ML20212P430

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Monthly Operating Repts for Dec 1986
ML20212P430
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/31/1986
From: Dupree D, Wallace P
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8703160107
Download: ML20212P430 (62)


Text

.

TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER

  • SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COlmISSION

" DECEMBER 1986" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 submitted by:

P. R. Wallace, Plant Manager 8703160107 861231 DR ADOCK 05000327 PDR

9 9

e OPERATIONAL

SUMMARY

TABLE OF CONTENTS Page I.

Operational Summary 1

Performance Sununary 1

Significant Operational Events 2

Fuel Performance and Spent Fuel Storage Capabilities 2

PORVs and Safety Valves Summary 2

Special Reports 2

Licensee Events 3-6 Offsite Dose Calculation Manual Changes 7

II. Operating Statistics A.

NRC Reports Unit One Statistics 8-10 Unit Two Statistics 11-13 B.

TVA Reports Nuclear Plant Operating Statistics 14 Unit Outage and Availability 15-16 Reactor Histogram 17 III. Maintenance Summary Electrical Maintenance 18-19 Instrument Maintenacne 20-27 Mechanical Maintenance 28-31 Modifications 32-42 IV.

Environmental Qualification (EQ) Summary 43-49 0288f

PERFORMANCE SUDMARY 4

December 1986 The following summary describes the significant operational activities for the month of December.

In support of this sununary, a chronological log of significant events is included in this report.

The units remained in an administrative shutdown the entire month due to l

design control review, configuration control updating and resolution of significant employee concerns. Outage related maintenance and modifications are being performed. Unit I has been off-line 496 days. Unit 2 has been off-line 497 days.

1 SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 12/01/86 0001C The reactor was in mode 5.

The administrative shutdown due to design control review, configuration l

control updating and resolution of significant employee concerns continues.

12/31/86 2400C The reactor was in mode 5.

The administrative I

shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.

Unit 2 Date Time Event 12/01/86 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.

12/31/86 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.

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

Unit 2 The core average fuel exposure accumulated during December was 0 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 SFP. Thus, the remaining storage capacity is 1,033.

PORVs AND SAFETY VA1,VES SUlttARY No PORVs or safety valves were challenged in December 1986.

SPECIAb REPORTS The following special reports were submitted to the NRC in December 1986.

86-07 Fire dcor D-1 to diesel generator building 28-B was not restored to function status within the seven (7) days required by Technical Specification (TS) 3.7.12.

The door was opened on November 30, 1986, in accordance with plant procedures for the scheduled six-year preventive maintenance performance and was closed on December 8, 1986. Due to the extensiveness and accuracy required, more time was needed to perform a thorough job.

86-08 A fire watch was missed due to the central alarm system computer being inoperable. This is a safeguard item.

This report was required by TS 3.7.12.

2-

LICENSEE EVENT REPORT (S)

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

LER Description of Event 1-86051 On October 24, 1986, NRC identified several valves that had exceeded their quarterly and two-year surveillance test frequency. Further investigation by TVA personnel confirmed NRC's findings. The sis that initiate the testing of the valves met the sis' required frequency, but the frequency for these valves was exceeded. The valves in question were tested and are now in their required frequency. These valves are required to be operable in mode 5.

New procedures will be instituted to place the valves that are required to be operable in mode 5 in their own procedure.

1-86053 on october 20, 1986, the auxiliary building vent radiation 1-86053/R1 monitor (0-RM-90-101) was declared inoperable due to a failed microswitch and Limiting Conditions for operation (LCO) 3.3.3.10 was entered at 0430 CST. Chemical personnel installed a backup sampler as required. The sampler flow rate was not estimated every four hours as required by SR 4.3.3.10.

This was the result of two personnel errors:

(1) SI-470.5, " Auxiliary Building Iodine Sampler Flow Estimation," used to estimate the flow rate was erroneously cancelled and (2) personnel failed to comply with Action 41 of the SR.

On November 10, 1986, it was discovered that a charcoal filter was missing after the monitor had been returned to service on November 6, 1986. This caused the iodine channel to be inoperable. A new filter was immediately installed.

SI-470.5 is being reinstated to ensure TSs are followed correctly. All personnel involved were instructed in the proper actions to take if the vent monitor becomes inoperable. All systems were returned to normal after maintenance.

1-86054 While performing a review on December 1, 1986, a discrepancy was identified between the "as constructed" wiring diagrams for the 125V de vital battery boards versus the data and drawings used in SI-105, " Vital Dattery and Charger performance Test - Units 1 and 2."

This SI inadequately fulfills TS SR 4.8.2.4.2.d.

personnel failed to update SI-105 to reflect actual plant conditions. This SI will be revised to reflect plant conditions, j

LER DescriDtion of Event 1-86055 on December 1, 1986, at 2215 CST, operations personnel discovered an ABI had occurred, but the relays associated with it were not sealed in, even though all equipment indicated it.

It is assumed that a spike on 0-RM-90-102 occurred illuminating the high radiation indicator (red light), but no high level of radiation appeared on the recorder due to its slow response.

Operations cleared the RM without realizing an ABI had occurred. An annunciator window indicating when an ABI has occurred will be installed. All systems were returned to normal.

1-86056 on December 4, 1986, an investigation involving tt.irteen incore detector tips revealed that there is insufficient evidence to ensure that TS SR 4.7.10 had been met.

SI-56, "By product Material Inventory And Sealed Source Leak Test," provides the procedural requirements for compliance with SR 4.7.10.2.c.

Due to personnel error and inadequate administrative controls, proper documentation cannot ascertain that less than

.005 microcuries of removable contamination existed at the time of installation of the tips. New administrative controls will be implemented to ensure the adequate handling of detector tips.

2-86006 During a review of SI-234.1, " Technical Specification Fire Detectors," on November 6,1986, it was discovered that a discrepancy existed in the number of fire detection instruments to be routinely tested. The SI lists eight detectors while TS requires nine detectors demonstrate operability every six months. One detector (XS-13-36T) was inadvertently deleted due to personnel error. Fire detector XS-13-36T was tested and found operable. SI-234.1 was revised with a checklist which will ensure that inadvertent deletion of TS requirements are not made.

2-86007 During a review of SI-246, "Recalibration Procedure For Reactor Coolant Flow Transmitters," and SI-155, " Reactor Coolant Flow Verification," on November 11, 1986, an error was discovered.

The allowable instrument tolerance used for test point voltages could lead to a TS violation. The tolerance used for test point voltages during the performance of SI-246 could allow the low flow trip setpoint of the reactor coolant system of TG GR 4.3.1.1.1, 4.2.3.4 to be violated. The calibration span for the transmitter is 12.25% tolerance in calibrating the transmitters in question. The TSs could be violated because the tolerance of 12.25% is not restrictive enough. Presently, eight of the twelve transmitters calibrated could be outside TG before the bistable trips on unit 2.01-255 records the data necessary for 81-246, but there are no time requirements for the performance of this DI.01-246 and 01-255 will be revised to ensure Tas are not violated and the transmitters recalibrated.31-255 will be revised to ensure 01-246 is performed in a timely manner.

4

kER Description of Event 2-86008 A CVI occurred at 1814 CST on November 30, 1986, when maintenance personnel failed to notify the operations Section before performing Response Time Test (RT) 106A.2, " Containment Building Lower Compartment Radiation Monitor - particulate."

The first step in the procedure is to have operations block out the signal from the radiation montitor to prevent the CVI. When the test leads were connected to the relay, the CVI occurred.

Appropriate actions were taken to prevent further occurrences.

All systems were returned to normal.

2-86009 A CRI occurred at 1145 CST, December 1, 1986, due to a personnel error while performing a retest of Westinghouse (W-2) switches in accordance with WP12268 as part of the Design Baseline Verification program.

It was discovered that this WP was deficient when testing 2-HS-31A-7A.

The WP required one wire to be lifted; however, an additional lead was not lifted which was in parallel with the contact under test. When 2-HS-31A-7A was placed in the " Actuate" position, the CRI occurred. Personnel were instructed to ensure all procedures are accurate. The system was returned to normal.

5-

ABBREVIATIONS 1.

D/G(s)- Diesel Generator Technical specification 2.

TS 3.

SR surveillance Requirement i

surveillance Instruction 4.

SI 4

containment Ventilation Isolation 5.

CVI Radiation Monitor 6.

RM

'i. WP Workplan

- l 8.

CHI -

Control Room Isolation 9.

ABI -

Auxiliary Building Isolation 4

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OFFSITE DOSE CALCULATION tuulUAL CHANGES No changes were made to the Sequoyah offaite dose calculation manual during the month.

E 4

e OPERATING STATISTICS (NRC REPORTS)

DOCKET NO. 50-327 DATE JANUARY 10, 1987 i

COMPLETED DY D.C.DUPREE TELEPHONE (615)B70-6544 OPERATING STATUS 1.

UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1

NOTES:

2.

REPORT PERIOD: DECEMBER 1986 3.

LICENSED THERMAL POWER (MWT):

3411.0 4

NAMEPLATE RATING (GROSS MWE):

1220.6 5.

DESIGN ELECTRICAL RATING (NET MWE):

1140.0 i

6.

MAXIMUM DEPENDADLE CAPACITY (GROSS MWE):

1183.0 7.

MAXIMUM DEPENDADLE CAPACITY (NET MWE);

1148.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUCH 7)SINCE LAST REPORT, GIVE REASONS:

I 9.

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

3

10. REASONS FOR RESTRICTIONS, IF ANY:

1 i

THIS MONTH YR.-TO-DATE CUMULATIVE i

11. HOURS IN REPORTING PERIOD 744.00 0760.00 4G241.00 l
12. NUMDER OF HOURS REACTOR WAS CRITICAL 0.00 0.00 24444.91
13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
14. HCURS GENERATOR ON-LINE O.00 0.00 23871.13
15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91
17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
18. NET ELECTRICAL ENERGY GENERATED (MWH)

-4272.00

-40170.00 24902559.00 i

19. UNIT SERVICE FACTOR O.00 0.00 49.4G,
20. UNIT AVAILADILITY FACTOR O.00 0.00 49.4E l
21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 44.97!
22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 44.97 i
23. UNIT FORCED OUTAGE RATE 100.00 100.00 37.12
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

l l

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

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

EMPLOYEE CONCERNS.

)

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

CUMULATIVE VALUES HAVE DEEN UPDATED.

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SEOUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : ONE DATE : JANUARY 12, 1987 COMPLETED BY :

D. C. DUPREE TELEPHONE :CE15)S70-6544 MONTH: DECEMBER 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWe Net)

DAY CMWe Net) 01 0

17 0

02 0

18 0

03 0

19 0

04 0

20 0

05 0

21 0

06 0

22 O

07 0

23 0

08 0

24 0

09 0

25 0

10 0

28 0

11 0

27 0

l 12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

l i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-327 UNIT NAME senuoyah one DATE January 5, 1987 COMPLETED BY D. C. Dupree REPORT MONTH DECEMBER 1986 TELEPHONE (615)M70-6544 S

u he Cause & Corrective Y ee O Licensee E4 c-n UE 5E Action to 30 5

55N Event

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No.

Date c

S U5 E

OU$

Report #

SO IO Prevent Recurrence

$5 E

NEc O

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851220 F

744 F

4 Design control, Configuration Updating, and Employee Concerns.

1 3Hethod:

4 Exhibit G-Instructions 2 Reason:

3F: Forced S: Scheduled A-Equipment Failure (Explain) 1-if anual for Preparation of Data B-!!aintenance or Test 2-flanual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)

E-Operator Training & License Examination Outage F-Ailministrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source II-Other (Explain)

SEQUOYAH NUCLEAR PLANT AVERAGE DATLY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : JANUARY 12, 1987 COMPLETED BY :

D. C. DUPREE TELEPHONE :CB15)B70-6544 MONTH: DECEMBER 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWe Net)

DAY (MWe Net) 01 0

17 0

02 0

18 0

03 0

19 0

04 0

20 0

05 0

21 O

06 0

22 O

07 0

23 0

08 0

24 0

09 0

25 0

10 0

25 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

tr tan i mw u n i,-i n e r u n i DOCKET NO. 50-328 DATE JANUARY 10, 1987 COMPLETED DY D.C.DUPREE TELEPHONE (615)S70-6544 OPERATING STATUS 1.

UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 2

NOTES:

2.

REPORT PERIOD:. DECEMBER 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 DEPENDADLE CAPACITY (GROSS MWE):

1183.0 7.

MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1148.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 0760.00 40201.00
12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54 i
13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
14. HOURS CENER ATOR 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)

-6656.00

-64434.00 22567523.60

19. UNIT SERVICE FACTOR O.00 0.00 53.47
20. UNIT AVAILABILITY FACTOR O.00 0.00 53.47
21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 48.90
22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 48.90
23. UNIT FORCED OUTAGE RATE 100.00 100.00 39.13
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
25. YF GHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

THE STARTUP OF UNIT-2 HAS DEEN SCHEDULED FOR APRIL 1987.

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

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME sequoyah Two DATE January 5, 1987 COMPLETED BY D.

C.

Dupree REPORT MONTH DECEMBER 1986 TELEPHONE (615)870-6544 I

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744 F

4 Design Control, Configuration Updating, and Employee Concerns.

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3 Method:

8F:

Forced Reason:

S: Scheduled A-Equipment Failure (Explain) 1-itanual 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 F-Administrative 5-Reduction 5 Exhibit I-Same Source G-Operational Error (Explain) 9-Other II-Other (Explain)

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OPERATING STATISTICS (TVA REPORTS) l f

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tva naza torwe.su NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant Period Hours 744 Month DECEMBER 19 86 item No.

Unit No.

UNIT ONE UNIT TWO PLANT 1

Averace Hourly Gross Load. kW 0

0 0

2 Maximum Hour Net Generation. MWh 0

0 0

3 Core Thermal Energy Gen. GWD (112 0

0 0

4 Steam Gen. Thermal Energy Gen., GWD (t)2 0

0 0

8 5

Gross Electrical Gen., MWh 0

0 0

si 6

Station Use, MWh 4,272 6,656 10,928 h

7 Net Electrical Gen., MWh

-4,272

-6,656

-10,928 8

Station Use, Percent N/A N/A N/A 9

Accum. Core Avg. Exposure, MWD / Ton!

0 0

0 6

10 CTEG This Month,10 BTU 0

0 0

11 SGTEG This Month,106 BTU 0

0 0

12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use, Hours-Min.

0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 y

16 Turbine Avail. Factor. Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 g

C 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 19 Reactor Avail. Factor. Percent O.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 Rate, Blu/kWh N/A N/A N/A j

25 Net Heat Rate, Btu /kWh N/A N/A N/A

E 26 D

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 Temp., 'F N/A N/A N/A b

32 33 Main Feedwater, M lb/hr i

34

[

35 36 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416, j

39 Oil Fired for Generation, Galtons 3,696 2

40 Oil Heatina Value. Btu / Gat.

138.000 41 Diegl Generation. MWh 56 47 Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor, *4 l

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

O Remarks: A For DFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.

j 2(t) indicates Thermal Energy.

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Date Submitted Date Revised 4

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I TVA 6%0C (PP 3-76)

UNIT OUTAGE AND AVAILABILITY SEQUOYAH Nuclear Plant Licensed Reactor Power 3411 MW(th)

Unit No.

ONE Generator Rating 1220.5MW(e)

Month / Year DECEMBER 1986 Design Gross Electrical Rating 1183 g,tw Period Hours 744 METHOD OF UNIT CORRECTIVE ACTION Turne Unit Available Tirne Not Available SHUTTING STATUS TAKEN TO PREVENT Time Time OUTAGE CAUSE DOWN DURING REPETITION Total Gen.

Not Uwd Turbine Gen.

Reactor Unit Out In Day Hrs l M.n Hrs ' Min Hrs ! Min Hrs l Men Hrs l Min Hrs l Min Hrs l Men Hrs ! Man Hrs

  • Men REACTOR OUTAGE 1

00 100 00 l00 l

24 800 24 '00 24 iOO 24 e00 i

Design Control. Configuration N/A Mode 5 QQp0_ 00 t00 t

24 '00 24 l00 24 10 0 24 ! 00 UDdatine. and EmDloyee Concerr s 2

1 3

00 00 00 '00 e

24 iOO 24 iOO 24 30 0 24 i 00 i

4 00 t00 00 ;00 l

24 800 24 800 24 '00 24800 1

5 00 100 00 t00 24 800 24 '00 24 l00 24 !00 e

6 00 800 00 100 1

74 '00 24 +00 24 '00 24 i 00 I

i 7

00 '00 00 '00 24 l00 24 !00 24 l00 24 e00 l

a 8

00 l00 00 '00 l

24 100 24 iOO 24 10 0 24i00 i

,a 9

00 l00 00 iOO I

24 IOO 24 '00 24 !00 24 e00 I

10 00 iOO 00 100 1

24 iOO 24 l00 24 iOO 24 ! 00 e

11 00 100 00 '00 l

24 800 24 t00 24 10 0 24 t00 t

12 00 800 00 l00 i

24 l 00 24 !00 24 l00 24 000 t

13 00 l00 00 iOO 24 '00 24 l00 24 t00 24 ! 00 e

14 00 iq0 00 '00 l

24 l00 24 iOO 24 800 24 l00 i

24 100 24 !00 24 l00 24 100 t

i 15 00iOO 00 !00 16 00 100 00 l00 i

24 '00 24 i00 24 !OO 24 I00 t

l 17 00 100 00 l00 24 i OO 24 !00 24 l00 24!00 a

IM 00 !00 00 iOO i

24 !00 24 l00 24 !00 24 l 00 i

i 19 00 '00 00 800 e

24 iOO 24 100 24 iOO 24 i 00 20 00 ;00 00 100 24 !00 24 !00 24 !00 24 i00 i

l 21 00 iOO 00 l00 24 ;00 24 iOO 24 l00 24 400 e

i 24 800 24 !00 24 a00 24 !00 e

i 22 00 100 00 10 0 i

23.DQ'00 00 80 0 1

24 !OO 24 iOO 24 '00 24 l00 8

8 24 00.00. 00 !00 24 t 00 24 !00 24 iOO 24 00 I

25 00j00_00 10 0 i

24 !00 24 l00 24 '00 24100 i

26 00 n00 00 10 0 l

24 l00 24 iOO 24 l00 24300 e

i i

27 00 000 00 !00 1

24 800 24 100 24 80 0 24 ! 00 t

i 100 00 100 i

24 l00 24 !00 24 l00 24l00 8

28 90 30 0

0 l

i 24 iOO 24 100 24 t00 24100 e

e 31 100.00 00 s00 e

Total 100 800 00 l00 744 !OO 744 '00 744 j00 744 l 00,%XXX X

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TVA 6560C (PP 3-76)

UNIT OUTAGE AND AVAILABILITY SEQUOYAH

4uclear Rant Licensed Reactor Power 3411 MW(th)

Unit No.

WO Cenerator Rating 1220. 5 MW(e)

Month / Year DECEMBER 1986

' Design Gross Electrical Rating 1183 MW Period Hours 744 METHOD OF UNIT Torne Unst Available Time Not Available CORRECTIVE ACTION Time Time SHUTTING STATUS TAKEN TO PREVENT OUTAGE CAUSE Total Gen.

Not Uwd Tufbine Gen.

Reactor Unit Out In DOWN DURING REPETITION a

Day Hrs l Men Hrs ! Min Hrs ! Men Hrs, M,n Hrs l Man Mrs l Man Hrs l Min Hrs ! Min Hrs I Man REACTOR OUTAGE 1

1 00 iOO 00 l00 l

24 800 24 '00 24 iOO 24s00 i

Design Control, Configuration N/A Mode 5 2

0.0 !OO 00 iOO I

24 !00 24 l00 24 80 0 24 ! 00 Updating. and Employee Concerr s 3

00j00 00 '00 24 ioO 24 iOO 24 '00 24 ; 00 l

3 00_ tD0_0Q_j00 l

24 800 24 '00 24 !00 24'00 I

5 00_!00_ 00 iOO i

24 '00 24 l00 24 l00 24!00 8

6 g

ID0_.00 100 1

24 l00 24 500 24 !00 24 i 00

/

nn. 00 00 '00 24 l00 24 !00 24 l00 24eao l

e H

DO l00 00 !00 l

24 800 24 IOO 24 10 0 24 00 e

4 nn 00 no inn 24 'on 24 8 00 24 !00 24e00 i

10 nninn an 8nn 24 inn 24 jnn 24 iOO 24!00 II 00 100 00 !OO 24 800 24 iOO 24 10 0 241 00 g

12 00 800 00 l00 i

24 l00 24 !OO 24 l00 24000 l

24 !00 24 l00 24 iOO 24 ! 00 a

13 00 '00 00 iOO 24 l00 24 iOO 24 '00 24l 00 14 DQdD0_Dag'.00 0

3 15 00.00 00 i

24 800 24 '00 24 l00 24 t 00 t

i 16 00 000 00 IOO i

24 00 24 i00 24 !00 241 00 t

i i

17 00 It'l 00 l00 24 i OO 24 300 24 l00 24 ! 00 I

18 00 !O' 00 100 i

24 !OO 24 l00 24 800 24 l 00 i

e 19 00 l00 00 100 i

24 iOO 24 100 24 iOO 24 i 00 I

3 8

24 ! OO 24 !00 24 !00 241 00 i

l 20 00j00 7 SO 21 00 #00 00 iOO l

24 iOO 24 300 24 ;00 248 00 22 00 100 00 iOO 24 800 24 !00 24 100 24! 00 t

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12 16 20 24 28 32 DECEMBER 1986 SEQUOYAH TWO REACTOR HISTOGRAM 100 90 -

80 -

70 -

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40 -

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0 4

e

SUMMARY

OF MAINTENANCE ACTIVITIES

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MAINTENANCE

SUMMARY

(ELECTRICAL)

1 ELECTRICAL MAlNTENANCE MONTHLY SU GARY 01-05 PAGE 1 f.

COMP THR. COMP U FUNC SYS ADDRESS. DATE.... DESCRIPTION.............................

CORRECTIVE ACTI0N.......................

l.b Q.

^

B125429 1 AHU 061 0615A 11/20/86 1-AHU-061-0015A et*NPRDt]rDRIVE BELT IS POSSIBLY, MOTOR LOCKED UP DUE TO WATER D%

CRACKED NEEDS REPLACED FALLING FROM DRAIN PAN ONTO MOTOR, yy$

'J' AND HAD COILS REWOUND. RE FREEZING MOTOR WINDINGS. R

~

SERVICE. WR B-125429.

Y iB125706 1 HTEB 313 0426 09/23/86 1-MTRB-313-0426-Br[tNPRDt],1A PRESS FAN PULLEYWASBADCAUSINGBEARINGSTOWEAR.M

'MTRMAKESUNUSUALNOISEFROMITSOUT 4

??

MTR BRG ENERGIZED FAN MOTOR AND RETURNED TO jf M

yJG '

. SERVICE. REFERENCE WR B-202909 FOR qig REPLACEMENT OF PULLEY AND BELTS. WR VMy

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+

B-125706.

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0001B08/29/861-GENB-082-0001B-Bet *NPRD*],ERRATICLOADLOADGAIhANDSTABILITYPOTENTIOMETER PEh):

'B126068 1 GENB 082 M$ Q M

CONTROL CHECK LOAD CONTROL CIRCUITS. 1BB WAS 001 CF ADJUSTMENT.' A?)USTED

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DG GOVERNCR CONTROL POTENTICMETER FOR PROPER LDAD GAIN. WR

..f M B-126069.

M:d Y

'B128247 1 GENB 082 0001B 09/25/86 1-GENB-082-0001B-Be[*NPRD*],D/G 1B-B THE TIME DELAY RELAY WAS OUT OF TIME DELAY RELAY 48. ADJUST / REPLACE TB8 ADJUSTMENT PROBABLY DUE-TO AGE AND..

43 RELAY TO OBTAIN ACCEPTANCE CRITERIA 0F VIBRATION. ADJUSTED TIME DELAY RELAY #8,

,Z

.1011 SECCNDS FOR STEP 6.3.8 IN SIl02 -

TO 10H-) SECONPS AND RETURNED TO N

'E/SA TIME RECORDED DURING TESTING WAS SERVICE. WR B-128247. ' ' ' M :O

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'6.7 SECONDS

U 5N B129959 2 AHU 061 0024A 11/20/86 2-AHU-061-0024A,[*NPRD*3, ICE DOES NOT THE MAGNETIC CONTACTOR COIL WAS OPEN.

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J B202073 2 MTR9 030 0176 11/24/86 2-MTRB-030-0176-B,[*NPRD*],R00M COOLER MOTOR WAS BAD DUE TO BAD BEARINGS, i

MOTOR BEARING.

CAUSING FAN BLADE TO SCRAPE END BELL.

t REPLACED RESISDUAL HEAT REMOVAL COOLING 7

UNIT MOTOR AND REINSTALLED BELTS AND BELT GUARD. UR B-202073. '

.A B202083 2 AHU 061 -0024A 11/20/86 2-AHU-061-0024A,I*NPRD*],AHU WILL NOT THE MAGNETIC CONTACTOR COIL WAS OFEN.

MANUALLY IEFRCST

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f

'l UNIT. WR B-202083.

B202103 '1 GENB'002' 0001B 09/25/86 1-GENB-082-0001B-B,ItNPRDt],D/G 1EB D/G THE FREQUENCY RESISTOR WAS'0UT OF BLDG. 1B-B D/G STARTED FROM SI TEST ADJUSTMENT. ADJUSTED THE FREQUENCY SIGNAL FOR SI-7 D/G VOLTAGE AND FRED RESISTOR TO OBTAIN 60 HZ. UR B-202103.

WERE WITHIN LIMITS BUT D/G FRED STABLIZED AT 59.6 HZ. Il SHOULD HAVE STABLIZED AT 60HZ. INVEST AND REPAIR NOTE! AFTER 8660R WAS RESET FREQ CAME UP TD 60 H2 B202789 2 ZS 061 0122 1 10/31/86 2-Z5-061-0122 1-1.CtNPRD*],VLV WILL THE STRIKER PLATE ON THE VALVE STEM WAS N3T STAY OPEN OUT OF ADJUSTMENT PREVENTINS THE CONTACTS FROM MAKING UP. ADJUSTED THE STRIKER PLATE ON THE VALVE STEM. WR B-202789.

B202876 2 BCTA 069 0341A !!/18/86 2-BCTA-068-0341A-A,CtNPRDt),PER HTR BRK POSSIBLY, THE RELAY COIL BURNED UP DUE-

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CFF 2AA SD BD WILL NOT CPEN FROM MCR TO NCRMAL WEAR. REFLACED 30RX '

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SUMMARY

01-05-87 PAGE 2

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  • 'B204231 'l' BATB '082 UC 10/02/86 1-BATB-082-UC-B,I*NPRD*]eCELL' 443 DID ^ PATTERY CELL POSTS WERE DIRTY' CAUSING M N,N k t'_

J,

NOT PASS SI 238 STEP 6.1.1 PAGE 2

-- CONNECTION RESISTANCE TO READ HIGH. -., NM

. _., REPLACED THE Z-BAR BETWEEN CLEANED BATTERY CELLS USING MI-10.54 AND:

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. 0091 11/04/86 2-BCTD-067-0091-A,[*NPRD*] FUSE BLOWS AS ELECTRICAL CIRCUIT ON RELAY A181 WA

,..gp f,i

- SOCN AS IT IS INSTALLED

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BAD.-REPLACED RELAY A181 ON ANNUNCIATCR' M y &

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CIRCUIT MONITOR. OPERATIO Qg'i' '

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1/16 FUSE AND RET.URNED TO S

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SUMMARY

(INSTRUMENTATION)

j INSTRUMENT MAINTENANCE MONTHLY REPORT FOR DECEMBER 1986 Colet0N 1.

Five PROS were initiated because instruments were found out of tolerance during routine SI performances. All were nonreportable. PRO numbers were 1-86-345, -346, -355, -362, and 2-86-120.

2.

Workplan 120222, ECN L6645, changed the range for R-90-275, -276, -277, and -278.

All field work and postmodification test requirements have been completed.

3.

Volumetrics delta pressurefcalibrators were returned to the vendor for repairs. These are needed~to calibrate the static o-ring pressure switches which were installed in systems 68, 74, and 87.

This is a startup item.

4.

A control building vent isolation was generated from RM-90-125 when recorder RR-90-125 developed a short circuit. PRO-1-86-367 was initiated to investigate.

5.

Completed evaluation of Nuclear Plant Reliability Data System (NPRDS) equipment failure reports for the period from July 1984 to June 1985 in accordance with Sequoyah's recently developed trending program.

Specified and initiated corrective actions needed to increase the reliability of various plant instruments.

Evaluations are continuing on additional NPRDS failure reports.

6.

Completed review of technical specifications and FSAR to identify preventive maintenance activities. Prepared a report to document additional action items needed to ensure compliance. This was a startup item (SAL ID #0316) required by the Nuclear Performance Plan.

UNIT 1 1.

Four work requests were received on the refueling water storage tank wide range level transmitters (1-LT-63-50, -51, -52, and -53).

All four control room indicators were reading high. An investigation revealed that during a heavy rainstorm, the water level in the moat area had i

risen and shorted out the transmitters. When the water level subsided, the transtitters and enclosures were inspected. The general condition of the transmitters and enclosures was deteriorated (i.e., rusted terminal blocks, missing transmitter cover screws, enclosure heater elements rusted, and missing covers on the heater thermostats).

Corrective actions are currently underway to repair the equipment.

Long-term corrective actions to prevent recurrences are also being considered.

2.

An auxiliary building vent isolation was generated from an apparent high radiation signal on RM-90-102. PRO-1-86-341 was initiated. '

UNIT 2 1.

Two containment vent isolations were generated from 2-RM-90-106M.

PRO-2-86-115 and -118 were initiated to investigate. The first isolation was caused by personnel error which occurred in setup of a response time test. The second event was caused by a high radiation spike which was generated by electromagnetic interference (EMI) being produced from a sample flowswitch actuation and a local alarm buzzer.

2.

Reactor Vessel Level Instrumentation System (RVLIS) vendor manual was PORC approved. This will allow use of the manual during performance of step-by-step calibration which began this month for unit 2.

It is planned to have the unit 2 system operable for startup.

3.

Submitted SMI-2-63-3, " Replacement Of Containment Sump Level Transmitter 2-LT-63-177," for informal PORC review. Replacement of this transmitter is required prior to startup.

4.

During the performance of plant instruction IMI 99 RT 16.7, response time test for phase A containment isolation, a phase B isolation occurred, as well as a suspected phase A isolation. PRO-2-86-117 was initiated and investigation showed that a procedural problem caused the phase B isolation; however, no explanation for the suspected phase A isolation could be determined. A retest of the procedure did not result in the phase A as did the earlier test. Later, Operations determined that only the air-operated phase A isolation valves closed and that was caused by the phase B signal isolating the air supply to those valves.

The phase A signal was never actually received.

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O MAINTENANCE

SUMMARY

(MECHANICAL)

i MECHANICAL MAINTENANCE MONTHLY REPORT FOR DECEMBER 1986 COMMON I

1.

Continued Grinnell valve diaphragm replacements.

2.

Prepared Special Maintenance Instruction for instrument line clamp inspection.

3.

Replaced packing, stub shaft, and shaft sleeve on ERCW pump.

4.

Prepared action plan for control building roof leaks.

5.

Continued rebuilding "B" waste gas compressor.

6.

Developed contingency plan for auxiliary boiler outage.

7.

Completed hanger bolt tightening walkdown.

8.

Performed new preventive maintenance on CO2 system.

9.

Completed the 6 year preventive maintenance on the emergency diesel engines.

UNIT 1 1.

Prepared for steam generator row 1 U-bend stress-relieving.

2.

Performed spring test on main steam isolation valves.

UNIT 2 1.

Performed spring test for main steam isolation valves.

2.

Continued Grinnell valve diaphragm replacements, i

3.

Repaired leaking 0-ring in 2BB containment spray pump which was allowing component cooling water to leak in the reactor coolant system, i

4.

Assisted in preparation of action plan for feedwater piping inspection i

as a result of surry accident.

5.

Rebuilt 2-FCV-62-636.

6.

Received spare low pressure rotor from Westinghouse repair facility.

7.

Continued procedure review / revision for restart.

8.

Began compiling data for Operational Readiness Review.

l i

illutMILAL MihlE.WCE riuiti;tY Mt.AWY 91-0:;-61 TACE 1 CDf58 i~2. HIST U FUNC SYS ADDESS. DATE.... ESCRIPTIDN.....

............. C ORR ECTIVE ACTIM.......................

B10W5 1 TCU 041 007111/12/841-TCU-041-0071,EwMPRDn3,TCU HAS FAILED ICE BUILDUP ARDillD SPRING. INSTALLED NEW CPEN ULY AND CECKED TOR LEAKS. FERFORMED TUNCTIDNAL CHECK AND RETuSED TO SERUICE B202037 2 FCD 030 0004812/12/86 2-fCD-030-00048,NOT CLOSING AFTER HDRN DIAPHRAGM. INSTALLED EX ACTUATDR SUPLLY FAN 't" Off B202193 2 AHU 041 0007812/08/84 2-AHU-041-0007B,ENNPRDn3, DRAIN LINE BAD HEAT TRACE. REPAIED EAT TRACE APPEARS TO K BROKEN AND HAS CAUSED CHECKED FOR OPERATION AND KTIENED TO INTEREDIATE KCK DOOR TO KCOME TRDZEN SERVICE SHUT B202195 2 AHU 061 0026B 11/29/84 2-ANU-0di-002dB,EuMPRDu3, DRAIN LINE APPEARS TD E BROKEN AND HAS CAUSED INTEREDIATE DECK D0DR TD BECDE FADZEN SHUT 4 records listed.

"B202724" not found.

't126534" not found.

't123325" not found.

"B126727" not found.

"B208459" not found.

't208454" not found.

"B208152" not found.

"A2379di" r at found.

"B208333" not found.

't126524" not found.

't202525" not found.

"B131429" not found.

"B201261" wt foun4.

"B202223" n>t found.

"B214452" n t F.>und.

1.___

nECxWitAL MihIEhANct inMfhtY lutdVKI Gl* U PAGE 1 CINF

. O.CIRF U FUNC SYS ADDESS. DATE.... KSCUPTION........................... CMRECTIVE ACTIM...........

l A2371di i ICV 047 0490A 11/20/841-FCU-Od7-0490A-B,uMPRDu EUS AITEAR TD K LEAKING THRDUGH BADLY-B123325 1 ENG 082 0001A111/25/841-ENG-082-0001Al,EuMPE5m],TRDRE SHDDT DEFECTIVE DIL PESSUK RELIEF UALUE DUE D/G 1M FOR KASON ENG KEEPS TRIPING ON TO NORML' DPERATIDN. INSTRLED KH DIL HIGH PESSURE ELIEF URUE PERFDHED SURUEILLANCE INSTECTIM 7.1 MD RETURNED TD SENICE l B124524 0 K 090 020412/10/84 0-E-090-0204-B LDW F'.DW MD PIRF FAIL PUMP FRO 2E 1F AB STARTER DEFECTIUE.

TD NN INSTRLED HEW PMP 8 STARTER B124534 0 E U 02d 098412/02/84 6-ULU-024-0984,WHEN FCU IS MMELY WDRN UALUE. INSTELED NEW URUE ISRATED WATER STILL RUNS DUT DMIN HOSE SUSPECT PORY LEAKING TEDUCH B126727 1 ULY 070 049412/01/841-EU-070-049e-A.EuMPDu3, RELIEF EU DIRT UWER SEAT NDT RLDWING URUE TD LEAKING THRU DN FLODR FULLY CLOSE. DISASSEMBLED UALUE CLEANED SEATS AND TESTED AT 160 PSI. CKCKED FOR LEAKS MD RETURNED TO SERVICE j B131429 2 LCU 003 0175 09/02/86 2-LCU-003-0175-A,EuMPRDu],KPLAE UNKNOWN. FABRICATED MD INSTALLED NEW INDICATOR DN UALUE STEM TMT MAKES IF AM As TMNSFEB TD DPERATIONS FOR LIMIT SWITHCES SURUEILMCE INSTRUCTION Idd.d F201241 1 ULY 070 068712/02/841-ULU-070-0487-A,ENNPRDu], REPAIR AS TRASH UNDER SEAT NOT ALLOWIHG ULY TD KEDED THIS URUE IS TESTED WITH SEAL IFF. CLEANED ULY BDDY LAPPED SEAT 1-FCU-70-87 AND DISC PERFORED SI 158.1 AND ETIIINED TD SERUICE l 0202223 1 FCU Od3 003812/17/8d 1-FCU-043-0038-B,EuMPRDu3,1 SUSPECT STEM NOT CDUPLED UP CDRRECTLY.

INSTRLED KW STEM SEAT AND PACKING PERFDRMED SI 164.6 AND RETURNED TO SERUICE B202525 2 RM 090 013012/10/84 2-N-090-0130-A PUMP MOTOR APPEMS TO PE WMN ETDR 5 PulF. REBUILT PUMP AND BLIIED UP IMUESTICATE AND REPAIR AS WE INSTELED KW MTOR MY NED THIS SOEDAY P202724 0 ULY 02d 103512/02/84 0-ULU-02d-1035,0-24-1035 TO STIP WDEN URUE. INSTELED KW UALVE.

LEAKAGE FRM EU WHEN FIRE HEADER IS CHAWRGED DENSTEM B208152 1 LCU 042 0135 12/05/84 1-LCU442-0135-A, EuMPRDu, uCZDNEu3,C-ZDNE i

LEAKING ULV 4

B208333 0 FMP 067 0%411/19/84 0-PMP447-04A,EuMPRDu], FLOW IMPELLER CLEARANCE ET OF ADJUSThENT.

l.

PERFDRMCE DDES NOT KET MMUFACTUKRS ADJUSTED IMPELLEi: CLEARANCE, PERIDRMED SPECS ADJUST DR REEUILD PUMP AS REQUIRED SI-45.1 AND KTURNED 10 SERUICE.

TD DBTAIN PROPER PERFORMANCE D208454 2 ULY 047 0585011/12/84 2-ULU-0d?-05850-B,EuMPRDu], TESTED PER SI DIRTY WATER AND RUST. DISASSEBLED UALUE 158.1 IN TANDEM WITH 47-299. FAILED WITH AND CLEMDED INTERNALS PEPFORMED A LEAK RATE OF 0.3184 REF LEAK RATE SI-153.1 MD RETURNED TO SERUICE j

0.1200

, B208459 2 ULY 047 0585C 11/24/84 2-ULU-061-0585C-A,ENNPRDu], CHECK ULY RUST AND SCRE IN SYSTEM. DISASSEMBLED TESTED IN TANDEM WITH FCUd7-296 FAILED URUE AND CLEAED BODY, SEAT 5 DISC.

SI 158.1 LLRT WIT'i A READING DF 15.4334 PERFORMED SI158.1 AND RETURED TO SCFH SERVICE.

I l

\\

i i

a !

P.LCitMlutL c.dlalEtiMUL r;u:HhLY EnnN!

01-vJ ol hibt. 2 00nP C. Car U FUNC SYS ADDRESS. DATE.... DESCRIPTION.......................... CDRRECTIVE ACTION....................

821%52 2 ULY 042.

048312/22/84 2-EU-042-0683-S.ULY WILL NOT CUISE WORN DIAPlWAGM 8 0-RING. INSTALLED NEW INUEST AND REPAIR DIAPiiRAGM S D-RING 15 re<ords liskd.

'T2021'l5" not found.

'S2021'0" not found.

'Ti%545" not found.

'1202037" not found.

9 k

i l

l

. t_

- - ~ - - - -

0 4

4 MAINTENANCE

SUMMARY

(MODIFICATIONS) l l

l l

i l

l

SUMMARY

OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS DECEMBER 1986 APPENDIX R ECN 6300 - Additional Sprinklers and Draft Stops The draft stop workplan is in work, and the sprinkler workplan is in the approval cycle. A workplan for the electrical portion is in the approval cycle.

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

ECN 6319 - High-Pressure Fire Protection Rework Workplan is in work.

OTHER ITEMS ECN 5435 - Fire Doors The installation of weatherstripping continues as resources permit.

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. Additional safety gates are to be installed.

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 perimanent power to manholes 42-46.

Electrical conduit and wiring installation for manholes 44, 45, and 46 complete per Workplan 12262. Additional FCRs are in process for manholes 42 and 43 and to provide sump pump for manhole 45.

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

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

ECN 5609 - Air Compressors Makeup Water Treatment Plant

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Air compressors and mechanical piping complete except for tie-in to headers which is held for issue of electrical drawings.

ECN 5609 - As-Construct Makeup Water Treatment Plant Drawings per SQ-DR-86-03-61R Final drawings marked up and given to DNE drafting to update.

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

ECN 5703 - Reinforcement of Block Walls DNE h?.s added a requirement for signs to be posted in areas where block walls exist. This is in process. Work was resumed on unit I wall supports.

ECN 5713 - Various Platforms in Lower Containment The first trolley was modified by the vendor and site testing completed. 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 5855 - Replacement of Doors A56/A57 The workplans remain in the review cycle. -- -

ECN 5880 - UNID Tags for Class 1E Fuses Field verification of Class 1E fuses and penetration cable protection is approzmately 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 Heater and Eroded Pipe Modifications Group B is supporting postmodification testing (PMT) on heaters 1 and 2 on both units as requested. Insulation work on unit 1 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 1 heaters 3 and 4.

ECN 6014 - Replacement of ERCW Pump Bearing Piping Work is holding awaiting resolution of piping deficiencies.

ECN 6057 - Cable Tray Covers This work on hold pending evaluation of cable tray efforts with respect to cable ampacity.

ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete (prior to mode 4).

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

ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete 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.

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ECN 6380 - Replacement of Barton Pressure Transmitters The unit 1 workplan continues in the approval cycle.

ECN 6357 - ERCW Roof Access and Rails for Security Equipment Workplan 12238 held for DNE approval of FCR showing installation details. DNE has promised 1/15/87 to release FCRs.

ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan 12223 approved for five remaining heaters. Work in process pending safe access to current transformers.

ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation All work la complete.

In-service tests will be performed when the system is brought up to temperature and pressure.

ECN 6455 - Upgrade CU-3 Box Battery Packs Workplan in approval cycle.

Engineer attempting to locate material purchased by DNE several years back.

ECNs 6491 and 6534 - ERCW Supports All hangers for unit 2 (ECN 6534) have been completed. Six hangers remain for unit 1.

Drawings are still to be issued for drawing-change-only workplan (ECN 6534).

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

ECN 6556 - Replace Solenoid Hangers and Limit Switches Fieldwork is complete. Lack documentation only.

FCR to complete unit I workplan.

ECN 6601 - Removal of Unit 1 EGTS Backdraft Dampers PMT remains to be completed by the Engineering Test Section.

ECN 6610 - Modify Air Return Fan Supports Unit 1 work is incomplete.

ECN 6661 - Upgrade of 'ERCW Piping During final closeout, it was discovered that additional work was required for the instrumentation lines. This is currently in progress.

ECN 6687 - Additional Office and Medical Facility Modification to medical facilities in process. Lead-shielded dry wall due 1/22/87 and doors due 2/19/87. Fencing along railroad area and west side in process.

ECN 6687 - South Central Bell Environmental Unit (SCBEU)

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Workplan 12251 in work. Building complete. All conduit installation complete. Cable pulls for power cable holding for pull cards from DNE.

j ECN 6689 - Relocation of Mainsteam PORV e

Reworking conduit and cable in process due to design errors.

Relocation of controls is expected shortly. Unit 1 conduit is in progress. Mechanical work for unit 2 is complete except PNT.

ECN 6698 - Repull 120-Volt Cables 4

All cables have been pulled. Workplan on terminations is in work.

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

ECN 6706 14 Support Enhancement i

Fieldwork completed on unit 2 and in progress on unit 1.

Initial inspections for unit 1 lack approximately 100 supports from

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completing. Unit 1 evaluations are continuing.

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ECN 6707 - Replace System 74 Flow Switches i

l First train is inetalled. Calibration equipment has been returned to vendor for rework.

Estimated return of calibration equipment is 1/21/87.

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ECN 6715 - D/C Random Loads Final tie-ins will be made in January during the regularly scheduled diesel surveillance.

ECN 6717 - Stub Bus Fuses Workplan is ready for work.

ECN 6719 - Volumetric Intrustion Detection Systems Workplan 12186 in work for civil and architectural features.

Workplan 12278 approved for conduit installation only.

Excavation and grading approximately 80% complete. Fence post behind diesel generator building complete. Installation of fabric and remaining fencing holding for material.

ECN 6720 - Crane Consistency Program Initiation of workplans holding for design and/or vendor information.

ECN 6739 - Alternate Analysis Work is in progress. There are 242 supports out of 250 on unit 2 completed. Approximately 10 additional support modifications are expected.

ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits Workplan is being worked in parallel with ECN 6698.

ECN 6746 - Install Fuses Workplan is in approval cycle.

ECN 6749 - Replacement of Bussman KAZ Replacement of MIS-5 will begin in February after receipt of new type of fuses and revised drawings.

ECN 6752 - Modification of P.D.

(Anchor Problems)

Fieldwork is complete. Some conduit rerouting remains incomplete.

ECN 6757 - Ice Condenser Valve Supports The workplan was written and placed in the approval cycle.

ECN 6758 - HVAC Supports Work is continuing for unit 1..

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i c-i ECN 6761 - EVR Blowout' Panels (h

All identified fieldwork was completed for unit 2.

The workplan for unit 1 was placed in the approval cycle.

ECN 6763 - Add Fuses to Flow Switches Workplan is in work.

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ECN 6768 - Rework Cable Tray Hangers i

l Workplan is being written. Drawing delivery is holding up

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completion of workplan.

ECN 6769 - Auxiliary Air' Compressor Traps Fieldwork was completed on one compressor. Work on the remaining compressor is being held for material delivery unassociated with this modification.

ECN 6770 - Water Spray Mechanical fieldwork completed.

Electrical work is completed.

ECN 6781 - Hanger Pipe Clamps All identified fieldwork is complete.

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ECN 6783 - Replace Motor on 2-MOV-70-87

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Workplan is. written. Motor was deliverd in December, however, s

- additional required parts have not been delivered.

ECN 6787 - Inspection and Replacement of Solenoid Valve Supports Ih Variances have been submitted to DNE for review. The workplan was written and approved.

Fieldwork will start when DNE completes their s

review.

,y ECN 6790 - Medium Energy Pipe Break Workplan was approved for sealing spare penetrations. This item was removed from startup list.

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ECN 6802 - Modify EGTS Filter Housing The workplan was written and placed in the approval cycle.

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ECN 6805 - Replacement'of Filters in Control Building and Auxiliary Building Gas Treatment System Fieldwork completed. DNE will issue EQ radiation drawings later.

ECN 6809 - MSVV Insulation The workplan for insulation installation was written and placed in the approval cycle. The workplan for the screens will be written upon receipt of the drawings.

ECN 6810 - Rewort Category "C" Devices Workplans are in writing.

ECN 6821 - Screens for RCPs The workplan was written and placed in the approval cycle.

ECN 6822 - Add Fuses to Flux Mapping System Workplans are in writing.

ECN 6823 - MSVV Hot Pipe Remedy All cable removed. Workplan for replacement in writing.

ECN 6826 - Ice Condenser Drains No design received to date.

ECN 6829 - Modify Control Building Fire Dampers No design received to date.

ECN 6835 - Ampacity Constructability walkdowns in process.

ECN 7000 - Addition of Support to Main Steam Dump Header Workplan implementation continues for unit 2.

I ECN 7003 - Thermal Mov'ement of Civil Structures No design received to date.

Dry Active Waste Building (DCR 1898)

Available work complete. Remaining work held for release of drawings.

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

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

Workplan 12208 written, but held for design drawings.

Procedure Revisions Many manhours were spent revising procedures (M&AI's).

Rework Hut 23 for Office Complex Complete except for checkout of fire detection system. Final checkout holding for material.

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

Trailer Complex i

Complete.

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MODIFICATIONS COMPLETE ECN DCR SYS UNIT DESCRIPTION L6218 F2652 067 2

Add a stainless steel doubler on ERCW carbon steel pipe as a temporary repair to those areas which have eroded due to excessive cavitation.

L6265 F2933 400 0

Allow removal of concrete foundations that were previously required for reverse osmosis equipment.

L6494 F3763 067 2

Replace degraded ERCW discharge piping with carbon steel pipe coated with Belzona molecular ceramic.

L6573 D2211 202 1

Lift wires for breakers 1716, 1728, 1816, and 1828.

L6606 D0972 000 2

Add fuses to provide overcurrent protection for penetrations 40, 52, and 53.

L6692 D0972 003 2

Replace of feedwater bypass control valve solenoid valves with Class lE qualified solenoid valves. Provide seismic mounting for solenoid valves.

L6736 F3348 082 1

To correct as-constructed drawings by removing a pressure switch that does not exist from drawing and showing the time delay logic. Document change only.

L6775 D2259 067 1

The replacement of the overcurrent relays in the 6.9 kV shutdown boards for ERCW pumps K-A, Q-A, J-A, R-A, L-B, N-B, P-B, and M-B.

Reference ECN L5320.

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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.

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4 ENVIRONMENTAL QUALIFICATION (E.Q.)

SUMMARY

Dat2: 1/3/87 0041E Estimated Date of Concletion SCR No.

Description EDI Engineer Workplan No. U-1 U-2 Comments EQP 8501 Disconnect 1-and 2-HS-62-61 6524 Peters 11901 C

C U-2 QIR submitted.

EQP 8502 Replace penetrations 23 and 48 6490 Peters 11001, 11802, C C

Couplete QIR sutaitted.

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.

EQP 8504 Splice methods not correct N/A Stockton 80 Nts EQP 8505 Drawing N/A N/A N/A N/A N/A EQP 8506 seal containment isolation 6514 Kimsey 11880 C

C valve 5

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EQP 8507 Rewire MDV N/A Rutledge 11866, 11853 C C

EQP 8508 JB weepholes (press) 6523 Alas 11898 C

C Conplete QIR submitted.

EQP 8500R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C

EQP 8509R2 Conduit seals 6615 N/A N/A N/A No fieldwork remaining.

EQP 8510 Disconnect local handswitches 6527 Peters 11901 C

C EQP 8511 Submerged OB inside 6549 Peters 11901 C

N/A containment

Date: 1/3/87 0041E Estimated Date of Concletion SCR No.

Description ECN Engineer Workplar. No.

U-l U-2 Comments EQP 8512R2 Rewire JB N/A Asburn 11855, 11856 C C

All boxes rewired.

EQP 8513 Weep holes (moistua l 6547 Alas 11898 C

C Couplete QIR submitted.

EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C

C Couplete QIR submitted.

EQP 8514 Motor insulation 74-1, -2 6540 Branh a 11906 N/A C

Complete QIR submitted.

EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C

C EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C

Maint.

EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C

EQP 8518 Submerged cables 6533 various/6 various C

C EQP 8519 Tee drains N/A Electrical N/A C

C Complete 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 18 and rework splices 6551 EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C

EQP 8522R2 Rewire local panels N/A Instrisnent 12016 C

C Maint.

Date: 1/3/87 0041E Estimated Date of Concletion SCR No.

Description ECN Engineer Workplan No.

U-1 U-2 cmts EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C

and misplaced brackets EQP 8524 Change setpoints 6551 Instrument 11916 C

C Maint.

EQP 8525 Reterminate hydrogen N/A Electrical N/A C

C Coupleted by Electrical Maint.

reconbiner (IWt)

Maint.

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

C Mods.

EQP 8527 Coat TB, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C

(MR) 3 EQP 8528 Solder strain gauge Barton IMI Instrument N/A C

C QIR submitted 1/24.

transmitters Maint.

e EQP 8529 PDT-30-42 -43 6554 Legg 11912 C

C EQP 8530 Gasket Namco L/S N/A Electrical N/A C

C (MR)

Maint.

EQP 8531 Delete Mov heaters 6544 Rutledge 11866, 11853 C C

EQP 8532 Delete L/5 1, 2-43-201, 6630 Alas N/A N/A No longer an issue.

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

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Date: 1/3/87 0041E Estimated Date of Co eletion SCR No.

Description ECN Enaineer nIDrkplan No. W1 W2 cmments EQP 8534 Resplice valve positioner N/A Maxwell PWI C

C Complete QIR submitted.

3-174 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927, W 2 C

C W 1 10. W 2 12 11928, W1 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.

EQP 8537 Rebuild or replace JB 3078 6579 Auburn N/A C

EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C

FCD-31-475. -476 EQP 8539 Replace capacitors N/A Instrument C

C Maint.

EQP 8540 Replace pigtails to Target 6649 Peters C

C Rock solenoid valves EQP 8541 Delete brakes 6582 Branham 11980 C

N/A EQP 8542 Replace unqualified cables 6600 Hall 3/30 N/A Two cables will be replaced in accordance with a new issue.

EQP 8543 Replace JB wire N/A Asburn 11855, 11856 C C

Date: 1/3/87 0041E l

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Description ECN Engineer ndorkplan No. U-1 U-2 Comments a

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.


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1, 2-FCV-70-87, -89 EQP 8603 Replace portion of PP7118 M27 Kinsey N/A C

EQP 8604 Cable IPL3241A not qualified No longer an issue.

EQP 8605 1, 2-TS-74-43, -44

-45, 6589 Branham C

C

-46 not qualified l

EQP 8606 undervoltage concern on 6611 Rutledge 3/30 C

In work.

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feedusater isolation valve M76 brakes 4

l EQP 8607 Delete TB for 1 2-PT-1-2A, 6626 Instrument 12014 C

'C

-27A Maint.

l EQP 8608 Enable / disable MOV brakes 6621 Rutledge C

C 3

4 6622 i

6665 l

6686 i

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EQP 8609 Replace cable Iv79738 6618 C

N/A ll i

j EQP 8611 JB has weephole in top N/A Auburn N/A C

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EQP 8612 Replace zone switches 6669 N/A C

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Date: 1/3/87 0041E Estimated Date of Completion SCR ho.

Description ECM Eneineer Workplan No. U-l U-2 Comments EQP 8614 Weep holes in Je 6652 C

C EQP 8615 Replace FT-72-13. -34 EQP 86Il Junction box internal wiring Asburn C

C EQP 8618 Relocate are suppression 6795 C

C network EQP 8619 Valve room submerged cables 6808 3/30 2/15 Holding for corrective action detemination.

EQP 8620 Relocate steam generator Instrument Will roll transmitters 1800 level transmitters Maint.

h EQP 8621 Resolve condJits and fittings 6808 3/30 2/15 Holding for corrective action that may be submerged in determination.

Auxiliary Building EQP 8E22 Replace teminal blocks with 2/15 1/30 Workplan is in writing.

spliced cables No longer an issue.

EQP 8623 Replace limit switch on FCV-3, -21 EQP 8624 Junction box 2145 may be a------

No longer an issue.

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c*=arged, unit 1 EQP 8625 6.9-kV nondivisional cables Holding for drawings.

in trained trays

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.l Date: 1/3/97 0041E

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Estimated Date of OcEDietion SCR No.

Description eof Eneinser Workplan 11o. U-1 U-2 Comments WA Rowe surge sg pression 5773 Kimsey 111B3 C

C network for PORV EEB 8523 Penetration overcurrent 6606 Legg C

C N/A Mark FOt to delete 1,

5883 Hall C

C Moed SI-166.

2-PS-3-1604, -1608, -165A, and -1658 WA Replace 1-FT-1-3A, -3B, -104, 6347 Instrument WA C

WA

-108, -21A, -218. -284, -288 Maint.

NEB 8510 Relocate LT-68-320, 6439 Carrasgsillo various C

C PT-68-323. -320 Peters W rit 63-71,68-308 6496 Legg 11865 C

C Replace L5-65-4, -5 6504 Legg 11865 WA C

MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C

Delete brakes FCV-62-61 6521 Branham 11905 C

C EEB 8517 Replace pressure transmitter 6488 Branham 11931 C

C PDT-65-80, -82

-90, and -97 M/A Raychen splice rework Peters Various nets 6/30 3/15 l

O *' w TilIS PAGE INTENTIONALLY LEFT BLANK

TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 January 15, 1987 Nuc1 car Regulatory Commission Of fice of Management Information and Program Control Washington, DC 20555 Centlemen:

SEQUOYAll NUCLEAR PLANT - MONTilLY OPERATING REPORT - DECEMBER 1986 Enclosed is the December 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTil0RITY 19y %C6&

D P. R. Wallace Plant Manager Enclosure cc (Enclosure):

Director, Region II Nucicar Regulatory Commission Of fice of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, coorgia 30323 (1 copy)

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

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

INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 (1 copy)

Mr. K. M. Jenison, Resident NRC Inspector g

O&PS-2, Sequoyah Nuclear Plant An Etpial Opportunity Employer