Text

Monthly Operating Repts for Apr 1987
	ML20237K691
Person / Time
Site:	Sequoyah
Issue date:	04/30/1987
From:	Dupree D, Nobles L; TENNESSEE VALLEY AUTHORITY
To:	; NRC
References
	NUDOCS 8708190371
	Download: ML20237K691 (44)
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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION s

" APRIL 1987" UNIT 1 DOCKET NUMBER 50-327 d

LICENSE NUMBER DPR-77 59' UNIT 2' DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:

L. M. Nobles, Acting Plant Manager 0023f 8708190371B[80 27 PDR ADOCK O PDR R

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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

Special Reports 2

Licensee Events 3-6 Offsite Dose Calculation Manual Changes 7

' II.

Operating Statistics A.

NRC Reports l

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

TVA Reports Nuclear Plant Operating Statistics 14 Unit Outage and Availability 15-16 Reactor Histogram-17 III. Maintenance Summary Electrical Maintenance 18 Instrument Maintenance 19-20 Mechanical Maintenance 21-22 Modifications 23-34 Environmental Qualification 35-41 0288f t.

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1 PERFORMANCE

SUMMARY

April 1987 The following summary describes the significant operational activities for the month of April.

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

The units remained in an administrative shutdown the entire month due to design control review, configuration control updating, and resolution of significant employee concerns.

Outage related maintenance and modifications are being performed.

Unit 1.has been of f-line 616 days.

Unit 2 has been off-line 617 days.

SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 04/01/87 0001E The reactor was in mode 5.

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

04/30/87 2400E The reactor was in mode 5.

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

Unit 2 Date Time Event 04/01/87 0001E The reactor was in mode 5.

The administrative shutdown due to design control review, configuration control updating, and resolution of si aificant 9

employee concerns continues.

04/30/87 2400E The reactor was in mode 5.

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

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

Unit 2 The core average fuel exposure accumulated during April 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 VALVES

SUMMARY

No PORVs or safety valves were challenged in April 1987.

SPECIAL REPORTS ThefollowingspecialreportIassubmittedtotheNRCinApril1987.

87-03 The meteorological instrumentation was declared inoperable on three different occasions on April 9, 1987.

LCO 3.3.3.4 was entered for each occasion. When the LCO was entered for the last event, the plant remained in the LCO until the root cause was determined.

The root cause was determined to be the telephone cable that transmits data from the data collection points.

The cable was repaired and the returned to service on April 27, 1987.

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LICENSEE EVENT REPORT (S)

The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in April 1987.

Description of Event LER l-87017 As a part of'the continued Surveillance Instruction Review Program at Sequoyah Nuclear Plant (SON), it has been determined that the technical instructions that implement SI-51, " Weekly Chemistry Requirements," have been in error with respect to the l

analysis of boron concentrations. More specifically, TI-ll, i

" Chemical Analytical Methods," and TI-16, " Sampling Methods,"

provided for analysis of boron concentrations based on the volume of solution to the volume of solute ratio.

This method fails to recognize that the specific gravity of concentrated boric acid is greater than 1.0.

In actuality, the specific gravity of the boric acid solution is greater tha: 1.0 and is a function of concentration at a particular reference temperature.

This analytical method resulted in the recorded boron concentration being higher than the actual concentration.

This error affects technical specification boron concentration readings for the boric acid storage tank, the boron injection tank, and the refueling water storage tank.

The root cause of this condition has been determined to be a procedural inadequacy to correctly account for the boric acid concentration solutions.

The analytical methods failed to recognize the effect of density changes in the varying borated water concentrations.

The dilution multi' plication factor should have been based on a weight ratio instead of a volume ratio.

1-87018 On March 17, 1987, as a part of a continuing Surveillance Instruction Review Program, it was determined that SI-166.16, "CCS Check Valve Test During Cold Shutdown," is inadequate.

ASME Boiler and Pressure Vessel Code,Section XI, Article IWV-3522, "Tes.ts For Check Valves," states that " Valves that are normally open during plant operation and whose function is to prevent reverse flow shall be tested in a manner that proves that the disk travels to the seat promptly on cessation or reversal of flow." To implement this requirement, SI-166.16 is performed at least once every three months during cold shutdowns to verify that the normally open component cooling water check valves' disks travels to their seat to fulfill the containment isolation function.

The inadequacy of SI-166.16 is in the test method for CCS check valve CV-70-679 (the inboard containment isolation valve on the CCS supply header to the reactor coolant pump thermal barriers).

The present test method may not ensure that adequate pressure is available to close the check valve due to the elevation differences between the two test vent valves.

After verifying no system pressure exists upstream of the check valve, the test directs the opening of a vent valve downstream 0023f.

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i Description of Event (continued)

LER 1-87018 of the check valve and to verify that a steady stream of water (cont.)

flows from the vent valve. This is to ensure that pressure exists to the check valve proving valve closure. However, water i

may flow out of the vent valve but may not produce adequate pressure to close the check valve due to the elevation 1

difference of nineteen feet between the vent valves upstream and downstream of the check valve.

The root cause of this condition has been determined to be a personnel error, in that an inaccurate test method for ensuring proper closing of CV-70-679 was incorporated into SI-166.16.

1-87019 On March 18, 1987, at 1411 EST, Electrical Maintenance personnel were using Surveillance Instruction 307.2, " Degraded Voltage Timer Functional Test For Unit 2," for isolating and testing the degraded voltage (DV) timer. As written, SI-307.2 allowed a grounded AC system to be connected to an ungrounded DC system.

This resulted in tripping the normal feed breakers and a loss of voltage on shutdown board 28-B.

The loss of voltage caused all four diesel generators to start and diesel generator 2B-B to load onto shutdown board 2B-B.

The root cause of the event was an inadequate procedure.

The procedure does not adequately isolate the DV timer contacts for functional testing.

Procedure SI-307.2 and three additional SI procedures that have a similar deficiency will be revised by June 8, 1987, to. include detailed instructions for the functional testing of the DV and load sequencing timers, which will prevent recur,rence of such events.

l-87020 On May 18,1987, a nonconformance report (NCR), SQNCEB8409, was written that described a condition in which class 1E electrical components, such as local control boxes, solenoid valves, and motors have been found unprotected against potential water spray from failure of piping not seismically qualified for pressure boundary integrity. This condition was further stated as not being in confo'rmance with NRC Regulatory Guide 1.29, " Seismic Design Classification," Revision 3, September 1978.

On June 19,1984, a failure evaluation / engineering report on this condition was completed and it concluded that the condition was not acceptable for some design conditions; however, a functional impairment of the component (s) is not likely.

Specific equipment had not been identified on the failure evaluation / engineering report, and no immediate actions were taken.

The above described condition is applicable to both units 1 and 2.

The root cause of this condition has been determined to be a lack of adequate design to ensure that 1E equipment is not interacted with by spillage f rom earthquake-damaged water lines.

The potential for this type of interaction was not adequately addressed from all aspects of the original design.

0023f 7

Description of Event (continued)

LER 2-87005 On March 5, 1987, at approximately 2352 EST, an inadvertent train B containment ventilation isolation occurred on unit 2.

Instrument malfunction alarm RA-90-106B was received in the main control room, and Operations personnel blocked the signals from radiation monitor 2-RM-90-106.

Operations dispatched Chemical Laboratory personnel who found the radiation monitor housing under an unusually high vacuum, and the operator noticed the train B containment isolation valves (FCV-90-108, -109, and

-110) in the sample lines were closed.

At the immediate time of the event, it was not known that a CVI had occurred because of the train B isolation equipment being out of service.

These valves are closed automatically on a train B CVI signal.

However, the train A isolation valves in series that are actuated from train A CVI signal were not closed.

It was noted that no high radiation signals were present from any of the associated radiation monitors, and no safety injection, phase A, or phase B containment isolation signals were present.

Operations personnel tried to reopen the isolation valves, but the valves would not stay open until the CVI signal was reset by handswitch HS-30-65B. At 0035 EST, the valves were reopened and radiation monitor 2-RM-90-106 was returned back to normal service at 0058 EST.

Since the train B valves required resetting of the CVI signal and the train A valves did not close, it is apparent that only a train B CVI signal was present.

The cause of this event has been investigated; however, no specific cause could be determined.

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i ABBREVIATIONS 1.

ABI

- Auxiliary Building Isolation 2.

BAT

- Boric Acid Storage Tank 3.

BIT

- Boron Injection Tank 4.

CCS

- Component Cooling System 5.

CRI

- Control Room Isolation 6.

CVI

- Containment Ventilation Isolation 7.

D/G(s)- Diesel Generator (s) 8.

DCR

- Design Change Request 9.

ECCS - Emergency Core Cooling System 10.

EMI

- Electromagnetic Interference 11.

ERCW - Essential Raw Cooling Water 12.

ESF

- Engineered Safety Feature 13.

FCV

- Flow Control Valve 14.

IMI

- Instrument Maintenance Instruction 15.

LC0

- Limiting Condition for Operation 16.

RCS

- Reactor Coolant' System 17.

RHR

- Residual Heat Removal 18.

RM

- Radiation Monitor (RAD Monitor) 19.

RWST - Refueling Water Storage Tank 20.

S/G(s)- Steam Generator (s)

21. SI

- Surveillance Instruction /or Safety Injection

22. SR

- Surveillance Requirement 23.

SSPS - Solid State Protection System 24.

TI

- Technical Instruction

25. TS

- Technical Specification

26. WP

- Workplan

27. WR

- Work Request 0023f _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _

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0FFSITE~ DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah offsite dose calculation manual during the month.

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OPERATZNG DATA REPORT l

DOCKET NO. 50-327 DATE MAY 5,1987 COMPLETED BY D.C.

DUPREE TELEPHONE (615)870-6722 OPERATING RTATUS 1.

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

REPORT PERIOD: APRIL 1987 3.

LICENSED THERMAL POWER (MWT): 3411.0 4.

NAMEPLATE RATING (GROSS MWE): 1220.6 5.

DESIGN ELECTRICAL RATING (NET MWE): 1148.0 6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0 7.

MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 8.

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

9.

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

10. REASONS FOR RESTRICTIONS,IF ANY:

THIS MONTH YR-TO-DTD CUMULATIVE

11. HOURS IN REPORTING PERIOD 719.00 2879.00 51120.00

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 71

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 25976386.00

18. NET ELECTRICAL. ENERGY GENERATED (MWH)

-3751.00 -15277.00 24887282.00

19. UNIT SERVICE FACTOR O.00 0.00 46.70

20. UNIT AVAILABILITY FACTOR ".

0.00 0. 0 0.

46.70

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 42.41

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 42.41

23. UNIT FORCED OUTAGE RATE 100.00 100.00 41.56

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

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATE DATE OF START-UP: START-UP I UNDETERMINED AT THIS T-IME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTIOii OF SIGNIFICANT EMPLOYEE CONCERNS.

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

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SEQUOYAH NUCLEAR PLANT l-AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : DNE DA7E : MAY~5, 1987 COMPLETED BY :

D. C. DUPREE TELEPHONE :(6153870-5544 MONTH: APRIL.1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL-DAY (MWe Net)-

DAY (MWe Net) 01 0

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DOCKET NO. 50-328 DATE MAY 5,1987 COMPLETED BY D.C.

DUPREE TELEPHONE (615)870-6722 OPERATING STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES 2.

REPORT PERIOD: APRIL 1987 3.

LICENSED THERMAL POWER (MWT): 3411.0 1

4.

NAMEPLATE RATING (GROSS MWE): 1220.6 5.

DESIGN ELECTRICAL RATING (NET MWE): 1148.0 6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0 j

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MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 i

f 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-DTD CUMULATIVE

11. HOURS IN REPORTING PERIOD 719.00 2879.00 43080.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE O.00 0.00 21494.42

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 23536780. O

18. NET ELECTRICAL. ENERGY GENERATED (MWH)

-5614.00 -22285.00 22545238.60

19. UNIT SERVICE FACTOR O.00 0.00 49.89

20. UNIT AVAILABILITY FACTOR 0.00 0.00 49.89 s.

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 45.59

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 45.59

23. UNIT FORCED OUTAGE RATE 100.00 100.00 43.72

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

25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATE DATE OF START-UP: THE STARTUI OF UNIT-2 HAS BEEN SCHEDULED FOR JULY 1987.

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

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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT. TWO DATE : MAY 5,1987 COMPLETED BY :

D. C. DUPREE TELEPHONE :CE15)B70-6599 MONTH: APRIL 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWs Net)

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NUCLEAR PLANT OPERATING STATISTICS

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.,l Period Hours 719' Month April gg 87 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 Enerav Gen, GWD (t)2 0

0 0

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

0 0

E 5

Gross Electrical Gen., MWh 0

0 0

h 6

Station Use, MWh 3,751 5,614 9,365 E

7 Net Electrical Gen., MWh

-3,751

-5,614

-9,365 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

6 11 SGTEG This Month,10 BTU 0

0 0

12 13 Hours Reactor Was Critica!

0.0 0.0 0.0 14 Unit Use, Hours-Min.

0:00 0:00 0:0@

15 Capacity Factor, Pcrcent 0.0 0.0 0.0 16 Turbine Avail. Factor. Percent 0.0 0.0 0.0" 17 Generator Avall. Factor. Percent 0.0 0.0 0.0 ta 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 f

19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 2

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 4"

g 24 Gross Heat Rate, Btu /kWh N/A N/A N/A

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

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y 26 Lu 27 g

28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature. F N/A N/A N/A

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30 Exhaust Pressure, inHg Abs.

N/A N/A N/A g

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 E

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 210.841$

j 39 Oil Fired for Generation, Gallons 5,016 2

40 Oil Heatina Value. Btu /Gai.

138,000 41' DieseJ Generation MWh 76 d7 Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor, %

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

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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Date Submitted Date Revised

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MAINTENANCE

SUMMARY

(MECHANICAL) 9 X

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1

L MECHAN 1 CAL MAINTENANCE MONTHLY REPORT FOR MARCH 1987 COMMON 1.

Continued control building roof repairs.

2.

Continued hanger. bolt tightening deficiency resolution.

3.

Completed the overhaul of "0" station service air compressor.

4.

Began overhauling the "C" station service air compressor.

5.

Completed auxiliary boiler inspections, 6.

Continued planning for replacement of metric valves.

UNIT 1 1.

Completed Grinnell diaphragm valve preventive maintenance.

2.

Completed main generator stator inspection repairs.

3.

Began main-generator rotor zone / retaining ring replacements.

UNIT 2 1.

Continued piping, elbow, and reducer replacements downstream of feedwater regulation valves.

2.

Continued planning replacement of 2-VLV-61-692 under WP12345, 3.

Began repairs on 2-FCV-70-134.

OTHER 1.

Continued suitability evaluations for old Section XI work packages under CAR 87-012.

2.

Continued SI and MI review and rewrites.

3.

Continued FSAR review corr.ective actions for restart.

4.

Continued equipment condition evaluation report actions for restart.

5.

Continued operability interview and PRO review actions for restart.

6.

Continued NMRG, INP0, NPP, and ORR action items for restart.

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C. COMP U. FUNC EYS ADDRESS. DATE... DESCRIPTION............................. CDRRECTIVE ACTION.............

' 0221774 1 LCU 003 0154 @V31/871-LCU-003-0154-A,ENNPRDu),00LTS ARE WDRM PACKING DUE TO WDRME DPERATION.

LODSE THAT lELD ACTUATDA DN VALUE.

INSTALLE NEW PACKING AS LUBRICATED STEM ALSDN PACKING HEDS TD DE CHECKED.

AND TICHTENED BETS ON ACTUATOR.

UALUE DOES NOT DPERATE SMDDTMLY.

PERFORMED SI 146.4 AND RETURNED TO SERVICE IG27150 2 RM M0 0099 04/10/87 2-RM-090-0041, PUMP FRUZEN UP. REPAIR ~ WORN INTERNALS. INSTALLED NEW BEARINGS 1 AS HEEDED. PMT.SI-206.2 IM'S SET DF UANES 8 U-BELT.

S228448 0 ULU 024 1018 04/07/87 0-ULV-024-1018,CK ULV STUCK WILL NUT RESET

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1 MAINTENANCE

SUMMARY

(MODIFICATIONS) 46*

s

t PROJECT OVERVIEW AND SIGNIFICANT ITEMS APRIL 1987 i

Project Overviews Currently the majority.of Modifications efforts are being placed against Operational Maintenance Expense in support of unit 2 restart. work.

Therefore, most major capital projects schedules have slipped to allow manpower to be used to support unit 2 restart.

94 m

6% *

~

SUMMARY

OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS APRIL 1987 M

" L9-*

l 1

.Mnior C2pital Projects:

l*

lHJFI PN7101:

ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan 12223 in process pending safe access to current transformers.

PN7102:

ECNs 5938, 6305, and 6571 - Replace Feedwater Heaters 3 and 4 and Eroded Pipe for Unit 1 and 2

!LDA!

Preparation work is. underway as time and manpower permits.

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

Structural steel reinforcement continues on unit I heaters 3 and 4 This work will be moved out possibly into fiscal year 1988.

PN7105: _ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel

!LDA!

The workplan for the replacement of unit 1 isolation valves was approved. This work was not scheduled to begin until later in the fiscal year.

Some insulation activities remain incomplete.

PN7106:

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 on unit 2.

The workplan for this is in

-the approval cycle.

PN7108:

ECN 6720 - Cratie Consistency Program

!HJFI Unit 2 polar crane modification in process. Unit 1 polar crane to be worked following unit 2.

PN7115:

ECN 6719 - Volumetric Intrusion Detection System lHJFl All fence' sad gate installations are complete. Installation of microwave units and reflectors are complete.

Final alignment in process as well as cable terminations in CAS.

)

Lighting additions being worked.

I i

f.

J

Major Capital Projects (cont.):

PN7122:

DCR 1373 - Secondary Side Steam Generator Preservation ECN 5657 - Installation of MSR Drain Valves Work is essentially complete on all the ECNs.

Some minor l

insulation installation activities are in process. There may be some small changes to complete this project in fiscal year 1987.

PN7123:

ECNs 5938, 6305, 6571 - Replace Feedwater Heaters 1 and 2 Units 1 and 2.

Modifications Group B is supporting postmodification testing

_(PMT) on heaters 1 and 2 on both units as requested.

Insulation work on unit 1 continues.

\\

PN7130:

DCR 1156 - Post Accident Monitoring This work has slipped to allow work to continue on priority unit 2 restart efforts. NRC commitment on NUREG 1.97 calls for unit 1 completion by September 1987 and unit 2 by U2C4.

A request has been sent to the NRC to move the unit 1 completion date to U2C4.

PN7136:

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

PN7152:

ECN 6808 - ExtArnal Conduit Sealing Unit 2 work complete. Unit I workplan in approval cycle.

PN7161:

ECN 5855 - Replacement of Doors A56 and A57 The mecha,nical workplans are approved and work started on door A56. Work on door A57 has been deferred. This project has yet to be authorized.

Electrical workplan approved. Will work in conjunction with mechanical work. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Major Capital Projects (cont.):

PN7159:

Appendix R lLDA!

ECN 6300 - Additional Sprinklers and Draft Stops The installation of the curbs in the shutdown board rooms was completed.

Final flushings and installation are awoiting

)

material delivery.

i

!HJFl ECN 6300 - Sensors and Detectors i

l Installation of detectors is complete.

i l

Installati.on of sensors and detectors in 4807 board room is not a restart item, however, wort is in process and scheduled for completion by the June 30 commitment date.

External conduit sealing in process.

ILDA!

ECN 6311 - Operator Extension on PORV A decision was made to delete final testing; therefore, this item is complete.

!HJFI Functional test held for calibration by Instrument Maintenance.

-PN7181:

DCR 1898 - ECNs 6832 and 6596 - Dry Active Waste Building

!HJFI Interface workplan for potable water and fire protection complete--held for material.

Electrical interface workplan held for sketch from DNE to submit FOR for reduction in conduit bank., Building and JGC workplans in approval cycle.

PN7199:

Miscellaneous Activities Under $100,000 This is for various work orders prepared for work under

$100,000 Total Site Cost.

This work is done as manpower resources are available that will not impact unit 2 restart effort.

l Significant Items:

The following major significant items are under Operation and l

Maintet2nce Expense (0&M) and will continue to be until restart of unit 2.

I 1.

Fuse Program Work.

!HJFl ECN 5880 - Workplan in approval cycle to install suppression

{

networks for unit 2 (3 required).

!HJFI ECN 6854 - Workplan being revised to install 300 VDC fuses.

This ECN supersedes ECN 6749.

I

!HJFI ECN 6890.Workplan approved.

Material being transferred from ECN 5880 to install fuse blocks.

2.

Main Steam Valve Vault Cable and Insulation Work.

All cables have been replaced.

Functional tests are held for delivery of resistors for surge networks.

Completion of functional tests is expected to be May 15, 1987.

!LDA!

E.N 6809 - MSVV Insulation The workplan for insulation-continues in progress. Work is continuing on the resolution of interferences.

3.

Cable Ampacity Program.

thRS!

ECN 6835 - DNE has informed SQN that there are 86 cables that

~

are required to be repulled for unit 2 restart.

DNE has completed all de,awings for unit 2 cables.

Eighty-four of 86 cables have been repulled.

4.

Esychem Cable Splicing Work.

!MRS!

There have.been 915 of 973 splices replaced.

Current completion is scheduled for May 15, 1987.

NOTE:

Financial Planning is in process of transferring funds to cover items 3 and 4.

This will be an increase in O&M expense.

05/0'5/87 0120K/pam t

Other Items:

ECN 5435 - Fire Doors LThe installation of weather stripping continues as resources permit.

lHJF!

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.

!HJFI ECN 5111 - Provide permanent power to manholes 42-46.

Electrical conduit and wiring. installation for manholes 44, 45, and 46 complete per Workplan 12262. Manhole 42 and 43 held for information from DNE on power cable routing and terminations.

!HJFI ECN 5599 2 Conduit' Supports for Fifth Vital Battery and Wsste Disposal Area Workplan 12186 in hold for fifth vital battery area supports.

Information needed from DNE on flex conduits. Workplan for waste disposal area held for issue of ECN by DNE to include FCR 4753.

!HJF!

ECN 5609 - Air Compressors Makeup Water Treatment Plant Electrical drawings received to tie in air compressors. Workplan being written.

!HJF!

ECN 5626 - Containment Ladders Unit 1

~

Workplan. being written to incorporate this ECN.' Need additional design information to complete. '

!LDA!

ECN 5676 - Diesel Generator Air Tank Valves A workplan was written and placed in the approval cycle.

ILDA!

ECN 5713 - Various, Platforms in Lower Containment The remaining trollies have been shipped to the vendor for modification. Work will cont'nue when the trollies are returned.

ILDAl ECN 5743 - Ladders In Containment A workplan to install additional safety gates was approved.

!LDA!

ECN 5779 - MHI Bypass Installation of supports for unit 2 is in progress.

1 Othse Itsms (cont.):

IHJFl ECN 5935 - Correef PsWoc Block Lighting Deficiencies Workplan initiation held for release of drawings by DNE.

ILDA!

ECW 5977 - Steam Generator Blowdown Demin Installation of SGBD tank tie-ins is in progress.

ILDA!. ECN 6005 - Replacement of AFW Air Ejector The workplan was approved and work started.

ILDA!

ECN 6034 - Replacement of ERCW Pump Bearing Piping Resolution of piping dimensional problems is in progress.

IMRS!

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

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

!?!

ECN 6185 - Offsite Paging System

~.

l Functional tests of the remote mobile units remain to be completed.

ILDA!' ECN 6196 - Pressurizer Hansers and Valves Postmodificat' ion testing (PMT) is incomplete and scheduled for startup.

IMRS! ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete.

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

l IMRS!

ECN 6380 - Replacement of Barton Pressure Transmitters

!&LAl

'he unit I workplan is holding for resources.

Unit 2 instruments are stalled but problems have been encountered in calibrating.

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

No new date for release of approved FCRs or drawings by DNE has been established. _ - _ _ _ _ - _ - - _ _

s Othir Itr s (contd.):

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

ECW 6437 - Replace FE-2-265, and 257 The mechanical workplan is completed and electrical work has started.

ECN 6455 - Upgrade CU-3 Box Battery Packs Workplan issued.

Material available and work in process.

ECNs 6491 and 6534 - ERCW Supports All hangers currently identified have been ccmpleted. A documentation workplan incorporating the final ECN 6534 drawings was prepared and placed in the approval cycle.

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 completo. Lack documentation only.

FCR to complete unit I workplan.

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

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

ECN 6631 - Modify Snubbers Work on approximately 20 hangers was transferred from Mechanical Maintenance and is in progress.

ECN 6661 - Upgrade of ERCW Piping Work is in progress on replacing non-conforming piping.

ECN 6689 - Relocation of Main Steam PORV Tube routing details have been transmitted to DNE for evaluation.

j Postmodification tests for unit 2 are held for calibration of positioners by Instrument Maintenance. Unit 1 activity in process of being manned by T&L.

l t

.A r.

Other Items (cont.):

!MRSI ECN 6698 - Repu11'120-Volt Cables Termination of o:x cable remains, f

ILDA!

ECN 6700 - Anchors Near Free Edge The workplan continues in work.

! LDA! - ECN 6701 - Modify Foxboro Recorder Latches Fieldwork is complete.

!LDA! 'ECN 6706 14' Support Enhancement A late addition to the unit 2 scope was received and repairs are in progress._ Ropairs continue on unit 1.

Initial inspections for unit 1 lack approximately 50 supports from completing.

Unit 1 evaluations are i

continuing.

DNE is evaluating contract proposals for unit 1 work.

!MRS!

ECN 6707 - Replace System 74 Flow Switches Switches will have a new setpoint based on another ECN. The installation will be complete after the flow transmitter is removed from the existing workplan.

!?!

ECN 6715 - D/C Random Loads Both trains complete.

Holding for PMT.

IMES!

ECN 6717 - Stub Bus Fuses Workplan is in work. Twenty-three of 26 complete.

!LDA!

ECN 6739 - Alternate Analysis All identified field work is complete.

Documentation review is in progress.

DNE is evaluating contract proposals for unit 1 work.

IMES!

ECN6742-InstallhissesinRadiationMonitorPowerSupplyCircuits Workplan is coaplete for unit 2.

ECN 6746 - Install Fuses Workplan is complete for unit 2.

!LDA!

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

Mechanical fieldwork is complete. Some conduit rerouting remains incomplete.

FCR and/or ECN may be required to resolve.

I a

Other Items (cont.):

ILDA!

ECN 6761 - EVR Blowout Panels Implementation of unit 1 work is progressing as resources are available.

Additional work on a unit 2 EVR door has been identified.

!LDA!

ECN 6762 - Modify Hanger NCR CEB8615 Fieldwork is complete.

!MRS!

ECN 6768 - Rework Cable Tray Hangers Workplan is in work.

IMRS!

ECN 6783 - Replace Motor on 2-MOV-70-87 This ECN is superseded by ECN 6858.

Regear is complete.

Valve will not pass leak test.

ILDA!

ECN 6787 - Inspection and Replacement of Solenoid Valve Supports Fieldwork is complete.

Final postmodification testing was completed.

ILDAl ECN 6790 - Medium Energy Pipe Break The spare penetrations have been sealed.

Work has not started on others.

!LDAl ECN 6791 - Pipe Clamp Replacement The workplan continues'in work.

a.

!LDA!

ECN 6802 - Modify EGTS Filter Housing Work continues.

Completion is on hold due to postmodification testing problems.

lHJFl ECN 6808 - Conduit External Sealing

~

The workplan for conduit sealing is complete for unit 2.

IMES!

ECN 6810 - Rework Category "C" Devices First workplan is complete; second workplan lacks installation of two pressure switches.

!HJFI ECN 6812 - Backup Control Room Cable Reroute Work is in complete. Workplan closure held for loop test by Instrument l

Maintenance.

I l

l 1

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Other Items (cont.):

J ILDA!

ECW 6827

,MELB Plugging Drains for Control Building A workplan was approved. Work is delayed for receipt of brazing rods.

!LDA!

ECN 6848 - Thermal Expansion Problems With Platforms I

Work continues in progress in #4 accumulator room, incore room, and RCD i

platforms.

i ILDA!

ECN 6851 - Thermal Expansion Problems With Hangers Fieldwork was started.

Completion held due to problems with HP and DNE (hanger located in high. radiation area).

!LDA!

ECN 6866 - Modification of Vrive Room Doors The mecha'nical workplan was written and placed in the approval cycle.

The electrical workplan is being prepared.

!HJF!

ECN 6871 - External Conduit Sealing DGB/CB/ERCW Workplan preparation in process.

!HJF1 ECN 6874 - CVCS Heat Trace Power Circuits

{

Workplan approved. Work in process.

I

!HJFI ECN 6878 - Repince PS and TS SYS 32 l

Workplan approved. Work held for bolting material.

ILDA!

ECN 6879 - Reinforcing EIpe Lateral Field work was completed.

ILDA!

ECN 6893 - Install New Air Regulators i

Workplan preparation has begun.

!LDA!

ECN 6899 - Seismic Supports Of Exhaust Hood The workplan was prepared and placed in the approval cycle.

ILDA!

ECN 7000 - Addition of Support to Main Steam Dunp Header Fieldwork is complete except final inspections during heat up.

ILDA!

ECN 7078 - Install Hangers - Main Steam Piping Mechanical work was completed.

Re-insulation is in progress.

t

n Oth9r Items (cont.):

ILDA!

ECN 7089 - ERCW Check Valve Replacement A workplan was written and placed in the approval cycle.

ILDA!

ECN 7095 - Sleeve Installation On Shield Building Preliminary coordination with DNE was started.

!LDAl ECN 7102 - Control Air Line Plugging A workplan was written and placed in the approval cycle.

ILDA!

ECN 7110 -' Relocate AFW Controllers

)

Preliminary work has begun with DNE.

ILDA!

ECN 7137 2 Calculation Review Hangers A workplan for 15 hangers was written and placed in the approval cycle. More supports are expected.

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

Workplan 12208 written, but held for design drawings.

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

lHJFl Control Room Bullet Resistivity - DCR 2268 - ECW 6860 Boundary redefined.

HeId'for decision on if new DCR and ECN are required.

Startup Activities List SAL Closure - Many manhours spent closing these items.

Appendix A - Inte' nil Conduit Sealing

!HJFI e

Work in progress.

Scheduled to complete June 30, 1987.

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s ENVIRONMENTAL QUALIFICATION (E.Q.)

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l THIS PAGE INTENTIONALLY LEFT BLANK a

e,

W e-0023f

._ ____ _ ~

/

d 3

TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant o

0 P. O. Box 2000 Soddy-Daisy, Tennessee 37379 May 15, 1987 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - APRIL 1987 Enclosed is the April 1987 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Nobles Plant Manager Enclosure cc (Enclosure):

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

Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 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) eI Mr. K. M. Jenison, Resident NRC Inspector 0&PS-2, Sequoyah Nuclect Plant

{

}

An Equal Opportunity Employer L._

ML20237K691

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