ML20212L131

Monthly Operating Repts for Oct 1986

ML20212L131
Person / Time
Site:	Sequoyah
Issue date:	10/31/1986
From:	Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8701290328
Download: ML20212L131 (47)

Text

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TENNESSEE VALLEY AUTilORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY ColmISSION a4 *

" OCTOBER 1986" UNIT 1 .-

DOCKET NUMBER 50-327 .,

LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by: - -

P. H. Wallace, Plant Manager 8701290328 861031 PDR ADOCK 05000327 R PDR t i l l b

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TABLE OF CONTENTS Page I. Operational Summary.

Performance Summary 1 Significant Operational Events ,, . 1 Fuel Performance and Spent Fuel Storage Capabilities -2 PORVs:and Safety Valves Summary 2 Licensee Events and Special Reports 2-4 Offsite Dose Calculation Manual Changes 4 II. Operating Statistics

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A. NRC Reports Unit One Statistics 5-7

. Unit Two Statistics 8-10 B. TVA Reports Nuclear Plant Operating Statistics 12 Unit Outage and-Availability 13-14 Reactor Histograms 15 III. Maintenance Summary Electrical Maintenance 16-17 Instrument Maintenance 18-22 Mechanical Maintenance 23-25 Modifications 26-35 IV. Environmental Qualification (EQ) Summary 36-42 e

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SUMMARY

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PERFORMANCE SUtWULRY October 1986 The following summary describes the significant operational activities for the month of 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, configuratiext control updating and resolution of significant employee concerns. Outage related maintenance and modifications are being performed. Unit I has been off-line 435 days. Unit 2 has been off-line 436 days.

SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 10/01/86 0001C The reactor was in mode 5. The administrative

-shutdown due to design control review, configuration 'I control updating and resolution of significant '

employee concerns continues.

10/31/86 2400C The reactor was in mode 5. The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.

Unit 2 Date Time Event 10/01/86 0001C The reactor was in mode 5. The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.

10/31/86 2400C The reactor was in mode 5. The administrative shutdown due to design control review, conCiguration control updating and resolution of significant employee concerns continues.

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a FUEL PERPORMANCE Unit 1 The core average fuel exposure accumulated during October was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.

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Unit 2 The core average fuel exposure accumulated during October was O MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.

SPENT FUEL PIT STORAGE CAPABILITIES '

The total storage capability in the spent fuel pit (SFP) is 1,386. However, there are five cell locations which are incapable of storing spent fuel.

Four locations (A10, All, A24, A25) are unavailable due to a suction strainer conflict, and one location (A16) is unavailable due to an instrumentation conflict. Presently, there is a total of 348 spent fuel bundles stored in the S,PP. Thus, the remaining storage capacity is 1,033. <

SPENT FUEL PIT INVENTORY

• A complete inventory via cassette tape of all 348 spent fuel bundles was performed on September 17 and 18, 1986. This inventory both resolved a discrepancy report and met a requirement in Plant Instruction TI-l to perform an inventory of fuel at least every twelve months. No discrepancies were observed.

NOTE: An inventory of new fuel in the new fuel storage vault was performed on August 5, 1986.

PORVs AND SAFETY VALVES SUIG4ARY No PORVs or safety valves were challenged in October 1986.

LICENSEE EVENT REPORT (S)

The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in October 1986.

LER Description of Event 1-86041 Two inadvertent diesel generator (D/G) starts occurred on September 14, 1986 and September 17, 1986, respectively. '

Item 1 - While replacing "KAZ" actuators on vital board IV, power was inadvertently removed from the logic relay panel for shutdown board 2B-B, causing a D/G start (1A-A, 2A-A, IB-B started). The occurrence was caused due to a procedure inadequacy resulting from a lack of instructions on marking up drawings in the main control room. After a modification on board IV, drawings were updated on unit 2 only; not both units. All electrical prints related to this event have been updated for both units.

. l LER DescriDtion of Event i

Item 1 - .- During this event, when 1B-B diesel generator was returned to (continued) normal, it tripped on high jacket water temperature. Essential raw cooling water is automatically supplied at a given setpoint, however, the supply was isolated to IB-B. Operations personnel failed to recognize.the flow path of raw water to this diesel.

Personnel involved were cautioned to ensure system lineup is ~

correct.

Item 2 - While attempting to replace "KAZ" fuses with " MIS" fuses, an inadvertent D/G start occurred when a jumper that was used to mala min guer to che . shutdown board came loose and blew the fuse to the adjacent circuit. The fuse was replaced and the i

D/Gs returned to service. Personnel were cautioned about working in confined areas.

i 1-86042 The following items pertain to Surveillance Requirement 4.0.5,Section XI Requirements which were determined on September 8, 1986.

j Item 1 - It was determined that SI-129, "Beergency Core Cooling Safet/  :

Injection Pump Operability," does not require the verification

of closing of the discharge check valve during testing if the -

RCS is less than 1700 psig as required by Surveillance Requirement (SR) 4.0.5. This test ensures that if one safety injection pump fails to start, flow will not be lost through the failed pump. However, this is performed when the RCS pressure is greater that 1700 psig. This procedural error was caused by interpretation of ASME XI Requirements and complexity of SR 4.0.5. The instruction will be revised to include this activity before startup.

Item 2 It was determined that thermocouples and resistance temperature detectors have not been calibrated as required by TS Definition 1.3 for channel calibration. Due to the fact that these items cannot be adjusted, a calibration was previously assumed to be

nonapplicable. The sensor is required to be calibrated with the rest of the channel, but it was not. Such sensors are used in systems such as the RCS, residual heat removal system, and monitoring of the pressurizer relief tank. A calibration

procedure will be implemented to verify these sensors.

i 1-86043 A review of SI-156, " Containment Integrated Leak Rate Test,"

determined that this SI was inadequate for leak testing of the ,

i containnent isolation valves FSV-30-134, -135 (Annulus '

Differential Pressure Isolation Valves) and valve 529 '

(Demineralized Water System) as required for SR 4.6.12. Venting is required for proper leak testing to ensure the backside will l be at atmospheric condition. All valves have been properly

, retested with required venting and zero (0) leakage was determined. SI-156 will be revised to reflect the correct l Venting procedure. The discovery of this event was

September 10, 1986.

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4 1-86044 It was determined on September 25, 1986, that SI-137.3,

" Measurement of The Controlled Leakage To The Reactor Coolant Pump Seals," did not adequately ensure that the seal injection flow rate during a loss of coolant was less than or equal to that which was assumed in the accident analysis as required for SR 4.4.6.2.1.C. This SR is to ensure that a flow of less than or equal to forty (40) gallons per minute is measured while the RCS is at 2235 1 20 psig and a pressure drop of greater than -

or equal to 100 pounds per square inch exists across the seal injection lines. SI-137.3 will be revised before startup to reflect SR 4.4.6.2.1.C.

1-86045 An emergency D/G sta'rt occurred at 0920 CDT, October 2, 1986, while performing modifications on a limitorque operator for ERCW normal supply valve (1-FCV-67-66) to lA-A diesel generator. As maintenance was being performed, a deenergized wire 7

inadvertently touched an energized part of the circuit. A review indicated a blown fuse contributed to the start. The Bussman " MIS-5" fuse is being investigated to determine its quality and reliability before startup of either unit. The D/Gs were returned to normal position. -

ABBREVIATIONS .

1. D/G - Diesel Generator

2. TS - Technical Specification

3. SR -

Surveillance Requirement

4. SI - Surveillance Instruction

5. RCS - Reactor Coolant System

6. KAZ - A fuse used as a safety device with an actuator

7. MIS - An MIS-5 fuse manufactured by Bussman j 8. ERCW - Essential Raw Cooling Water t

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SPECIAL REPORT (S)

There were no reports submitted to the NRC in October 1986.

OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah offsite dose calculation manual during the mo.4th.

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, OPERATING STATISTICS ~'

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OPERATING DATA REPORT

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DOCKET NO. 50-327 i DATE NOVEMBER 6,1986  ;

COMPLETED DY D.C.DUPREE l TELEPHONE (615)B70-6544 OPERATING STATUS

1. UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1 NOTES: ~

2. REPORT PERIOD: OCTOBER 1986

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 (CROSS MWE): 1183.0

7. MAXIMUM DEFENDASLE CAPACITY (NET MLE)

1145.0

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS

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3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:

9. PCWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):

10. REASONS FOR RESTRICTIONS, IF ANY:

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THIS MONTH YR.-TO-DATE CUMULATIVE-

11. HOURS IN REPORTING PERIOD 745.00 7296.00 46777.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 24444.91

, 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE O.00 0.00 23871.13

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00 l 10. NET ELECTRICAL ENERGY GENERATED (MWH) -3921.00 -32384.00 24910353.00

19. UNIT SERVICE FACTOR O.00 0.00 51.03

20. UNIT AVAILABILITY FACTOR O.00 0.00 51.03

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 46.39

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 46.39

, 23. UNIT FORCED OUTAGE RATE 100.00 100.00 34.60 1 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

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25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

• STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT

• EMPLOYEE CONCERNS. ,

l NOTE THAT THE THE YR.-TO-DATE AND

CUMULATIVE VALUES HAVE BEEN UPDATED.

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DOCKET NO. 50-327 i UNIT SHUTDOWNS AND POWER REPUCTIONS UNIT NAME sequoyah one DATE November 4, 1986 i ,

COMPLETED BY D. C. Dupree REPORT MONTH OCTOBER 1986 TELEPHONE (615)870-6544

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Scheduled A-Equipment Failure (Explain) 1-Manual . for Preparation of Data B-!!aintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)

! E-Operator Training & License Examination Outage i F-Ailministrative 5-Reduction l .6 G-Operational Error (Explain) 9-Other sExhibit I-Sade Source l II-Other.(Explain)

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l OPERATING DATA REPORT DOCKET NO. 50-328 DATE NOVEMBER 6,1986 COMPLETED BY D.C.DUPREE TELEPHONE (615)B70-6544 OPERATING STATUS

1. UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 2 NOTES:

REPORT PERIOD: OCTOBER 1986

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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 -

G. 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: '

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THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745.00 7296.00 38737.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.00 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) -4393.00 -51173.00 22580784.60

19. UNIT SERVICE FACTOR O.00 0.00 55.49

20. UNIT AVAILABILITY FACTOR 0.00 0.00 55.49

21. UNIT CAPACITY FACTOR (USING NDC NET) 0.00 0.00 30.78

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 50.78

23. UNIT FORCED OUTAGE RATE 100.00 100.00 36.50

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

l 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

i THE STARTUP OF UNIT-2 HAS BEEN SCHEDULED _ EOR _ MARC _H_1987.

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NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.

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E-Operator Training & License Examination Outage

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Tva nerA (DfdO80 NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant Period Hours 745 Month OCTOBER 19 86 I Item No. Unit No. UNIT ONE UNIT TWO PLANT 1 Averaae Hourly Gross Load. l<W 0 0 0 2 Maximum Hour Net Generation. MWh 0 0 0 3 Core Thermal Energy Gen. GWD (t)2 0 0 0 Steam Gen. Thermal Energy Gen., GWD (t)2 0 0 0 4

5 Gross Electrical Gen., MWh 0 0 0 8

5 6 Station Use, MWh 3,921 4,393 8,314 h 7 Net Electrical Gen., MWh -3,921 -4,393 -8,314

$ 8 Station Use, Percent N/A N/A N/A 9 Accum. Core Avg. Exposure, MWD / Ton! 0 0 0 10 CTEG This Month,106 BTU 0 0 0 11 SGTEG This Month,10 6 BTU 0 0 0 12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use, Hours-Miri. 0:00 0:00 _

0:00 15 Capacity Factor, Percent _

0.0 0.0 0.0 Turbine Avail. Factor. Percent 0.0 0.0 0.0 y 16 g 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 C 18 Turbocen. Avail. Factor. Percent 0.0 0.0 0.0

$* 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 u- 20 Unit Avail. Factor. Percent 0.0 0.0 0.0 21 Turbine Startuos 0 0 0 22 Reactor Cold Startuos 0 0 0 23 g 24 Gross Heat Rat?, Blu/kWh N/A N/A N/A

.E 25 Net Heat Rate, Btu /kWh N/A N/A N/A E 26 Y 27 g 28 Throttle Pressure, psig N/A N/A N/A

& 29 Throttle Temperature. *F N/A N/A N/A j 30 Exhaust Pressure, inHg Abs. N/A N/A N/A E 31 Intake Water Temp., F N/A N/A N/A F 32 33 Main Feedwater, M lb/hr N/A N/A N/A

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$ 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 N 39 Oil Fired for Generation, Gallons 2,904 5 40 Oil Heatina Value. Btu / Gal. 138,000 -

41 Dieul Generation. MWh 44 42 May. Hour Net Gen. Max. Day Net Gen- Load MWh Time Date MWh Date Factor, %

3 43 N/A N/A N/A N/A N/A N/A

$ Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.

j 2(t) indicates Thermal Energy.

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• UNIT OUTAGE AND AVAILABILITY

. e SEOUOYAlt Nuclear Plant Licensed Reactor Power 3.411 MW(tf Unit No. N Generator Rating 1220.5 MW(e) Month / Year OCTDf2R 198ft -

i Ocsign Gross Electrical Rating _ 1,183 _ MW Period Hours 745 METH F UNIT CORRECTIVE ACilON Time Unet Avaisable Teme Not Available Tinie Time SHUTTING STATUS TAKEN TO PREVEf4T OUTAGE CAUSE DURING T otal Gen. Not Used Turtune Gen. Reactor Unit Out in - DOWN REPETITION Day Mrs ! Min Hrs i Men Hes l Men Hrs [ Men Hrs l Min Hrs ! Men Hrs ! Men REACTOR OUTAGE Mrs l Men Hrs ! Men 1 00s00 00 l00 l 24e 00 24 *00 24 i OO 24 #00 i e DestRg Control. Confituratton N/A Mode 5 2 00500 00 i00 t 24 : 00 24 ;00 24 e00 24 !00  !  ! Updatine. and Employee Conc 1Ill8 3 00 ' 00 00 00 e 24 i 00 24 00 24 !00 24 ;00 l i 4 00 i OO 00 l00 ~

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18 00 ! OO 00 100 i 24 ! 00 24 i00 24 !OO 24 iOO i 19 00 : 00 00 800 1 24 i 00 24 I OO 24 iOG. 24 iO3  !  !

20 00 ; 00 00 !00  ! 24 ! 00 24 !00 24 800 l 24f00 I 4 21 00#00 00 j 00 l 24i00 24 #00 24 iOO 24 100 i e 22 00l00 00 #00 i 244 00 24 !OO 24 e00 24 l00 i i 23 00!00 00 000 1 24!OO 24i00 24 l00 24 500 8 8 24 00l00 00 !00 ' 24a 00 24 ! 00 24 iOO 24 iOO 8 25 00;00 00 100 t 24?00 24 '.00 24 !00 24 100 i ,

26 00 i OO 00 000 1 25 l 00 25 t 00 25 l00 25 400 . e i

27 00 t 00 00 !00 l 24800 24 e00 24 '00 24 !00 t I l 23 00 8 00 00 t 00 t 24!00 24 ! 00 24 #00 24 l00  !

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SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -

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. . . . ^ ~

SEQUOYAH TWO REACTOR HISTOGRAM 100 90 -

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G S.UMMARY OF MAINTENANCE ACTIVITIES .

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SUMMARY

(ELECTRICAL) -

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F?..C0F U PJT SYE CREEE. !4TE. . . . DEECRIPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTI2N. . . . . . . . . . . . . . . . . . . . . . .

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ms m J3125706 .1 MTU 313 0426 09/23/261-MTR-313-0426-LetfSPRO*3:1A FRESS FAN PULLEY WAS PAD CAUSING BEARIN35 TO VEAR.

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MTR MAKES UNUSUAL' NOISE FROM ITS CUT ERD. REPLACED " w" mIN

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MTR ERG- ENERGIZED FAN MOTOR AND RETURNED TO

. SERVICE. REFERENCE WR B-202909 FOR . . #-

' - Y ." Y REPLACEMENT OF FULLEY AND EELTS. WR 4 B-125706.~ ' ; ~a : .N. m T@, s B126068*1)GENBOB2 ;0001B 08/29/861-GENB-082-0001B-BsC*NFED*3sERRATIC LOAD LOAD GAIN AND STAPILITY POTENTIOMETER . b%

, CONTROL CHECK LOAD CONTROL CIRCUITS. ISB WAS OUT OF A2)USTMENT. ADJUSTED -

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%r DG GOVERNOR CONTROL POTENTIOMETER FOR FROFER LOAD EAIN. WR' A. ; ',

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B-126063. f i gy:..

y B126717 0 XS 013 0165A1B 11D 4/26 0-XS-013-0165A1P >P0TH DETECTORS ARE - REPLACED PAD SMOKE DETECTORS IN Z0hi 120 " C ' !

PICKUP AND WILL NOT CLEAR 1 121. R.* 3I-2I4.2 CN ZONE 120 1 121. ~

B12B246 1 GENP 082 00013 09/25/S61-GENE-052-0001B-B,CtNFRD*2,15-3 DIESEL THE I!ME DEAY REAY WAS OUT OF GENERATOR D/G 720.5 ADJUST / REPAIR TD9 ADJUSTMENT FROBAELY DUE TO AGE OR ;p.

'"e PELAY TO OPTAIN St! SEC00 0FERATION PER VIBRATION. ADJUETED TIME DELAY RELAY #9

-STEP 6.4.4 SI 102 E/SA. RELAY 0?ERATED TO BH-). SECONDS AND RETURNED TO .,

J 6.9 SECONDS DURINT THE 102 SERVICE. WR B-128246. eq e , , ~ y. s, IFERFORMANCE - M <

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T ' ~ON B12S247 1 GENB 092 0001B 09/25/26 1-EE,NF-082-0001B-B,C*NPRD*],D/G 1B-B THE TIME DELAY FELAY WAS GUT OF . .-

A , , TIME DELAY RELAY i9 ADJUST / REPLACE TES ADJUSTMENT FR0!AELY DUE TO AGE AND

~-

' RELAY TO OBTAIN ACCEPTANCE CRITERIA 0F VIERATICN. ADJUSTED TIME DELAY RELAT #8.. ,

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1 10t1 SECONDS FOR STEP 6.3.8.IN SIl02 TO 10H-) SECONDS AND RETURNED TO A ~

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• E/SA TIME RECORDED DURING TESTINS WAS SERVICE; WR P-12E247. 1p*\>\ ,

6.7 SECONDS

' E1324?S 2 GENB OS2 0002A 11/04/56 2-GENB-032-0002A-AsttNFED*],D/G 2A-A THE LOAD SENSOR CARD WAS REPLACED WITH .

• D

. . 'SI-26.' D/G 722. TROUBLE SHOOT CAUEE OF THE CARD FROM IB-B BUT DID NOT RESOLVE LOAD SWING DURING SI 26 PRGELEM. PLACED LDAD SENSOR CARDS EACK IN GRIGINAL POSITIONS. THE PROBLEM WAS ,

FOUND IN THE GOVERN 0R ACTUATOR. WORK REQUESTS WERE WRITTEN TO REMOVE ACTUATORS AND SHIP TO WOODWARD GOVERNOR 3 .L .. . .

COMPANY TO PE REBUILT.-

" ~B202103 1 GENB 092 . '00015 09/25/86 1-GENB-082-0001B-B,C*NPRD*]sD/G 1BB D/G THE FREDUENCY RESISTOR WAS DUT OF '

PLDG. 1B-B D/G STARTED FROM SI TEST ADJUSTMENT. ADJUSTED THE FREQUENCY SIMAL FCR SI-7 D/G VOLTAGE AND FRED RESISTOR TO CSTAIN 60 H2. L'E 3-202:03.

"; ha Ab* f .J

. . .WERE WITHIN LIMITS BUT D/G FRED 'L

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STAPLIZED AT 59.6'HZ. IT SH0'JLD HAVE - '.- '

STA5LIZED AT 60HZ. INVEST AND REFAIR NOTE: AFTER 8660R WAS RESET FRES CAME UP TO 60 HZ P202190 2 MIRP 026 0009 !!/04/26 2-MTRP-026-0009A-A,THE FUMP WI :. 50i DI:TY CONTACTS. FINGER CONTACTS WERE NOT STOP FROM THE CONTROL SWITC; '" CONTROL ENGASED FRCPERLY. CLEANED CONTROL AND ROOM AUXILI M Y CS TACTS AND READ ONM VALUE OF W* r TRIP CGIL.

-E2024?? 2 RE 090 0100A 11/04/S6 2-RE-0?0-0100A sSHIELD PLDG EXHAUST MOTOR DRIVEN PUMP UAS LOCKED UP. AFTER MCNITOR AUX 749 REPLACE NO.1 VACUUM PUMP PEING REEET REFEATEDLY, MOTCR WINDINGS MOTOR. IT IS PURNED UP. PURNED. REPLACED MOTOR AND OVERL0AD

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ELECTRICA'. :!AINTENANCE MCNTHLY EUMRARY 11-04-86 FAGE 2 CONP : ,

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'GR.CCI U FUNC SYS ADDRESS . DATE. . . . EESCRIPTI0N. . . . . . . . . . . . . . . . . . . .;. .

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, , a:-C . , ,rs,;;;9 HEATERS. TERMINATED WIRES PER MI1AI-7. 'N

B20:592 0 XFD 313 , 0907 11/04/86 0-XFD-313-0907 ,DAPIER HAS CLO3ED  ;.ETL LINK ON FIRE DAFJER WAS PAD.

{ * -

). ' BLOCKING OFF VENTILATION ' 7' - a

'4

, . INSTALLED NEW ETL LINK ON FIRE DAMPER , _ 4$

e',; # .USING MI-6.20 AND M1AI-7. * -

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" B202789 4 ZS 061'0122 1 10/31/86 2-25-031-0i22' 1-Br[tNPRD*],VLVWIli.' THE STRIKER PLATE ON THE VALVE STEM WAS NOT STAY GPEN OUT OF ADJJSTMENT PREVENTING THE '

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'!-t l$204231 1 FATB 082- 'UC 10/02/861-BATB-082-UC-Br[*hPRD*JsCELL I43 DID ' LBATTERY CELL POSTS WER NOT PASS SI 23S STEP 6.1.1 PAGE 2 CONNECT!ON RESISTANCE TO READ HIGH. - -

4- ".5 CLEANED PATTERY CELLS USING MI-10.54 AND [>U 3.,

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REPLACED THE Z-BAR BETWEEN CELL I42 AND g

43. WR BV-204231. - >"

B205529 2 BCTD 067 0091 11/N/96 2-PCTD-067-00?1-A,EtNPRIt],FUEE FLOWS AS ELECTRICAL CIRCUIT ON RELAY A181 UAS S00N AS IT IS INSTALLED PAD. REPLACED RELAY A181 ON ANNUNCIATOR M" -

.m CIRCUIT MONITOR. OPERATIONS REPLACED ."

L 1/16 FUSE AND RETURNED TO SERVICE. WR

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l INSTRUMENT MAINTENANCE MoWTHLY REPORT FOR OCTOBER 1986 COMMON 1

1. Work Request (WR) B202885 was initiated by the Operations Section to.

investigate a higher than normal indication on the Auxiliary Building.

Exhaust Stack Flow Monitor (Loop 0-F-30-174). Flow transmitter

.0-FT-30-5174A was found out of desired tolerance and recalibrated.

~

e PRO 1-86-275 was initiated to evaluate the condition.

2. WR 12107 was approved to replace the condensate Demineralizer Regenerant Effluent Composite Sample Flow Monitor 0-FI-14-466. This replacement is '

being performed in accordance with ECN L6737 (D-FCR-4541RI) and is part of corrective action for PkO 1-86-104.

3. Received on site the special calibration test equipment for the Static-O-Ring (SOR) differential pressure switches used in the UHI system. These calibrator units were purchased from SOR to calibrate the switches, compensating for the system pressure static shift. This static pressure shift problem was identified to SQN in NRC-IE Notice -

86-02 and procurement of the special calibrator units is the corrective action being taken_in response to this NRC notice. Both of the calibrator units purchased were defective from the factory (i.e., they experienced internal pressure leakage) and steps are being taken to .

remedy this problem. The UHI switches will be recalibrated using these special calibration units. This is required for startup.

4. Discovered that the Measuring and Test Equipment (M&TE) used in SI-125 (Calibration of Seismic Monitors) had never been included in a

. calibration certification program. PRO l-86-295 was initiated to 4

evaluate this condition. Steps have now been initiated to include the calibration of the M&TE on a regular schedule at the TVA Central Lab.

t

, 5. Completed revisions to SI-98.1 (Functional Test of the Auto Stop Oil for

! Turbine Trips), SI-695 (Calibration Procedure for Auxiliary Building Steam Line Isolation Temperature Switches), and SI-706 (Vital i

Instrumentation Sense Line Insulation Inspection Procedure), which were all required for unit 2 startup. The SI-l checklist was completed and submitted on these procedures.

6. 'Responsed to Operating Experience Review WBN-NCR-6750s concerning l problems with the Isokinetic Sampling Systems at Watts Bar Nuclear Plant supplied by Air Monitor Corporation. The two problems identified on the experience review were in regard to

(1) lack of QA requirements being specified on the contract to meet the requirements of Reg. Guide 1.97 ,

and (2) failure of vendor to provide an Operation and Maintenance Manual '

showing the latest configuration of the instrumentation, and failure to l provide equipment upgrades to maintain system operation. Our response noted that the applicability of item (1) to SQN is indeterminate until ,

the SQN Reg. Guide 1.97 review is complete. For item (2) our response indicated that similar problems do exist at SQN and recommendations were made for SQN Division of Nuclear Engineering (DNE) to coordinate with Air Monitor Corporation in determining what system upgrades are needed and to obtain an updated vendor manual.

O-INSTRUMENT MAINTENANCE MONTHLY REPORT POR OCTOBER 1986 COPMON (continued)

, 7. Responded to five PROS on various compliance instruments on both units 1 and 2. The PROS were initially categorized as Not Reportable by the PORS engineer. The PRO numbers are 2-86-096, 1-86-264, 1-86-270, 1-86-271, 2-86-105. -

8. Received final copy of Westinghouse setpoint methodology report (WCAP 11239R2). This report documents adequacy of reactor trip and engineered safety features-instrumentation setpoints. The report will be reviewed by a special subconnittee and submitted to PORC for official issuance.

UNIT 2

1. A unit 2 containment vent isolation occurred because of spurious high radiation signal spikes from radiation monitor 2-RM-90-106B.

PRO 2-86-098 was initiated to evalute the condition. Investigation revealed that the probable cause for the erroneous high radiation spikes

• was electrical nois,e from welding machines being used inside containment. .-

2. In continuation from unit 2, item 2 in the September 1986 Monthly .

Report, the WRs for rotating four steam generator level transmitters (2-LT-3-43, 56, 94, 107) were approved and worked. The transmitters were rotated and recalibrated to satisfy SCR-8620Rl. Quality Information Release (QIR) No. SQN86173 was submitted to close this open item in EQ Binder SQNEQ-XMTR-001.

3. WR B202076 was initiated by the Operations Section to investigate erroneous readings on unit 2 shield building stack flow monitor (loop 2-F-30-242). Flow transmitter 2-FT-30-5242A sense lines were purged and transmitter was recalibrated. PRO 2-86-100 was initiated to evalute the condition.

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MAINTENANCE

SUMMARY

(MECHANICAL) 4 e

9 l

MECHANICAL. MAINTENANCE MONTHLY REPORT FOR OCTOBER 1986 COpm0N

1. Continued hanger bolt tightening program. To date approximately 700 of 1,050 hangers are complete.

2. Completed damper repairs for successful completion of SI-149. '

3. Disassembled and began repairs on "B" waste gas compressor.

4. Disassembled ERCW piping for inspection for signs of microbiologically-induced corrosion (MIC). Found evidence of MIC on a 6-inch line, 1-1/2-inch line, and 2-inch line.

5. Put together plan for six year preventive maintenance on the diesel generators. This involved revising two maintenance instructions and preparation of a workplan. Additionally, arrangements were made for diesel mechanics from Watts Bar Nuclear Plant and Browns Ferry Nuclear Plant, as well engineering support from Bellefonte Nuclear Plant.

6. Initiated work reqyests for 143 diaphragm valves to replace diaphrages  ;

for preventive maintenance.

7. Completed annual preventive overhaul of "A" control air compressor.

UNIT 1

1. Completed unit 1 main steam safety valve ring setting adjustment.

2. Continued repairs to unit 1 main generator.

3. Repaired and successfully MOVATS-tested 1-FCV-63-40.

4. Began repairs to pipe supports in 1C condenser.

UNIT 2

1. Disassembled 61-745 valve for Glycol Outage.

2. Initiated work requests for 143 diaphragm valves to replace diaphrages for preventive maintenance.

3. Replaced scored valve stem in 2-FCV-63-172.

OTHER

1. Completed Employee Concern Task Group Report Corrective Action Plans on four reports.

2. Participated in the periodic INPO evaluation of maintenance activities.

1

~

~

. MIC4CICfd. MAINIDIAllCE IDITit.Y SIWARY 11-04-36 PPCE ' 1 - . - - _

+ OtP nR. NIST U . FURC SYS ADDRESS. C ATE. .. . DESCRIPTION. . . . . . . . . . . . . . . . . . .. . . . . . . . CDGECTIVE ACTIDN. . . . . . . . . . . . . . . . . . . .

b10% 3 i PC0 045 0000 03/30/241-PCD-045-0080 ,DHPRDw3, AIR OPER WDRH IEITIDNER DUC TD HORMAL D?ERATIGH.

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, POSITIDH SU2VEILLANCE INSTRUCTIU;I 188 AND ,

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Y-f 0124980 1 VLV 070 IS LErdIRC CCHTALiATED XATER AT A .

STEADY RATE 6; ,

D12H'10 1 VLV 070 0583 0'f/04/361-VLV-070-0533-A,DNPR0nMD.*UST ULV HDEMAL REAR OF PACKING. IHSTALLED FEU

<.a;. -.s.,m, STEM PACKIEC TO PREVEhi LEAK Off PACKLiC, CHECKED FOR LEAKS AND RETURNED ' -

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' ' ' ~~

. ' HOISE. FAR HEEDS PEPAIR

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6 5

• e e MAINTENANCE

SUMMARY

(MODIFICATIONS) .,

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e

SUMMARY

OF WORK COMPLETED MODIFICATIONS OCTOBER 1986 ~

APPENDIX R ECN 5435 - Fire Doors The installation of weatherstripping continues as resources permit.

ECN 6300 - Additional Sprinklers and Draft Stops The draft stop workplan is in work, and the sprinkler workplan is in the approval cycle. Questions concerning the design have been **

raised by Operations. Applicable representatives are working to -;

resolve the problem. A workplan for the electrical portion is in the approval cycle. .

~

ECN 6311 - Operator Extension on PORY This work has been completed except for final cycling at startup.

OTHER ITEMS ECNs 2783 and 5202 - Installation of Fifth Diesel Installation of the fifth diesel generator has been deferred indefinitely.

ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of unit 1 isolation valves was approved. Some insulation activities remain incomplete.

ECNs 5034 and 5743 - Various Platforms in Lower Containment Because of new weld inspection requirements, Modifications Group B ,

is waiting on DNE to furnish inspection requirements on tack welds to hold down grating.

ECN 5111 - Remove Power From Old Carpenter Shop at Dry Active Waste ,

Building Modifications Group C is holding the completion of this ECN until the completion of the Dry Active Waste Building. Power is needed for construction power.

ECN 5111 - Provide permanent power to manholes 42, 43, 44, 45, and

46. Workplan 12262 being revised to include manhole 43 and will be issued for approval. , ,

ECN 5599 - Conduit Supports for Fifth Vital Battery and Waste Disposal Area Workplan 12186 in approval cycle for fifth vital battery area.

Workplan for waste disposal area held for issue of ECN by DNE to include FCR 4753. .. .

ECN 5609 - Air Compressors Makeup Water Treatment Plant Ale compressors and mechanical piping complete except for tie-in to headers which is held for issue of electrical drawings.

ECN 5609 - As-Construct Makeup Water Treatment Plant Drawings per SQ-DR-86-03-61R .

Held for release of five remaining drawings from DNE. .

ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete.

ECN 5703 - Reinforcement of Block Walls Unit 1 is incomplete.

ECN 5713 - Various Platforms in Lower Containment The first trolley was modified by the vendor. Additional onsite testing is required. The remaining trollies are being prepared for shipment to the vendor for modification. Work will continue when the trollies are returned.

/

ECN 5724 - CVCS/RHR Supports One hanger and one notification of indication remains incomplete for unit 1. Work is in progress.

ECN 5880 - UNID Tags for Class 1E Fuses ,

Field verification of Class 1E fuses and penetration cable protection is approxmately 85 percent complete. DNE to issue fuse ,

listing and drawings before remainder of the work completed.

ECN 5935 - Correct Power Block Lighting Deficiencies Workplan initiation held for release of drawings by DNE.

ECNs 5938. 6305, and 6571 - Replace Feedwater Hester and Eroded Pipe Modifications Group B is supporting postmodification testing (PMT) on heaters 1 and 2 on both units as requested. Insulation work on ~

unit I continues. Installation of the monorail on unit 2 continues in preparation for the changeout of feedwater heaters 3 and 4.

Structural steel reinforcement has begun on unit I heaters 3 and 4.

ECN 6014 - Replacement of ERCW Pump Bearing Piping The workplan was written, approved, and work has begud.

ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced. The extent of cable tray cover requirements are being reevaluated by DNE. ~

ECN 6147 - Airlock Packing Not Final testing of the airlocks on unit 2 remains incomplete (prior to mode 4).

ECN 6185 - Offsite Paging System Functional tests of the remote mobile units remain to be completed.

ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete and scheduled for startup.

ECN 6204 - Electrical Penetration Overcurrent Protection

_ Fuse replacement and fuse block installation are complete.

Modifications Group A is waiting for a technical specification change to place the circuits in operation.

ECN 6237 - Modify Snubbers Work is continuing for unit 2.

ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement Cleanup and reinsulation is continuing.

ECN 6380 - Replacement of Barton Pressure Transmitters .

Unit 2 installation is 98 percent complete.

ECN 6357 - ERCW Roof Access and Rails for Security Equipment Workplan 12238 held for DNE approval of FCR showing installation details.

i ECM 6388 - 500-kVA Switchyard Current Transformer Heaters Two heaters completed on workplan 12005. Workplan 12223 for five '

remaining heaters in approval cycle.

ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation All work is complete. In-service tests will be performed when the system is brought up to temperature and pressure.

ECN 6459 - Upgrade CU-3 Box Battery Packs Workplan being written to perform work.

ECN 6459 - Declassify Certain Class 1E Equipment Work is complete.

i -  :

ECNs 6491 and 6534 - ERCW Supports All hangers for unit 2 (ECM 6534) have been completed. Six hangers remain for unit 1. Drawings are still to be issued for drawing-change-only workplan (ECN 6534).

ECW 6543 - Install Public Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from DNE.

t ECN 6556 - Replace Solenoid Hangers Work is in progress.

ECN 6599 - Unit 2 Shield Building Anchor Problem I

Fieldwork is complete and documentation is in progress.

ECN 6601 - Removal of EGTS Backdraft Dampers

! PMT remains to be completed by the Engineering Test Section.

ECN 6610 - Modify Air Return Fan Supports ,

I Unit I work is incomplete.

I ECNs 6631 and 6683 - Snubber Replacements / Modifications

! Fieldwork for unit 2 is complete.

i i ECN 6636 - Replace Cable in Valve Room Cable and conduit are complete. Functional test of the last valve is being held until the FCR approving the configuration change is complete.

ECN 6667 - Delete Torque Switch MOVs

. Work is complete.

ECN 6687 - Additional Office and Medical Facility Modification to medical facilities in process. Fencing along railroad area and west side held for installation of the South Central Bell environmental unit.

ECN 6687 - South Central Bell Environmental Unit Workplan 12251 in work. Excavation complete. Conduit installation in process.

ECN 6689 - Relocation of Mainsteam PORV .

Reworking conduit.and cable in process due to design errors. .:

Relocation of controls is expected shortly. Unit 1 conduit is in progress. .

ECN 6698 - Repull 120-Volt Cables All cables have been pulled. Workplan on terminations must be written.

ECN 6700 - Concrete Edge Distance Hangers -

Fieldwork was completed.

ECN 6701 - Modify Foxboro Recorder Latches i Fieldwork is continuing. Completion delayed due to material which is on order.

ECN 6702 - Upgrade of ERCW Valves Workplan written and approved. Awaiting valve tags for completion.

ECN 6706 14 Support Enhancement ,

Fleidwork continues on both units. Initial inspections for units 1 and 2 are complete. There are 19 unit 2 supports that lack field modifications and are in work. Unit i evaluations are continuing. ,

ECN 6707 - Replace System 74 Flow Switches Workplan is ready for work. Work will start upon receipt of mounting screws.

ECN 6710 - Diesel Generator and SIS Supports Fieldwork is complete.

r w

ECN 6712 - Turbine-Driven Auxiliary Feedwater Room DC Exhaust Fan Work is complete. ,

ECN 6715 - D/C Random Loads Workplan in approval cycle.

ECN 6717 - Stub Bus Fuses Workplan is in approval cycle.

RCN 6719 - Volumetric Intrustion Detection Systems Workplan 12186 in work for civil and architectucal features.

Excavation is 75 percent complete and gravel installation is 50

~

percent complete. Fence posts installation is in process.

~ -;

ECN 6739 - Alternate Analysis Work is in progress. There were 155 supports out of 228 on unit 2 completed. Approximately 50 additional support modifications are expected.

ECN 6747 - Install Fuses in Radiation Monitor Power Supply Circuits Workplan is in approval cycle.

ECN 6746 - Install Fuses Workplan is in approval cycle.

ECN 6749 - Replacement of Bussman KAZ Replacement with MIS-5 has begun.

ECN 6752 - Modification of P.D. (Anchor Problems)

Work is continuing.

ECN 6754 - Penetration Supports ,

Work is completed.

ECN 6758 - HVAC Supports ,

Unit I workplan was approved, work was started, and work is continuing ECN 6761 - EVR Blowout Panels Workplan was approved and work started.

ECN 6769 - Auxiliary Air Compressor Traps Workplan was written and placed in the approval cycle.

k ECN 6770 - Water Spray Workplan was approved and work is in progress. '

_ECN 6781 Hanger Pipe Clamps Workplan was approved and work is in progress. l ECN 6783 - Eoplace Motor on 2-MOV-70-87 Workplan is being written.

ECN 6785 - Install Tee Drains Workplan is in the approval cycle.

ECN 6787 - Inspection and Replacement of Solenoid Valve Supports "

A workplan was prepared, approved, and placed in work.

I ECN 6190 - Medium Energy Pipe Break Workplan continues in approval cycle.

ECN 6805 - Replacement of Filters in Control Building and Auxiliary Building Gas Treatment System Workplan was written, approved, and worked.

Dry Active Waste Building (DCR 1898)

The roofing work is complete. Some roofing panels will require removal for crane access to align the compactor. Work continues on the trim, dock levelers, and metal doors. Remaining work on inside wall and mechanical features held for drawings and material. In addition, no interfaco drawings have been released.

Storage Building at Power Operations Training Center Building erection complete. Work in process for HVAC system. Fire protection piping held for design by POTC and material receipt. ,

ADP Additional Lights to Parking tot No. 2 (DCR 2260)

Workplan 12208 written, but held for design drawings. ,

Material Traceability Project Support was provided as requested.

Procedure Revisions Many manhours were spent revising procedures (MLAI's).

Rework Hut 23 for Office Complex Insulation material received for walls is being installed. DNE

~

material contract not issued to PA, and three contracts not awarded.

Control Room Bullet Resistivity - DCR 2268 Workplan initiation held for issue of ECN and drawings.

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MODIFICATIONS ECW DCR SYS UNIT DESCRIPTION L5607 D1195 410 0 Replace existing pushbutton electrically operated controls for overhead doors listed with units incorporating constant ~

pressure switches for down control.

L6161 F2406 090 2 -Modify the RP-30 modules on the noble gas and air particulate radiation monitoring channels to operate with an upper-level discriminator set below maximum preamplifier pulse.

L6305 D2133 400 0 Install one hour fire barrier wall in the Auxiliary Building along the A-8 line on elevation 714 from Q line to a point 20 feet east of Q line from floor to ceiling.

L6642 D2133 026, Add fire detection and suppression to the 1

Reactor Building annulus to protect electrical conduit. .

L6718 D2266 043 2 Cross tie containment air sample line with chemical analysis panel off gas sample line.

L6725 F4405 067 2 Reroute 1-1/2-inch stainless steel ERCW pipe around conduit interference.

Correct drawings to show actual as-built "

pipe size on ERCW penetration room Coolers.

L6727 F4526 410 1 Install high radiation swing gates in doorway of all polar crane wall door in each unit (4 per unit). This is a regulatory requirement.

L6741 F4557 317 2 Remove unreinforced masonry block walls around hot sample room chillers and reflect on drawing. Also remove unnecessary restraints.

L6744 F4561 363 1 Request DNE evaluation of the variances - '

identified in NSRS survey of supports in

• MOV board rooms.

L6748 F4407 002 1 -

Revise drawings to show current plant configuration for the chemical addition injection points to the condensate system.

4 ECN DCR SYS UNIT DESCRIPTION L6755 D2257 000 1 Revise and reissue anchor design drawings and isometric piping. Calculation of sum of alternate criteria or deadweight supported piping and rigorous loads.

L6584 D2212 001 1 Remove the torque switch from the opening

• circuit and bypass the closing torque switch with a closing ihmit switch.

Closing Itait switch set at 97-percent to 98 percent of travel.

L6754 D2259 000 2 Evaluate and modify as needed 3/8-inch diameter sampling tubing penetrating the steel containment vessel and associated supports.

L6801 F4482 001 2 Drawing No. 47W801-1 (detail A1) and Drawing No. 47W400-2 (detail B2) call for 1/4-inch orifice in both units in all *

, locations. In accordance with ECN 3005 .;

and original design, the correct configuration is 1/4-inch orifice for ,

class P piping. .

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i I

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6 e

k. h ENVIRONMENTAL QUALIFICATION (E.Q.)

SUMMARY

I e

t

• 1 9

Date: 11/3/86 0041E

• 8 Estimated

• Date of Camletion_

SCR No. Description ECN Encineer Workplan No. U-1 U-2 Consents EQP 8501 Disconnect I- and 2-HS-62-61 6524 Peters 11901 C C U-2 QIR submitted.

EQP 8502 Replace penetrations 23 and 48 6490 Peters 11801, 11802, C C Complete QIR submitted.

11810, 11811 EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Complete field verification sheets are in binder. No QIR needed.

t EQP 8504 Splice methods not correct N/A Stockton 80 Nts C C Conplete QIR submitted.

EQP 8505 Drawing N/A N/A N/A N/A N/A

. EQP 8506 Seal containment isolation 6514 Kitasey 11880 C C valve EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C EQP 8508 JB weepholes (press) 6523 Alas 11898 C C Couplete QIR submitted.

EQP 8500R2 38 weepholes 6709 Alas EQP 8509RI Conduit seals 6529 Kimsey 11903, 11904 C C EQP 8509R2 Conduit seals 6615 N/A N/A N/A No fieldwork remaining.

EQP 8510 Disconnect local handswitches 6527 Peters 11901 C C ,

EQP 8511 Submerged JB inside 6549 Peters 11901 C N/A containment j

. . 8'

e Dat;: 11/3/96 0041E d

Estimated

- Date of Concletion SCR No. Description ECN Engineer WorkDlan No. U-1 U-2 Ctmments EQP 8512R2 Rewire JB N/A Asburn 11855, 11856 C C All boxes rewired.

EQP 8513 Weep holes (moisture) 6547 Alas 11898 C C Complete QIR sutaitted.

EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C C Couplete Q1R submitted.

EQP 8514 Motor insulation 74-1, -2 6540 Branham 11906 N/A C Complete QIR submitted.

EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C C EQP 8516 Replace 2-LT-3-114 N/A Instrument N/A N/A C 4

- Maint.

EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C i

l EQP 8518 Submerged cables 6533 Various/6 various C C EQP 8519 Tee drains N/A Electrical N/A C C Canplete QIR submitted.

Maint.

EQP 8520 Expired cables 6553 Gonzalez 11902 C C EQP 8521 Delete 18 and rework splices 6550 Stockton 11914, 11915 C C EQP 8521R1 Delete TB and rework splices 6551 EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C EQP 8522R2 Rewire local panels N/A Instrument 12016 C C Maint.

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.* -8 1

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Dat3: 11/3/06 0041E

• Estimated

• Date of Concletion SCR No. Description ECN Engineer nbrkplan No. U-1 U-2 Comments EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C and misplaced brackets EQP 8524 Change setpoints 6551 Instrument 11916 C C Point.

EQP 8525 Reterminate hydrogen N/A Electrical N/A C C Completed by Electrical Maint.

reconbiner (PWI) Maint. .

EQP 8526 Replace FSVs, U-1 1. U-2 11 6552 Mechanical 11897 C C Mods.

EQP 8527 Coat T8, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C (MR)

, i y EQP 8528 Solder strain gauge Barton IMI Instrument N/A C C QIR sutaitted 1/24.

' transmitters Maint.

EQP H529 PD1-30-42, -43 6554 Legg 11912 C C EQP 8530 Gasket, Namco L/S N/A Electrical N/A C C (MR) Maint.

3 EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C EQP 8532 Delete L/S 1 , 2-43-201, 6630 Alas N/A N/A No longer an issue.

-202, -207, and -208 EQP 8533 Delete dual voltage splice N/A Rutledge 11866, 11853 C C 4

1 9

r j .

Date: 11/3/06 0041E 3

Estin.ated Date of Cgnoletion SCR No. Description ECN Enaineer Workplan No. U-1 U-2 Consnents EQP 8534 Resplice valve positioner N/A Maxwell MR C C Conplete QIR submit;ed.

3-174 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927, U-2 C C U-1 10, U-2 12 11928, U '

EQP 8536 Valve room submergence 6561 Mechanical 11939 C C Cap drains - 6632 Mods. C . C EQP 8536R1 Valve room submergence 6612 Electrical C C Mods, s

EQP 8537 Rebuild or replace JB 3078 6579 Aniburn N/A C EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C 0 FCo-31-475, -476

?

EQP 8539 Replace capacitors N/A Instrument C C Maint, a

EQP 8540 Replace pigtails to Target 6643 Peters C C Rock solenoid valves EQP 8541 Delete brakes 6582 Branham 11980 C N/A EQP 8542 Replace unqualifled cables 6680 Hall 12/30 N/A two cables will be replaced in accordance with a new issue.

l EQP 8543 Replace JB wire N/A Anturn 11855, 11856 C C 1

• I g hf-

Date: 11/3/96

• 0041E

• Estimated Date of-Completion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Coments EQP 8601 Replace 1 , 2-PT-1-2A, -27A; 6588 Elkins 12014 C C upgrade 2-PT-1-28, -278 EQP 8602 Reroute control cables for No longer an issue.

1 , 2-FCV-70-87, -89 EQP 8603 Replace portion of PP711B 6627 Kimsey N/A C 1

EQP 8604 Cable 1PL3241A not qualified a" "aaaaaaaaa" " "******************a" "aaa No 1onger an issue.

EQP 8605 1 , 2-15-74-43, -44, -45, 6589 Branham C C

.-46 not qualified EQP 8606 Undervoltage concern on 6611 Rutledge 11/24 11/24 In work.

. feedwater isolation valve 6676 t i brakes EQP 8607 Delete TB for 1 , 2-PT-1-2A, 6626 Instrument 12014 C C

-27A Maint.

EQP 8608 Enable / disable Mov brakes 6621 Rutledge C C

66?2 4 6665 6686 EQP 8609 Replace cable IV79738 6618 C N/A EQP 8611 JB has weephole in top N/A Ant > urn N/A C EQP 8612 Replace zone switches 6669 N/A C

, e

Dats: 11/3/86 0041E *

• Estimated

• Date of Concletion

$_CR No. DescriDtion ECN Engineer Workolan No. U-l U-2 Consnents EQP 8614 Weep holes in JB 6652 C C EQP 8615 Replace FT-72-13, --34 EQP 8617 Junction box internal wiring Anburn 11/5 11/5 Workplan is 90 percent conplete.

EQP 8618 Relocate arc suppression 6795 11/30 11/30 Workplan is in writing.

network .

EQP 8619 Valve room sutmerged cables , Holding for corrective action determination.

EQP 8620 Relocate steam generator Instrument Will roll transinitters 1800.

level transmitters Maint.

a

• - EQP 8621 Resolve conduits and fittings Holding for corrective action Y that may be sutxnerged in detennination.

Auxiliary Building i EQP 8622 Replace terminal blocks with Workplan is in writing.

i spliced cables j

i EQP 8623 Replace limit switch on *** "A"aaaaaaaaaaaaaaa"aa" " " " "aaaaa"Aa No longer an issue.

FCV-3, -21 EQP 8624 Junction box 2145 may be aaaaaaaaaaaaaaaaa"a"Aaaananaaaaaaaaaaaaaa* Nolongehanissue, submerged, unit 1 EQP 8625 6.9-kV nondivisional cables Holding for drawings, in trained trays y

$0

~

e Dat2: 11/3/86 0041E 3

Estimated Date of Concletion S_CR No. Description ECN Enaineer Workplan No. U-1 U-2 Comments N/A Move surge suppression 5773 Kimsey 11883 C C network for PORV ELB 8523 Penetration overcurrent 6606 Legg C C N/A Work FCR to delete 1 , 5883 Hall C C Need SI-166.

2-PS-3-160A, -1608, -165A, and -1658 -

N/A Replace 1-FT-1-3A, -3B, -10A, 6347 Instrument N/A C N/A

-108, -21A, -218, -28A, -288 Maint.

NEB 8510 Relocate LT-68-320, 6439 Carrasquillo Various C C i PT-68-323, -320 Peters S Remount 63-71,68-308 64 % Legg 11865 C C 7

Replace LS-65-4, -5 6504 Legg 11865 N/A C MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C Delete brakes FCV-62-61 6521 Branham 11905 C C ELB 8517 Replace pressure transmitter 6488 Branham 11931 C C PDT-65-80, -82, -90, and -97 1 e

4

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O 6

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4 4 b Tills PAGE INTENTIONALLY LEFT BLANK -

0 4

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( )-

a ,

TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 November'14, 1986 b

Nuclear Regulatory Commission Office of Management Information and Program Control g[j)Q S (f

/

Washington, DC 20555 Centlemen:

SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - OCTOBER 1986 Enclosed is the October 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY OR. ruu P. R. Wallace Plant Manager Enclosure cc (Enclosure):

Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcqment Suite 3100 101 Marietta Street Atlanta, Georgia 30323 (1 copy)

Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copies)

Mr. A. Rubio Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 (1 copy)

INPO Records Center Suite 1500

1100 circle 75 Parkway Atlanta, Georgia 30339 (1 copy)

Mr. K. M. Jenison, Resident NRC Inspector d O&PS-2, Sequoyah Nuclear Plant hy An Equal Opportunity Employer

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