No changef,were made to the Sequoyah offsite dose calculation manual during the month.
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4 OPERATING STATISTICS (NRC REPORTS) t i
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OPERATING DATA REPORT DOCKET NO. 50-327 DATE NOVEMBER 10,1987 COMPLETED DY D.C.DUPREE TELEPHONE (615)870-6722 OPERATING STATUS 1.
UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1
NOTES:
2.
REPORT PERIOD: OCTOBER 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 C.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHIC'H RESTRICTED,IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
5 THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 745.00 7296.00 55537.00
- 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 23781.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-2008.00
-38746.00 24863813.00
- 19. UNIT SERVICE FACTOR O.00 0.00 42.82
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 42.82
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 39.00
- 22. UNIT CAPACITY FACTOR (USINO DER NET) 0.00 0.00 39.00
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 48.96
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
- 25. IF SHllTDOWN 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.
I NOTE THAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED..
SEODOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 1
UNIT : ONE DATE : NOVEMBER 06,1987 COMPLETED BY : D.
C.
DUPREE I
TELEPHONE':(615)870-6544 MONTH: OCTOBER 1987 l
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL 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 0
06 O
22 0
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 0
16 0
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OPERATING DATA' REPORT DOCKET NO. 50-328 DATE NOVEMBER 10,1987 l
COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6722
' OPERATING STAI,US i
1.
UNIT NAME: SEGUDYAH NUCLEAR PLANT, UNIT 2
NOTES:
J 2.
REPORT PERIOD: OCTOBER 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 C.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
e.
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 745.00 7296.00 47497.00
- 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)
-5006.00
-51194.00 22516329.60
- 19. UNIT SERVICE FACTOR O.00 0.00 45.25
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 45.25
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 41.29
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 41.29
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 49.55
- 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:
PREPARATIONS ARE NOW UNDERWAY FOR SYSTEM ALIGNMENT. THE STARTUP OF UNIT-2 IS UNDETERMINED AT THIS TIME.
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
' t
OPERATING STATISTICS (TVA REPORTS)
r.v4 ras:Anw +su' NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR-Plant Period Hours 745 Month OCTOBER 19 87 f
item No.
Unit No.
UNIT ONE UNIT TWO PLANT I
Averaae Hourly Gross Load, kW 0
0 0
2 Maximum Hour Net Generation, MWh 0
0 0
3 Core Thermal Enerov 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 j
6 Station Use, MWh 2.008 5.006 7.014 E
7 Net Electrical Gen., MWh 2.008 8
Station Use, Percent
-5.006
-7.014 N/A N/A N/A 9
Accum. Core Avg. Exposure, MWD / Ton!
0 0
0 10 CTEG This Month,106 BTU n
0 0
6 11 SGTEG This Month 10 BTU
'O O
O 12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use, Hours Min.
0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 16 Turbine Avail. Facter, 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 y J Gross Heat Rate, Btu /kWh N/A N/A N/A j
25 Net Heat Rate, Btu /kWh N/A N/A N/A E
26 W'
27 g
28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature *F N/A N/A N/A 30 Exhaust Pressure, inHg Abs.
N/A N/A N/A E
31 Intake Water Terno., *F N/A N/A N/A 32 33 Main Feedwater, M lb/hr N/A N/A N/A y
34 35 36 37 Full Power Capacity, EFPD 404.86 360.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 j
39 Oil Fired for Generation, Gallons 29,898 2
40 Oil Heatina value. Btu / Gal.
138,000 l
41 Deal Generation. MWh 453 4?
Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor. %
=
43 N/A N/A N/A N/A N/A N/A 3
Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
j 2(t) indicates Thermal Energy.
3m Date Submitted Date Revised _
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SUMMARY
Of MAINTENANCE ACTIVITIES t
6 i
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e MAINTENANCE
SUMMARY
(ELECTRICAL) l l
f MO,id'( lC[I'I.!.
,,0 9?ECf i.9t?ER.10f E UA3.40T GEii1NC UFCH
'1
'l
.)-Ld3 :.M 0?PATE!N Uf FAM. LonPEH tl0TCR STAYING
' MII "# CLDIE0 uHEN Ei!ERCIZED. iCUND
. E::'NF Sufit:1 : DI.niTRan WGRCOC
'JH"; et 7 NDPER 1-ir.': ) 863 REtu1HED U:',: :' 'EPWED Nt""'! !!'ilC9.
+-
5 r >c,rL;) *. g g;gp;;; ;p;,9 t:1
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,.q
+
c; "EME" U RD IP IMit.Hl.CUS TRI? TEST.
':Ti!!T5? ;FJ/S.' OM A PE!I Ment.Est.
s
.: Elm-.utc; c!.';.75.2 :Usini Jia:j2 W m f. F:.D' c;'.D ;I-3?:1.2 UN JCW
'Ri MFP. ;:LP140E0 tREAGR.
- F63 /.
A.:C r.' v6 in 0 F5ia!E KnS UPEN UN PDKEQ 4C1 CURING II-273.2 FC::Fl!Rf;nNCE REPLACED BREAKER M.U Y1--2t': 1.
21';N 2
.?.. m-MJ ;E I;':T MD
?i'D MCni TffiCE CCNTROLLEl! PDISIBLY DUE T
P "30 i3 3Xirl LEid f:EPLfiCE0 IIEAT TRACE E. !!:!Clj.2!. diTJaTED 1:!! 1: 2h202 TD
':EF3T!! TriC::!!'!! C::1T!fLllit.
T '-
J M:
- 9..
0?CE'.9 FMLL) PERf!:RJAF.CE ili SI-;53.d.4
.t'
- t 7 C.T/cL" RENT TE27. FEPLACED CIRCUIT i'
"'::AT!.
"tl3 I:n PEC:MtED DH NEW
.ne:rs r'M:E T::2 fall.il):!M.
- + Dis :r1T TU:: ::: i!!: CIPCHIT Ris Mui INSTALLED
.'. c 01 '
' Ps r'r,'ERL't.
PECrE9 TCOr.TK CI'!CllIT RD
.i.
12;lrn llr 1 LGDr. C'lf.le.LD. CLEMED iin;s,J.D t LC"!:r MD a'AlltsTED FUSE
. IP; "" Giltt 3 J D PM PF. FLY:
J:C!:IT.l.JC
..E t:D CCH. CRU31:ES m "p CH 1ti;l.1tl lit,1D.
M3
. L ' E " L L
- 1 TU.E CLi? UJ2 LUME W llaKIr:C PDDR i
' jf :'I ;;H. CD:!InCT /ETEREMCE IPN-87-021. THE FU'E i'Lf!Cr Fr?Ilic C1.IPS ifrPEF. RED 10 liAVE TEta::En IllE SPRING TENSIVN DUC f0 Titt REUD';tt aHD REPL?.CET.EHi lif THESC TUSES.
IEr.:T)D fli!fS. WID !!1i!E3 AMD LITTED rr.':1 :P3 /r:. 3.PLnCD IU!E HULDERS TP 5
- " c:!o PC f H;inLLTD W f. ER 0:1D f uSE.
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at D:CE :i'.E "Cf.R. JEPl.7:E0 utL CIE'JIT E n;!
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."/X9 t0:lIRDLLER H
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MAINTENANCE
SUMMARY
(INSTRUMENTATION)
I
- ?
.2 Ob'
- = '
CDiMECTIVE ACTICN.
i
(
- LIQ:;
' ' T2 PE?!1,CE AS G58205159 CHEi'ED ON I!!T-Mk.1 INST ALLED l
IN 415 AND RE.TlED DEFECTFJE TC RDn 915. CEPL R E9 S.~C AHD (UlTH LiitiPS.
- TPLICLD CAPaCIitM C4, TUHi. CHECRED AHD 1
'L:n D UI SWF:' G T1: t.
)
7' l', I"!T3LLD ["L'ER, ET'UHfD C0'.'E.h C2'.'!r.
LILL rai 9E "EPL '.0D, C2:4TPULLC! W E ':f 4" LACED PE ' NP D]38, LOVER THAT j
'/AS URIGINAl LY Tr"'JED CH HRil:13115 WAS 4
RE-I:!STPLLED DN M S-l2'!1J3.
' ' '3
'W i.iD THSTaLLD EXISTI:'U !WITCll CDUER WIT 3 NEW su.
cI:"
':,. "]
"tEWS T!GHTEnED SMUC TICHf
,;i
- ,;0!76 )
/1 ;-W w;
':1.:.'; /,.1P :: OCRHED Dili LAnP PURHED DUT,'9EPLACEO LA.1P, t'ERITIED CPERATICH, PERURr:ED SI-400 AS FnT
. :;O5.
- N.. t :s e)..
'"rjt :;,indt,fai INSTALLED EEW PRINTER i INTERf ACE E'DARD.
PERfl:CIED PnI (TI-b80)
.;oN2 1 4
w
,L
.JJ:'t !!ICIH; rN FU FAILURE /PERTUtrED 3I-480, FDUND ED hl PRDBLEn WITH Tile Cl:ECX SDHDCE.
lI;101 2
,fi. :c. "\\.C: fTL" f3 FETUDED TRANSnITIER TD PLhCE MANIfDLO
" Dil'.';
BELCW TUE TRCHSt!1TTER AND PLACE TEC.
f.ELCH TilE MHIf 01.D. CLEAND itBIHG WITH CLASS A WATER (II-70). BLD LINES XMTR WITH '.TER L:0X, i:ACK FILLED WITH f:80K r
FILL P!21P (IMI-L13) RETURHED TD TERVICE, PCI!?DW::ED Pul.
.1:110 0
..? T HZ iHSTUiER TD FETULED TIAHinITTER 10 PLACE MANIfDLD is,
CELC!I (FE TRAH5N1TTE* PHD l' LACE TFE
/
iELC;l PIE SUN!iCLD. CLEN!ED TUVIFs WITH CLASS A MIEW (TI-70) PLED LINES AND X5TR WITH CATEN EUX, f:ACK FILLED WITH LACK FCLL Pun? (1n1-113) RETURHED TD
!EINICf.S. PERTURHED PflI.
I 12 ' !
m
& ', :t. IP R.nITTER 70 DDH'T !. AVE GDCD YEHTIWG/RETUBED M PP r : y TReHStitTTER, i:1HITULD iiHD SENSE LINES To FLAC'J THE MAHITDLD BELUW Tile TRAH!nITTER AHD THE iEE. CLEANED TU3ING, BACXfILLED TUCD:C rPD TPnNSi!ITTER PER IflI-118.
. '6 6 s
2-
.,1 SUI FDO'it uSE/ REPAIRED CDHTEDLLER FRCn CKT 133. FEPLACED RED LAF:P AND C4 CAPACITDR, PleCD CCHIRDLLER IN SPARE CDNTPDLLER.-___-__-_-_-____ - _____ _
c
. *.: 'i f d '..
C"NECTILE PCTI' !.
2 CAhT!lET 14N.
.Ji
,.'o TEM LIGHT :: CUT
- 14b
- I::G lNE E-t TICHTEN vtMP A0 rCMECICR,
+
LTH T3 ; '
"8ihG ID inCS
EA!RLED f?!1E LEHGTH
-~
if
'ER 10 ELECT. 'O C'jf/!9T Cille.. CHECl:ED JIII E1 FLACT rEE3) f0 'JLSIGN "ECUIRt."ENTS frR Cele ICI:"J diTACHED TC nLL :1WIWCCD "",T, LD T IN ';E?UICE JM
~
- FE C-i IICHTEil CLAMP AND CDHNECICP,
?:P, :. :.;
~1 'O : ELL hiti!G r> if.GS MEA!LRED CABLE LENGill OfER
~~
i:
~3 LL L ' T1 SUPPC?T CACLE. CliECKED WIIH
~.
- CR LL.J:X (EE:) ;G DESICil RED
- IREMENTS J
FOR C%tE !.ED:G nTTACHED 10 UALL.
PERFURMED PHT, llTT IN SERVICE
- 19376
. r.;.
.. ;;; p.qu.u; CAH T3 ':6LL CNE E-1 TI;HTENED CLAMP AND CDHHECTGR
~
.7 Ei
.S 10 IE L:'31!
PEASURED cal'LE 1FMGTH N") XTER TD ELECT. fu turPl!Hf CAPLE. C:!ECKED WITH MORN f; LOCK (EEU) - MO DESIGN RED. FCR CABLE :.EIWG AIT ACHED TD Hall., PERfCRHED P1T, LCri I;l ';E.WICE.
Te4
.2:
eN.CLn.F ";.t01:i; G A T3 TTCHTD'LD CALMP VD CCNNECTER r.EASurED
".Jr.v. ~ mnRS T3 CE CABLE LO:CTH TIMHSTER TD ELCT TD SUPPURT a.
O !!;! " W CALIE *:-13-87. CHECXED WITH HDRM 11ACK (EES) 10 DESIGN REQUIRER.ENT FOR Call'E
[.EIhG nfIndiCD TI5IALL CR StlPPDRI.
FErb";iED FNi, ATURNED 10 SERVICE.
2Nd
'/.
4 ':_.; KD%'
MEEN Ld? !:LE!Ui MD BdD CAPACITr#RDIOVED CCNil:ULLER AMD VEPLJct'D 9:ED! ifnP AND MLPLACED CSPACII"R C413 ALLCU 30 lHITPUT CH 400 AND FET!.'iHED FPf?ES ID CABIHET
, r?UND IECM REPLorED T!, PEEfDR?tED FT AND RETURHED t-2 JITC "C i;
!UITC:1 "! CCRUICf/REPLf>CED TS AMD FEEfC;"I9 fI f.HD RETUWED 10 SERVICE J4TM i
. ni-r' "WD DCPLtt:LE tu1TC:1 f.LIGHrENT/PDJUSTED AND ALIGNED P. b Usi.
. Ust SWITCH AI!EnftY FEC3tII: RATED PER SI-197 6up I?E'ENED TO SEFVICE 29 %3 e
~-
' 'iCL!LEII!Ji SMD ibE P0's.~4 lUPPLY HAD A DIFECTIVE ZEHER
.0 DTC0E '" II. TifE CIDDE Ed! REPLACED, THE Edi?UT '"iLitCE !9S CHECX:D, AHD IT '. ins
?E TLRFLD ill !ERUCCE. MF! 3 i<214743 i
l i
_-a
n m.,. fi ;
i'..' ?: E CHECT!t'E ACrial.
, 9 JA 'i -
c:.
J-v:Jr
' 4T > "iE RE:PliiE TESTING DHLYiINSTALED LIEt,R r"
DI!PLACENENT TRNH00CED CH VAltE FDR TE';T. CDNhECTED TEST LEA 0h TD LS-87-23 99 SPARE LIMIT 7 Ital. ':Fi:)NED TEST EWIIP,1EMI.
_,/ 0
- TE TETCT'E
!ESTIN; DNLY/Ibi3LLD Li;'Ef.1
- I Pl./.EE:1ENT TS:?SDUCER DH VNTE f D?
' E ST. CCNFECTEU ![!T LE@5 TJ LHT-21 l;
HD PARE LIMIT 521T01. PERF5eD 3.'L l
"E!PUESE Tide PEP MP 12183 ANO SI-1H, L
$tt'5UED LM SED TEST ;;IRt! TD LI;;If l-21I1CilLS.
.. O L N IETECT!!M [0 0.1D CHANNEL /PEPLACED CHANHEL 82 PREMP 373 1 ;
t:
o.,
4 il PUR M MEEIED ASSY. PERFDRMED rni SI-430
- '/.723 I
- o:
~
- N-
.,CH$ntt 11 CETECTCR "65 A CAD PHOTD-P.ULTIPLIER TUPE 8 LRGKEN MYLAR
. Grei::J WINDDW UiATLR DAMACE)/ REPLACED CHANNEL, 21 PM TUBE. PERFORMED SI-480 FDR PMT.
.;16723 1 4 U.'.VWE 15 IETECTC21185 A W'tTER Dat: AGE / REPLACED THE MYLAR WINODW 5
.1
- 11%C4 :!') CDNFECIDR AND IS REPLACED Tile H.V. CDNNECTCH PERfDRMED JN SI-480 FDR Piti.
- 16771 1
'1 i',.WIC1 ut Th;E FCUPD DUT DT HD F AILURE/PERfur'nED SI-685 STEP 5.4, i.4.LE FE1T%11:6 I s;8
. VERIFIED SDURCE CDJNT RATE IN TDLERANCE.
119227
S2
~
f:t n.CW
- '0 t M EEPLACE WB218327 IN SUPPDRT CF S1I-2-317-T4 nF.D J '. ELD 'JM: 40.1 SSTFL1EHT TD TC P7-420 INSTALLED 2 NEW 0-RINGS ON HEW
. idh 01 M Pt. 2 :
PICTAIL REMOVED PIGTAIL TRUM 2-LT-3-51-0 AND IH3IALLED NEW PIC TAIL MG 0 '
O.
..; C GFECu tl W.ui HDcMAL USE GREEN Lf.MP ILDWH AND CAPACITUR BAD / DETAIFEDIFARE CDNTRDLLER 1ND IH;TeLLED IN CIRCUIT 163 AND FUNCT.
TESTED CIRCUIf.
HSTf.LLED GREEN LAPP IN CDSTRELLER I333M7 mlIC:1 ilAS REMOVED FFF.M CIRCUIT 163. INSTALLED CAPACITDR C4 TD 6LLOW DVDLf5 UUT DN M0 DEGREE IWPUT. METURNED CDHIRDLLE!! TD SPARES CAPINET.
- I
- / e w
7 j; pI::IE ERGKCN LES DN CAP, LCDSERED CONHECTION EN FLE!1591TC11 C/SLE/ REPLACED EDTH CAPacIiGR$ DH St.CK Of FD'lR SUPPLY,
. RE!::L'E4 IE2illk'AL LUG DH FLOW SUITCH POL:R CA0LE, CLEAHED ROTC!!LTER, PERfCRMED SI-1>6 UERIFILD hD SPIKI!!G DH MONITOR. _ _ _
l CNJECTIVE JCIE!
'.Eri IN SfRMICE.
2527/1 '
- l: :1 91 ND CAFD/PERFCRHED BENC!l C"ECK CN CARD GIFD$ ER':ATIC GPEiHTInh IMSIALLED WEu %) CAM IM l:tLLS !!C' PERFCRHED M fK CAL. PtR SI-4S4 PK 2.
INITIATED maq y n7 4 !
~
E.
. "? ?
p.., ':&,c ; m::p;;
'l
'L: if WWpb 1EPLACE JD CRACKET AND CCR!u
'::'3.
.~ i: '! "f.'M '?
- i:J. f OIRTV/CLE3MED 50:!ITCR CA3IllET 7
^?)T23 i
, />: % CAL.c?M l', 9 'E"O "AS DUT CF OSLIBRATICM/ CALIF' RATED r.RD
"* i? :") THE
'l :LCitD ! C:1.fS P CACXrILLED CH HI SIDE SENSE LINES
'24
!? MER %E SETPGIHf :aS
. s..,
,1 npo$ 7 i
m.; qq. in, NIM DCES NOT FERFDRNED SI 205.2 Pni AND TSC PDINTS
."U !!
- d. 2 WERE FDUND TD DE IN TDLERANCE.
2 N 10 ?
- 1-
- ^1:& T,; PCINT DCE3 HIIT MD FAII.L'RE/PERTD9nED SI-205.2 PHT 3 TSC FOINTS PE9E FD@D 10 CE WITHIN TDLERAMCE l N 11
Afr.lfd LEfT I;! TERVICE
- vM mes,J-2:0. M ~ ;CLERANCE DUT Dr CALIBRATIUM/ RECALIBRATES P250
- r'i:'MITU' CarPu i! R.
- W8.
- s-01I;.;:0 '-1:-! 'uS MUT BKFCUF/ CHECKED I!C FDINT PER SI 205.2
') r e Uli i M 1:4 FDhKD r.00D LEff IN SERi> ICE
- Pol?
.M +)i5 r TIM!: 'm c:::DJIT FORML MEAR/REMDDVED SWITCH CDVER AND
-:' d!si'
- ^
IIcafE';ED CUHDUIT FITTINC PER n AND AI-d
- iE9 1.'.J.4.
'. d.TJ
@;m-sT-4:?n; L3;E; OjR.1AL LIE /TICHIENED CCHDUIT FIITINGS
!O L2TI i?R Si1!-:17 ~.1) 3:fD CDXCTED lm!!E LIHES
%q 7-N /. iq:E-UED ::ri ;catc.
' O!,TE'i..' E.
- ,33 ?
i i-W :012-;. "" - Ui '
'Hi" SAL COVE LCDSE DUE TD EDRMAL WEAR / TIGHTENED
'n G W." :
ZI T4 ruk9 ::1 L.T.
TRAMSitITTER CDVER.
, E:2'i.'
- M-0 % N 21. ": El OCC li l'XKFUpWiPERFDRMED SI-205.2 RETURHED TO
- !) '7 iM! :::iII:'R SERVICE j
,, ayr 3.
ag.. q:n ;;;4 r;7.LL!;' n3D PErFDEFID TEST MD CALIBRATIDH PER IMI l
4 TU E.CCT'"
O 2%.1 i
- -'c 9 a.
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Of $1-300, ANDASSISTING ENGINEEKS DETERMIEED t: LACK 00X NDT HECESSARY, ALARM SET POINTS TESTED AND ALL REQUIRED VOLTAGE HEASUREllfNTS MADE.
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. bb L i ' :r 'COH10 alf21 i:T CDULD N3T CET LD ALARM TD !!DRX, TP VERIf!ED PROPER OrERATIrN DN P250 CDrPUTER PTS dND AL6Ri13 (DHt27) PER II-2'Pi.2
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MF3 DUED'T CROKEN WIRE / REPAIRED f:RCKEN llIRE ON PJFV DlITCll
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M!ST AND DIRT /DPERATOR BLOCKED MDHITOR.
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.T TURytD PUMP Cff, REM'iVED ACCESS PANEL,
.:LEAHED r.UNITCR CAPIRET, TURNED PUMP DN, RETUWED MGHITOR TD SERVICE, PERf0RMED fMT AND HAD UPERATIURS TAKE MUNITOR DUT Of 31.ilft G yi i
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"! ' !EF ' 95.' "E ' i W 9 P ITER REGUIFEnERTS. PERFORMED TOROUING PER 1cnts-iAJT~. ii?J i APP.C THE CDUERS HERE REMDYED AND
- n'..L L TDRQUED. $11CCESSTUL TORQUE ilAS D0dE AND SATI!fIED PMT. TRANSMITTER WERE E.ACXfILLCD AND RETURNED TO SERUICE.
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RE93IREMEHIS PERfDRMED TORQUE - - _ _ _ _ _ _ - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ - - - - _ _ - _ - - _ - _ _ _ _ - _ _ _ - _ - _ _ - _ _ - - - _ _ _ _ _ _ _ _ - _ - - _ - - _ - _ _ - _ _
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/PP. L F;" RETUENED TO SERVICE.
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- M.: 1:E OU?i:4G it'HCTICMAL IEST PIGTAIL, REnUVED i]LD PIGTAIL FRCM 2-PDT-30-44 AND INST 6LLED NEU PIGTAIL Sl5EiC87011948
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..w.,gq;; c.:FET JEUSTURS ARE HDHE/ REMOVED MODULE AND SIGNAL CAf:LE W Ei' T""2 4 D 10LEl?AHCE.
CUVER. RESISTER IIA DATE 8342J, RH E D, 2440F. UHat:LE TO TELL TCLE2ANCE FRun EESISTDR. RETUi!NED TO SERVICE.
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' CED MAHUAL AND USING QA PAHTS.
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.a m NOT nJMCTICM CROSSED 'JIRES AT PANEL 2-L-10. LDCP
-. FE?FI'mC.i :]CT RETURMED TO AS FL"JHD CCNDITICH PR0f LEM TD EE CURRECTED CH WP i 12573 PER FCR 6817.
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.-H-YFM 02-in &331 COULD T;iE NCDIFIER WAS C'JT CF CALII:RATIDH HIGH lLL.;LD 1.!Cli'.ED TIERANCE THROUCWlui THE EHTIRE SCALE /THE TEnPEUAICRE n0DFIER WAS RECALIERATED WITH TM aCCEPTA!'LE TOLEldHCE AND RETurMr.D TO SERVICE.
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6 e.
h MAINTENANCE
SUMMARY
(MECHANICAL) l h
t I
l l
SUMMARY
OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS l
OCTOBER 1987 i
)
)
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l Major Capital Projects:
PN7101:
ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan (WP) 12223 is in progress pending safe access to current transformers.
PN7102:
ECN 5938 - Replace Feedwater Heaters 3 and 4 Preparation work is underway as time and manpower permits.
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.
This work will be moved out possibly into FY 1988.
PN7105:
ECM 5009 - Essential Raw Cooling Water (ERCW) Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of unit 1 isolation valves i's not scheduled to begin until later in the year. Some insulation activities remain incomplete and are being worked as resources permit.
PN7108:
ECN 6720 - Crane Consistency Program Unit 2 polar crane modification is complete.
Postmodification testing (PMT) by Electrical Maintenance is not complete.
Unit 1 polar crane work started on July 6, 1987 and is approximately 90 percent complete. Auxiliary Building crane WP 12596 is in the approval cycle.
Drawings have not been issued on the remaining cranes.
PN7115:
ECN 6719 Volumetric Intrusion Detection System ECN 6719 is still on hold.
Security is dissatisfied with system operation.
Security and Engineering Design have not concluded discussions on resolution.
Design is working on making the system functional.
PN7122:
DCR 1373 Secondary Side Steam Generator Preservation l
l 4
Major Capital Projects (cont.):
ECN 5657 - Installation of Moisture Separator Reheater (MSR)
Drain Valves Work is essentially complete on all the ECNs.
Some minor insulation installation activities are in progress as resources permit.
'PN7123:
ECNs 5938, 6305, 6571 - Replace Feedwater Heaters 1 and 2 Units 1 and 2 and Eroded Pipe Modifications Group B is supporting PMT on heaters 1 and 2 on both units as requested.
Insulation work on unit I continues.
PN7130: DCR 1156 - Post Accident Monitoring This work has slipped to allow work to continue on priority unit 2 restart efforts. NRC commitment on NUREG 1.97 calls for unit 1 completion by September 1987 and unit 2 by U2C4.
A request has been sent to the NRC to move the unit 1 completion date to U2C4.
PN7132:
DCR 2324 - Sewage Treatment Facility and Civil Upgrade This DCR has been cancelled. TVA has opted to tie in with the Soddy Daisy sewer system.
PN7'.36:
ECN 6259 - MSR Tube Bundle Replacement Complete except for PMT, inservice leak test, and final cleanup.
PN7152:
ECN 6808 - External Conduit Sealing Unit 2 work is complete.
Unit 1 workplan is available to work.
PN7159: Appendix R ECN 6300 - Additional Sprinklers and Draft Stops All fieldwork and testing are complete.
Procedures revisions are in progress. __ - __ ______
Major Capital Projects (cont.):
I ECN 6300 - Sensors and' Detectors All fieldwork is complete.
PN7161:
ECN 5855 - Replacement of Doors A56 and A57 Installation of door A56.was. completed, security of A56 to be worked later. Work on door A57 and interlocks will begin later.
l-New door hinges were installed on the active leaf of A57.
PN7181: DCR 1898 - ECNs 6832 and 6596 - Dry Active Waste Building Electrical interface is in progress.
Remaining items are resolved.
PN7199: Miscellaneous Activities Undor $100.000 This is for various work orders prepared for work under
$100,000 total site cost. This work is done as manpower resources are available that will not impact unit 2 restart effort.
1 1 -
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l Major Capital projects (cont.)
Significant Items:
j The following major significant items are under Operation and Maintenance Expense (0&M) and will continue to be until restart of i
unit 2.
1.
Fuse Program Work ECN 5880 - Incomplete work restrained by hold orders and work L
requests.
ECN 6854 - The workplan is complete.
Valve cycling test by j
' Operations has been rescheduled by hold orders and work i
requests.
2.
Main Steam Valve Vault (MSVV) Cable and Insulation Work SI-166-6 stroke tests are being performed by operations'in
)
accordance with the schedule, j
3.
Cable Ampacity program Unit 2 is complete.
Unit 1 is in progress.
4.
Raychem Cable Splicing Work - Unit 2 Work is complete; however, a 100 percent walkdown outside containment has been requested by DNE during reentry into 1
Mode 5.
Other Items:
ECN 5435 - Fire Doors The installation of weather stripping continues as resources permit.
ECN 5111 - Provide Permanent Power to Manholes 42-46 Electrical conduit and wiring installation for manholes 44-46 is complete according to WP 12262. Manholes 42 and 43 are being held for l
information from DNE on power cable routing and terminations.
FCR 4572R1 was sent to DNE and was logged in, but it was not sent to the responsible engineer. Manholes 42-46 will be worked by this FCR 4572RI. This item is not considered unit 2 startup by DNE and they will not authorize the engineer to do the necessary work to obtain pull cards or drawings for manholes 42-46.
FCR 4572R2 will be written to supersede 4572R1 for conduit and cable routing for manholes 42-46.
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,p fi Major Capital Proiects (cont.);
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Other Items (cont.):
ECN 55'03 - Fire Detection System O&PS Building f.h 4
Workplan 12482 is'in work.
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ECN 5599 - Conduit Supports for Fifth Vital Battery and Waste Disposal-l Area Workplan 12186 is being held for fifth vital battery area conduit supports.
Information is needed from DNE on support variances.
Initial installation of the 60th cell to the battery is to be'added to this workplan. All fieldwork is coniplete. Waiting on Instrument
(.
-Q Maintenance to run functions! before workplan can be closed.
?
)f m ECN 5609 - Air Compressors Makeup Water Treatment Plant
]
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Installation and checkout is'ccmplete. Modifications is s, waiting
' "j approval from DNE to install water drain valve on receivet tant.
The specified valve called for by DNE is not obtainable.
Modifications ba received approval to install water drain valve located by field, i
Additional isolation valves need to be'added on the water drain valve for installation and an additional valve should be added on the downstream side of air receiving tank for isolation of the air
/
i receiving tank which Design originally omitted. Fieldwork is complete.'/
j f
]
r ECN 5609 - Evacuation Alarm J
1 Workplan 12387 is in work and is 90 percent complete.
I ECN 5626 - Containment Ladders, Unit 1
/
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)
AworkplanisbeingwrittentoincorporatethisECN.fModif/ cations i
needs additional Design information'to complete. DNF neem to issue
)
all drawings listed on thit., ECN. Work has not bege bec ph of this 7"(\\L
,j holdup.
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ECN 5713 - Various Platforms in Lower Containment
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The installation of trollies on 9-1 is incomplete.
i
's X
1 ECN 5726 - CAQR SQP870478 - Reroute Sense Line Piping for Traine' i
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Separation to Panels 2-L-58 and 2-L-68 I
Fieldwork is complete.
In-service leak check will be performed during
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") J,ejor,Capitab Projects (cont.):
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H M 5831'- Ho't Shop Fire Detection
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i Workplsty2360 is 95 percoat complete.
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,e ECN 5935 - Correct Power Stock Lighting Deficiencies
',/
Workplan 12437 hr5 been apptored and is in work.
This is a noncestart
/
f'
'itet Variances need to be approved by DNE. Workplan 12275 is being written. Mod 1heations'needsFCRs5998and6128fromDNE.
[
ECV 6005 - Replacement ol' AFw Air Ejector
)
y Ih6Iorkpla'a is,c:6 nplets except for the leak checi 'o' be cone by t
CI430.1 in mo& 3.
N ECf/ 6057 r Cabi'e Ttay Covers Ib s aAcivity is in progress for the unit 2 restart.
ECN 63 1 < W?p for,2aric Acid Tank (BAT) t r'
Workblan is in the approval cycle.
ECN 6147 - Airlock Pecking Nut 7
Final testing of the airlocks En u Ut2 t'3.hahns/ incomplete (prior to mode 4/.
,/
i
)'
n ECN 6165 - Of'tsite Paging System i
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iona' t's cs of the remot'e mobile units remain to be completed.
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. SUN $19d-PressurizerHangersandValves
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PMT is incomplete and scheduled Nr startup for unit 1.
Remaining 1-4 nit C work. is scheduled for,U3, G'rhtsiding, cutage, y
E 6205 replacement of Instrument,'!aop Power Supply Fuses p..
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Unit 2 work is complete. Unit t1 wor'r and spares is incomplete.
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ECN 6380 - Replacement. of Bartor/ Pressure Transitte: s (l
F2diduork is corh;itte. 'f 'hdi closure awaiting instruction revision by f
Instrument Mainitaance.{
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! i, riajor Capital Projects (cont.):
j Other Items (cont.):
ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails for Security Equipment Workplan 12238 is being held for DNE approval of FCR showing installati n details. No new date for release of approved FCRs or s
drawivs by DNE has been established.
ECNs 6402 (Unit 17 and 6439 (Units 1 and 2) - Pressurizer Instrrv ntation Relocation Incervice tests will be performed when the system is brought up to tmperot.nre and pressuro.
EON 6437 - Replace FE-2-256, and 257 C
Unit 2 work is couplete.
Unit 1 lacks electrical work and calibration.
l EC) 6455 - Upgrade CU-3 Bor Battery Packs Workplan 12295 has been issued. Modifications are complete for 97 of 129 CU-3 boxes.
Mot k is presently on hold until locks are replaced on i
some of the renialcing boxes (WR 220403).
1 ECNs 6491 and 6534 - Eisential slaw Cooling Water (ERCW) Supports l
sul restart work is complete. A workplan to remove previously installed piping was approved and will be worked as resources permit.
ECN 650 - Install Put.iic Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from DNE.
ECN 6557 - Installation of CO2 Abort Switches.
Modifications is waiting resolution of design problems.
5:06 5601 - Estove.1 of Unit 1 Emergency Gas Treatment System (EGTS) i?M.tdraft D mpers PMT remains to be completed by the Engineering Test Section.
Fieldwork is complete.
ECN 6610 - Modify Air Return Fan Supports 11 nit I work is iv.onplete.. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ - _ _
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Major Capital Projects (cont. ):
j l
Other Items (cont.):
ECN 6631 - Modify Snubbers Documentation review is in progress for unit 2.
ECW 6689 -Relocation of Main Steam Power Operated Relief Valves (PORV)
-Instruction revision is in process.
ECW 6698 - Repull 120-Volt Cables Unit 2 is complete. Unit 1 is 90 percent complete and held by ECN 6742.
ECN 6706 14 Support Enhancement Repairs cdntinue on unit 1 as resources allow.
Initial inspections for unit 1 lack approximately three supports for completion.
Unit 1 evaluations are continuing. Documentation review of unit 2 work is in progress.
ECN 6715 - D/C Random Loads Both trains are complete. A technical specification change has been requested to close this workplan. The change has been approved by the NRC but has not yet been received by TVA.
ECN 6717 - Stub Bus Fuses Work is complete.
ECN 6739 - Alternate Analysis Unit I work has been started.
ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits The workplan is complete for unit 2.
Unit 1 is 50 percent complete.
Instrument Maintenance cannot support until 1988.
ECN 6761 - East Valve Room (EVR) Blowout panels Implementation of unit I work is progressing as resources are available. Work on a unit 2 EVR door is complete.
ECN 6784 - Documentation to Show Pipe Class Breaks Tho' resolution of Quality Assurance (QA) comments made during the review cycle is in progress.
l __________-_ __-__ _______-__
e e
Major Capital Projects (cont.):
Other Items (cont.):
ECN 68d2 - Modify EGTS Filter Housing Fieldwork is complete.
ECN 6808 - Conduit External Sealing Workplan 12363 has been PORC approved. We are awaiting vendor information.
ECN 6810 - Rework Category "C" Devices Complete except for functional test.
ECN 6815 - Installation Power Circuit Breaker Install 500-kV power circuit breaker and associated equipment for bay 1.
Retire 161-kV PCB and associated equipment. A total of eight workplans will be required. Workplan 12654 is ready for craft to work. Workplans 12739 and 12740 are being prepared.
ECN 6848 - Thermal Expansion Problems With Platforms Fieldwork is complete.
ECN 6866 - Modification of Valve Room Doors Fieldwerk is complete.
ECN 6871 - External Conduit Sealing DGB/CB/ERCW Physical work is complete.
Data sheet paporwork is being coordinated for closure by November 15, 1987.
ECN 7000 - Addition of Support to Main Steam Dump Header Fieldwork is complete except for final inspections during heatup.
ECN 7078 - Install Hangers - Main Steam Piping Complete except for final inspections during heatup.
ECW 7089 - ERCW Check Valve Replacement l
Hanger work is in progress.
ECN 7092 - Capping of Spare Sleeves in Unit 2 Shield Building
}
Fieldwork is complete.
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Major Capital Projects (cont.):
Other Items (cont.)
ECN 7110 - Relocate Auxiliary Feedwater Controllers Electrical work is complete. PMT remains.
ECN 7271 - Purge Air Supports Fieldwork is comp 1cte.
ECN 7272 - Auxiliary Feedwater Shields The workplan was completed.
ECN 7281 - Grout ERCW Hanger Fieldwork is complete.
Final closure is awaiting 28-day grout test.
ECN 7294 - ERCW Check Valves for Turbine Building Compressors The workplan was approved. Fieldwork awaiting receipt of material.
ECN 7297 - Auxiliary Air Compressor ERCW Relief Valves Work on "A" compressor is complete. Work on "B" compressor is scheduled later.
WR B226336 - Modify the maintenance portion of the Sandblast Shop.
DCN X00006A - Remove Hydrogen Analyzers Tubing The workplan lacks PMTs (SI-219).
DCN 2000188 - Install Needle Valve for Hydrogen Analyzers The workplan lacks PMTs (SI-219).
DCN 49 - Computer Room Air Conditioner The workplan continues in work.
DCN 58 - Penetration X94 and X95 Stiffeners j
I The workplan was completed.
DCN 73 - Installation of Microbiological Induced Corrosion (MIC) Boots A workplan was written, approved, and work started.
Completion is awaiting material delivery.
~
Major Capital' Projects (cont.):
Other Items (cont.):
DCN 80'- Flood Mode Spool Pieces A workplan was written and placed in the approval cycle.
Procedure Revisions Many manhours were spent revising procedures (M&AIs).
Control Room Bullet Resistivity - DCR 2268 - ECN 6860 Workplans 12602, 12603, 12604, and 12605 are in work. Approval is needed from DNE for FCR 6271.
Startup Activities List (SAL)
SAL Closupe - Many manhours were spent closing these items.
Appendir A - Internal Conduit Sealing Fieldwork is complete on WP 12272.
Instrumentation Verification program There have been 953 discrepancies issued to MODS to date with 476 not required for restart. All discrepancies required for restart have been completed, 334 nonrestart discrepancies are open.
DCN 4B - Fieldwork is complete.
DCN 7A - Fieldwork is complete.
DCN 9A - Fieldwork is complete.
ECN 7297 - Auxiliary Air Compressor - ERCW Relief Valves "A"
train is complete- "B" train is being held for outage.
DCN 14A - Fieldwork is complete.
DCN 36A - Fieldwork is complete.
ECN 7171 - Fieldwork is complete.
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Major Capital Projects (cont.):
Other Items'(cont.):
Lost Hanger Calculations ECN 7276 - One is incomplete. (Post M4 shakedown. )
ECN 7282 - One is incomplete.
ECN 7283 - One is incomplete--located in high radiation area.
ECN 7284 - Two are incomplete.
ECN 7290 - Three are incomplete.
ECN 7293 - Eighteen are incomplete.
ECN 7295 - Fourteen are incomplete.
ECN 7296 - Thirteen are incomplete.
ECN 7298 - Twenty-three are incomplete.
ECN 7299 - Ten are incomplete.
ECW 7300 - Fourteen are incomplete.
ECN 7302 - Twenty-one are incomplete.
ECN 7303 - Thirteen are incomplete.
ECN 7304 - Eighteen are incomplete.
ECN 7305 - Thirteen are incomplete.
l
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ECN 7307 - Thirteen are incomplete.
i ECN 7308 - Twenty-two are incomplete.
ECN 7311 - Twelve are incomplete.
Dry Active Waste Building ECN 6832 - WP 12473 - complete.
l WP 12449 - Requires energization of charged HVAC system for closure, j
WP 12477 - Requires installation of fire detector heads. _ _ - - - _ _ _ - _ - - _ _ _ _ _ _ _
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' Najor Capital Projects (Cont. ):
'Other Items (cont.):
WP 12478~- Complete.
WP 12612 - Panding manhole 78 closure to complete fire detector testing.
ECN 6596 - WP 12402 - Requires manhole 78 closure for fence completion.
WP 12377 - Complete, e-i e'd*
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0 M
Se THIS PAGE INTENTIONALLY LEFT BLANK e
a
l TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 November 13, 1987 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - OCTOBER 1987 Enclosed is the October 1987 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY
/f, f
^<J L. M. Nobles 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) i Director, Office of Inspection and Enforcement Nuclear Regulatory Commission
/
Washington, DC 20555 (10 copies)
\\
b Mr. T. Marston 5
N@
Electric Power Research Institute o
P. O. Box 10412 Palo Alto, California 94304 (1 copy) 99 4
INPO Records Center gcA l
Suite 1500 geyf 1100 Circle 75 Parkway Atlanta, Georgia 30339 (1 copy)
Mr. K. M. Jenison, Resident NRC Inspector O&PS-2, Sequoyah Nuclear Plant An Equal Opporturuty Employer