Text

Monthly Operating Repts for Mar 1987
	ML20237K701
Person / Time
Site:	Sequoyah
Issue date:	03/31/1987
From:	Dupree D, Nobles L; TENNESSEE VALLEY AUTHORITY
To:	; NRC
References
	NUDOCS 8708190375
	Download: ML20237K701 (48)
	v • d • e

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'i TENNESSEE VALLEY' AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION

" MARCH 1987" a

UNIT 1 DOCKET NUMBER 50-327' LICENSE NUMBER DPR-77 UNIT-2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:

L. M. Nobles, Acting Plant Manager 8708190375 870331 _

b DR ADOCK 0500

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TABLE OF C0). TENTS Page 1

I.

porational Summary Performance Summary 1

Significant Ope' ational Events 2

Fuel Performance and Spent Fuel Storage Capabilities 2

PORVs anti Safety Valves Summary 2

Special Reports 2-3 Licensee Events 4-6 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 14-15 Unit Outage and Availability 16-17 Reactor Histogram 18 III. Maintenance Summary Electrical Maintenance 19 Instrument Maintenance 20-22 Mechanical Maintenance 23-25 Modifications 26-36 Environmental Qualification 37-43 f

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.e OPERATIONAL

SUMMARY

4 PERFORMANCE

SUMMARY

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

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 off-line 586 days.

Unit 2 has been off-line 587 days.

ll SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event __

03/01/87 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.

03/31/87 2400E The reactor was in mode 5.

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

Unit 2 Date Time Event 03/01/87 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.

03/31/87 2400E The reactor was in mode 5.

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

4

~

-FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during March 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 March was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /hTV.

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 March 1987.

SPECIAL REPORTS The following special reports were submitted to the NRC in March 1987.

86-08 A firewatch was missed due to the central alarm station not Rev. 1 functioning.

(This is a safeguard item.)

Comments:

A sign will be painted to indicate the position of the transfer switch if power is temporarily removed.

See the NRC report for the month of December 1986 for initial data.

87-01 Fire door A-57, the auxiliary building to the service building Event 1 passage door on elevation 690, exceeded the'seven-day fire breach permit.

This was due to management's decision to attempt to reduce wear on the door and facilitate access of personnel and equipment.

The door will be restored to functional status prior to mode 4.

2

4

.X 87-01 Fire door A-92, Unit 2 auxiliary building pipe chase door, was Event 2 found inoperable due to a broken mechanism and LCO 3.7.12 was immediately entered on February 6,1987. A fire breach permit was initiated.

Due to planning difficulties, repairs were not completed within the designated time.

This was a personnel error. The assistant shift engineer responsible for writing the fire breach permit was counseled.

Door A-92 was restored to functional status on February 14, 1987.

These events were detcrmined on february 13, 1987.

87-02 Fire door A-216. fifth vital battery room door, was not restored to functional status within the~seven-day requirement. The door was breached to establish room ventilation.

It was determined that inadvertent failure of either_of the two tornado damper control handswitches could cause total isolation of the battery room and would disable the redundant control building pressurization systems when the. tornado dampers close.

Immediate action was taken to open the breakers of the switches to fail the dampers "as is" in their open positions.

Subsequent to.this action, the fifth vital battery room tornado dampers failed closed because their actuators are air-operated.

The other dampers are motor-driven. To prevent hydrogen buildup, door A-216 was opened using the breaching permit. A design change will be initiated to modify the fifth vita battery room tornado dampers' controls.

This will allow the door to be returned to functional status.

This event was determined on February 25, 1987. See LER 50-327/86057.

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c LICENSEE EVENT REPORT (S)

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

l LER Description of Event 1-84070 During a weekly surveillance of containment isolation valves, Rev. 1 7-FCV-61-110 and -122 f ailed to stroke correctly.

These are inboard and outboard containment isolation valves for the ice condenser glycol system.

Both valves were open providing glycol to the ice condenser.

The valves were declared inoperable and the unit entered LC0 3.0.3.

The operator took immediate action to close one of the valves.

An investigation revealed a buildup of sediment on the stems of the valves.

The sediment buildup was determined to be a dried lubricant substance. The valves.

were cleaned and returned to service.

This was an isolated case.

1-87010 This revision includes other components that have not been Rev. 1 calibrated and were not covered by LER l-87010 (February 1987 Report).

On February 20, 1987, it was determined that several undervoltage relays, overvoltage-relays, and meters were identified as not being routinely calibrated.

These items were discovered during a Quality Assurance audit.

The components were not identified by any procedure to require routine calibration.

This was due to lack of clearly defined departmental responsibilities.

All items necessary for restart will be calibrated prior to the respective unit's restart and procedures will be revised to incorporate all components.

1-87013 On February 1, 1987, a reactor coolant system (RCS) spillage occurred on unit 1 as a result of a procedural inadequacy.

The RCS has been drained down to allow U-bend heat treatment on the steam generator (S/G) U-tubes with the primary side manways off.

Operations received a work package to stroke time test valve 1-FCV-63-1.

Operations recognized that the SI was inadequate for the given plant configuration and attempted to supplement the SI by isolating the refueling water storage tank (RWST) f roin the RCS.

This isolation was incomplete and when the valve was stroked, approximately 6,000 gallons of water flowed by gravity into the RCS and approximately 3,000 gallons flowed from the open SG manways onto the floor of the lower compartment.

1-87014 During a review of SI-16 " BIT Heat Tracing," it was determined that the BIT heaters were not verified operable every thirty-one days as required by TSSR 4.5.4.2.a.

This is a procedure error in which the BIT was not considered as part of " heat tracing".

SI-16 will be revised to include the BIT prior to unit 2 restart.

This event was determined February 17, 1987. - - - -

LER Description of Event i

l-87015 On February 24, 1987, the Reactor Engineering Section was notified by Westinghouse that a discrepancy existed between the Point Xenon model and the 3-D Xenon model.

This discrepany could result in the Xenon worth data supplied by Westinghouse for the units being nonconservative for use in shutdown margin calculation as much as 600 pcm (percent millirho).

The condition is assumed to be inadequate validation by Westinghouse of the Point Xenon model.

Long-term corrective action has not been finalized and will be dependent upon Westinghouse recommendations.

1-87016 On February 22, 1987, at 1024E, an inadvertent diesel generator start occurred, resulting in 16-B loading to the system. While test personnel were performing a functional test on ERCW feeder breaker, the technician mistakenly connected the test jumper across the wrong test block.

This resulted in loss of voltage on 6900 volt shutdown board 18-B.

This is a personnel error.

The instruction will be revised to change the sequence of steps for verification, and personnel have been counseled about i

following instructions.

2-83097 One containment sump level high channel (2-L1-63-176) was Rev. 2 declared inoperable and the unit entered LC0 3.3.2.

Initial investigation showed that the possibility existed of an air bubble in the reference leg of the transmitter.

This revision to the LER establishes the following commitments.

Instrument Maintenance will install double 0-ring transmitters prior to unit 1 restart.

The new transmitters will be installed on unit 2 before the end of the next refueling outage (U2C3).

2-87004 On February 20, 1987, it was discovered that one of the cables in electrical penetration 36 did not have redladant overcurrent protection.

The deficiency was found during a walkdown for fuse verification.

Cable 2-RM-80 that was connected directly to circuit breaker "12" should have been terminated to the load side of fuse 2-FU2-90-60B with a cable connecting the output of circuit breaker "12" with the supply side of the fuse. This event was caused by personnel error during plant construction.

The electrician failed to connect the fuse into the circuit.

This condition has been corrected and no further action is required. The circuit breaker / fuse combination for all penetrations has been verified as correct. _ _ _ _ _ _ _ _ _

E ABBREVIATIONS 1.

RM

- Radiation Monitor (RAD Monitor) 2.

LCO. - Limiting Condition for Operation 3..

S/G(s)- Steam Generator (s) 4.

ESF.

- Engineered Safety Feature 5.

'IMI

- Instrument Maintenance Instruction 6.

SSPS - Solid State Protection System 7.

ERCW - Essential Raw Cooling Water 8.

DCR

- Design-Change Request 9.

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

10. TS

- Technical' Specification 11.

SR

- Surveillance Requirement Surveillance Instruction /or Safety Injection

12. SI 13.

CVI

- Containment-Ventilation Isolation

14. WP

- Workplan

15. CRI

- Control Room Isolation

16. ABI

- Auxiliary Building Isolation

17. WR

- Work Request 18.

EMI

. Electromagnetic Interference 19.

ECCS - Emergency Core Cooling System 20.

RHR

- Residual Heat Removal 21.

RCS

- Reactor Coolant System

22. TI

- Technical Instruction 23.

BIT

- Boron Injection Tank 24.

FCV

- Flow Control Valve 25.

RWST - Refueling Water Storage Tank I

l 1

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

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S 4

0 OPERATING STATISTICS (NRC REPORTS)

~

OPERATING DATA REPORT DOCKET NO. 50-327 DATE APRIL 10,1987 COMPLETED DY D.C.DUPREE TELEPHONE ( 615 ) B70-6544 OPERnTING STATUS 1.

UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1

NOTES:

2.

REPORT PERIOD: MARCH 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 DEPENDADLE CAPACITY (GROSS MWE):

1183.0 7.

MAXIMUM DEPENDADLE 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 2160.00 50401.00

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

13. R EACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENER ATOR ON-LINE O.00 0.00 23571.13

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)

C. 00 0.00 25976386.00

18. NET ELECTRICAL ENERGY GENERATED (MWH)

-4595.00

-11526.00 24091033.00

19. UNIT SERVICE FACTOR O.00 0.00 47.36

20. UNIT AVAILABILITY FACTOR O.00 0.00 47.36

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 43.02

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 43.02

23. UNIT FORCED OUTAGE RATE 100.00 100.00 40.51

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

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

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

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

CUMUL ATIVE VALUES HAVE DEEN UPDATED.

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'SEQUOYAH NUCLEAR: PLANT AVERAGE DAILY POWER LEVEL i

DOCKET NO. : '50-327 j

UNIT: DNE DATE : APRIL:5,.1987 COMPLETED BY :

D. C. DUPREE-TELEPHONE :(6153870-8599-MONTH: MARCH 1987 AVERAGE' DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL'

DAY (f1We Net)

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(f1We Net)

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.g OPERATING DATA REPORT DOCKET NO. 50-328 DATE APRIL 10,1987 COMPLETED DY D.C.DUPREE TELEPHONE (615)870-6544 OPERATING STATUS 1.

UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 2

NOTES:

2.

REPORT PERIOD: MARCH 1987 3.

LICENSED THERMAL POWER (MWT):

3411.0 4.

NAMEPLATE RATING (GROSS MWE):

1220.6 5.

DESION 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:

f THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 2160.00 42361.00

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

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

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

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

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

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 23536780.00 i

18. NET ELECTRICAL ENERGY GENERATED (MWH)

-4604.00

-16671.00 22550852.60

19. UNIT SERVICE FACTOR O.00 0.00 50.74

20. UNIT AVAILABILITY FACTOR O. OO O. C 0 50.74

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 46.37

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 46.37

23. UNIT FORCED OUTAGE RATE 100.00 100.00 42.64 l

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

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

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

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

t SEQUOYAH NUCLEAR PLANT AVERAGE DAILY ~ POWER LEVEL 1

DOCKET NO. : 50-328 UNIT : TWO DATE : APRIL 5, 1987 COMPLETED BY :.D. C. DUPREE TELEPHONE :CB15)870-6549 MONTH: MARCH 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CHWe Net)

DAY (MWe Net)

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i OPERATING STATISTICS (TVA REPORTS)

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M n82A tDNM 80 NUCLEAR PLANT OPERATING STATISTICS Sequoyah Nuclear Plant Period Hours 744 Month March 19 87 ftem )

No.

Unit No.

UNIT ONE UNIT TWO PLANT 1

Average Hourly Gross Load. kW 0

0 0

l 2

Maximum Hour Net Generation. MWh 0

0 0

3 Core Thermal Energy Gen GWD (t)2 0

0 0

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

0 0

E 5

Gross Electrical Gen., MWh 0

0 0

5 6

Station Use, MWh 4.595 4.604 9,199 h

7 Net Electrical Gen., MWh

-4,595

-4,604

-9,199 5

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

Accum. Core Avg. Exposure, MWD / Ton 1 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 Reactur W.s Critical 0.0 0.0 0.0 0:00 0:00

'0:00 14 Unit Use, Hours-Min.

15

Cap, y Factor, Percent 0.0 0.0 0.0 R

16 Turbine Avail. Factor, Percent 0.0

~

0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 e

18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 f

19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 0

20 Unit Avail Factor. Percent 0.0 0.0 0.0 21 Turbine Startups 0

0 0

22 Reactor Cold Startuos 0

0 0

) 3 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

5 26 U

27 y

28 Throttle Pressure, psig N/A N/A N/A 29 Thrc p** Temperature *F N/A N/A N/A y

30 Exhaust Pressure, inHg Abs.

N/A N/A N/A E

31 Intake Water Temp., F N/A N/A N/A H

32

_Z3 Main Feedwater, M lb/hr N/A N/A N/A 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, Gallons 2,376 2

40 Oil Heatina Value. Blu/ Gal, 138,000 41 Diesel Generation. MWh 36 49 Max. Hour Net den.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor, %

3 13 N/A N/A N/A N/A N/A N/A Remarks: A For DFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.

j 2(t) indicates Thermal Energy. _

3 m

Date Submitted Date Revised O

.14-Plant Superintendent

i' l

D TVA 7382A (DNP4 81)

.dCLEAR PLANT OPERATING STATISTICS

~

Sequoyah Nucicar Plar t Period Hours 672 Month February 19 87 Item No.

Unit No.-

UNIT ONE UNIT TWO PLANT 1

Averaae Hourly Gross Loarf. kW 2

Maximum Hour Net Generation. MWh 3

Core Thermal Energy Gen. GWD (t)2 4

Steam Gen. Thermal Energy Gen., GWD (t)2 8

5 Gross Electrical Gen., MWh j

6 Station Use, MWh l'

7 Net Electrical Gyn., MWh

{

8 Station Use, Percent j

9 Accum. Core Avg. Exposure, MWD /Tonl

{

6 10 CTEG This Month,10 Blu l

11 SGTEG This Month,106 BTU I

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

15 Capacity Factor, Percent 16 Turbine Avail. Factor, Percent j

17 Generator Avail. Factor. Percent

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g e

18 Turbooen. Avail. Factor. Percent f

19 Reactor Avail. Factor. Percent E

20 Unit Avail. Factor. Percent 21 Turbine Startuns 22 Reactor Cold Startuos 23 g

24 Gross Heat Rate, Btu /kWh 25 Net Heat Rate, Stu/kWh 26 E

27 g

28 Throttle Pressure, psig 29 Throttle Temperature. *F

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30 Exhaust Pressure, inHg Abs.

E 31 Intake Wcter Temp., "E F

32 33 Main Feedwater, M lb/br i

34

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35 36 37 Full Power Capacity, EFPD

}

38 Accum. Cycle Full Power Days, EFPD j

39 Oil Fired for Generation, Gallons 2

40 Oil Heatino Value. Blu/ Gal.

2.574 l 'IR. 000 41 Diesef Generation. MWh 49 Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor, %

3 43 IFor BFNP this valJe is MWD /STU and for SQNP and WBNP this value is MWD /MTU.

o Remarks:

g 2(t) indicates Thermal Energy.

E Items 39 and 40 revised for February 1987.

m R* t 5 IOO7 Date Revised C

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(ELECTRICAL) a-_______

-ELECTRICAL MAINTENAN:E MDNTHLY !UMMARY 04 02-87.

PAGE 1 COMP-

, MR. COMP U FUNC SYS ADIRESS. C ATE.... I ESCRIPT ION............................. COEEECTIVE ACTI 0N.......................

1 A322142 1 FCV 067 04 MA 01/20/87 1-FCV-067-04??A-P:VLV V3N'T ODER FROM POSSIPLY, THE MOTOR (1-MTRD-067-0490A-?)

LOCAL PUSH PUTTON 1 HS 67 4909 ON JB UAS EURNED UP-. RFPLACED M2T:R AND 3244 EEN P9TTON IS PUSNED CONTROL FUR FETURNED TO SERVICE. FR A-522142,.

FUSE !H COMP.5E OF 1FP ERCW MCC PLOUS P130427 1 IGN' 26S 0154 01/09/87 1-ION-269-0154-A.[*NPRDt], REPLACE OR THE riYDROEEN IGNITOR DID NOT MEET REPAIR TJEFECTIVE IGNITER CIRCUIT 2A ACCEPTABLE SURVEILLANCE CRITERIA FPEAKER AX 2 EL 785 LOW TEMP FEADIUS IS POSSIPLY LUE TO NCRMAL WEAR CF THE MC PER SI 305.1 COMPLETICN " ATE S-15 IGNITOR ELEMENT. PEftACED 10NITCR ELEMENT AND RAY-CHEM SLEEVE. UR B-130427.

B202S39 2 MV0P 070 00 d 11/21/86 c MV0f 070-0014-?,ttN$R!tJrTCRDUE SUITCH OFEN AND CLCSE TOROUE SWITCH WAS OUT OF IS STO: FIN 3 VLV MOVEMENT ALM 3ST ADJUSTMENT. ADJUSTED CPEN AND CLOSED IMMEDIATELY AFTER VLV STA;TS TO M3VE IN TOROUE SWITCH. WR P-202S39.

THE OPEN POSITICN B216646 1 IS 061 0194 /2 02/09/S7 1-2S-061-0194 /2-3,:tNPRD G REPAIR AS ICE BUILDUP APOUND THE VALVE STEM P"$HED NEEDED FOR LIGHT TO IN?!CATE PRCPER LIMIT SUITCH ARM OPEN CAUSING RED

$0SITION INDICATOR LIDHT TO TUEN OFF. CLEAPED ICE FROM AROUND VALVE STEM. UR P-?16646.

.P216647 1 2S 061 0192 /2 02/09/07 1-25-061-0192 /2-f,ItNPR!t],EEPAIR AS ICE FUILDUP AROUND THE VALVE STEM PUSWED NEEDED TO GET LIGHTS TD INDICATE THE LIMIT SWITCH ARM CFEN CAUSING PED POSITION OF VLVS INDICATOR LIGHT TO TURN DFF. CLEARED ICE BUILDUP FRCM AROUND VALVE STEM. WR

!-216647.

B218959 1 GENB 082 0001P 01/23/S7 1-GENP-032-000!P-?,[tNPRDt]rVOLTA3E THE AMPLIFIER MODULE WAS PAD POSSIPLY CAUSING SUINGING FROM 4-2 MU W/NO ONE DUE TO NOFMAL WEAR. REPLACED 2301 CONTCOLLIN3 E'JITCHINGS DUE!N3 SI 102 AMPLIFIER MODULE. CLEANED CONNECT 0PS ON PERFORMANCE ADJUET OF FIM AS NECEESARY POTH ENGINES. ADJUSTED rROCP SETTING POTENTI0 METER TO DECREASE LCADING TIME.

UR B-218959.

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i MAINTENANCE

SUMMARY

(MECHANICAL)

b MECHANICAL MAINTENANCE MONTHLY REPGRT FOR MARCH _.1987 COMMON 1.

Continued control building roof repairs.

2.

Continued hanger bolt tightening deficiency resolutions.

3.

Began disassembly and inspection of "D"

station service air compressor.

4.

Completed disassembly of two spare contaminated charging pump elements for decontamination and repair by manufacturer.

5.

Completed repairs to the eroded section of the 24-inch ERCW header.

6.

Installed crank case pressure detector baffles on the diesel engines.

7.

Made preparations for isolating one auxiliary boiler from the other for inspections and repairs while the other one is operating.

8.

Completed repairs to fire door A10 in accordance with NRC commitments.

9.

Discovered problems with the original installation of the metrix valves and began work with DNE to resolve.

UNIT 1 1.

Began preventive inspections and parts replacements of rritical Grinnell diaphragm valves.

2.

Continued the main generator inspection.

Replace two stator bars.

3.

Completed repairs on 1-PCV-68-340A.

4.

Completed closing the steam generators and torquing the manways.

UNIT 2 1.

Began replacement of eroded 16-inch elbows and 16-inch by 18-inch reducers with stainless steel elbows and reducers downstream of the feedwater regulating valves.

2.

Completed replacement of the eroded bell reducer with a stainless steel reducer downstream of the feedpump recirculation control valves.

3.

Completed shaft replacement in 2A-A and 18-B boric acid transfer pumps.

4.

Replaced the leaking lube oil cooler on 2A condensate booster pump. --_____-___ - _-_ __. ___-

UNIT 2 (continued) 5.

Continued planning repairs for 2-VLV-61-692.

6.

Continued hanger bolt tightening effort.

7.

Completed tubing / fitting modification on 28-B centrifugal charging pump seal component cooling supply.

8.

Continued work on the installation of a new pump in the H2 analyzer.

ENGINEERING 1.

Began work on approximately 90 Section XI packages as a result of CAR 87-012.

2.

Attended PMT training a POTC.

Attended welding procedure selection training at POTC.

4.

Continued SI reviews / rewrites.

5.

Continued procedure upgraaes.

6.

Continued FSAR review for corrective actions required for restart.

7.

Continued equipment condition evaluation report actions for restart.

8.

Continued operability interview and PRO review for actions required for restart.

9.

Continued NMRG, INPO, Nuclear Plant Performance, and Operational Readiness Reviews for action items required for restart.

?

.~_

CDMP MR.CDMP U FUNC SYS ADDRESS. DATE... DEECRIPTIDN...

. CDRRECTIVE ACTIDN..

0119632 1 ULY 047 05808 07/10/861-ULV-047-05800-B,[CHPRDn3,ULU 1 YLV 67 5808 DDES NDT BACKSEAT PRCPERLY P126974 2 VLY 001 0819 02/13/87 2-ULU-001-0819-3,RY CAN CHLY BE TURNED WDRH INTERNALS. I2 STALLED NEW STEM i

APPRDX 3A DF DHE TURN LY HAND ASSEMBLY PACTING AND DIAPHRACM B124977 2 ULY 001 0816 02/13/87 2-ULV-001-0814-S,ULU CAN DHLY BE TURNED WDRH INTERNALS. INSTALLED HEW STEM l

APPRDX 1/4 DF DHE TURN BY HAND ASEMBLY PACKING AND DITHRAGM l B126978 2 RV 001 0818 02/13/87 2-ULY-$01-0818-$,ULU CAN DHLY BE TURNED WDRH INTERBHANALS. INSTALLED NEW STEM APPRDX 3A Of DHE TURN BY HAND ASSEMBLY DIA?HRAGM AND PACKING.

8127885 2 PMP 062 0232 02/05/87 2-PMP-062-0232-B,2BB 00RIC ACID TRANSTER PUMP HAS INEDARD MECH SEAL LEAK. REPAIR AS SEEN HECESSARY B200043 1 PMP 047 0460 02/16/871-FMP-067-0460,[KNPRM,CA ERCW PUMP IMPELLER CLEARANCE DUT OF ADJUSTMENT DUE FAILED SI 45.1 DN LOW D/P TO HURMAL DPERATIDN. ADJUSTED IMPELLER CLEARANCE PERfDRMED SI-45.1 AND RETURNED TD SERVICE B201039 2 MUDP 003 0087 02/1d/87 2-MVDP-N3-0087-A,En10CFR50.49u1CDRRECT CDRRECTED INADEQUATE N'T ENCACEMENT DH J

INADEQurr;E HUT ENGAGEMENT DN LITTDRQUE LIFIT[R9UE DPERATOR HDLDDDWN BDLTING DPERATDR HDLDDDWH BDLTINC B202930 0 CMP 077 0105 02/18/87 0-CMP-077-0105-A,CDMPRESSDR RUNS BUT WDRH CDMPRESSDR. REBUILT COMPRESSDR DDES NOT MDUE AIR DR BUILD PRESSURE B211481 2 PMP 042 0182 02/14/812-PMP-062-0182,CDUPLING APPEARS TD BE WDRN PUMP. INSTELED NEW PUMP BRDKE REPAIR DR REPLACE AS NECESSfRY B218774 2 VLU 062 1072A 02/18/87 2-ULU-062-1072A,UALUE IS LEAKING WATER NDRMAL WEAR. INSTALLED NEW BONNET DUT Of THE BONNET ASSEMBLY.

B218777 2 ULY 062 1072B 02/16/87 2-ULU-062-1072B,ULV IS LEAKING WATER NDRMAL WEAR. INSTALLED NEW BDNNET.

DUT Of THE BDHNET B222604 2 CENB 082 000208 03/12/87 2-CENB-082-M02DB,PDLISH THE CILLECIDR N/A. PDLISHED CULLECTDR RINGS TO REMDUE RDHCS REQ'D TO REMDUE SPDTS SPDTS B207113 2 WV 002 0572 02/19/87 2-ULY-002-0572,[ENPRDu],REWDRK HANDLE INSTALLED HEW SPkING, CHECKED DPERATIDH DN ULU AND REPLACE SPRING SD THAT THE AND RETURNED TO SERUICE ULU WILL STAY DPEN TFE VLU IS STAYING IN THE THRDTTLED PDSITIDH B215471 2 ULU 002 0575 03/03/87 2-ULU-002-0573,[ANPRDm3,ULY 2-002-575 DIRTY SEATING SURFACE. CLEANED SEATING LEAKS THRU CAUSING MDISTURE DAMAGE TD SURTACE CHECKED FDR LEAKS AND RETURNED FILTERS TD SERVICE A215473 2 ULO 002 0574 03/03/87 2-EU-002-0574,ExNPRDn3,ULU 2-2-574 INSTALLED NEW SEAL, D-RING AND CASKETS LEAKS THRU CAUSING MDISTURE DAMACE TD AND CLEANED UALUE. CHECKED FDR LEAKS FILTERS AND RETURNED TD SERVICE.

i B214624 1 LCV 002 0009 03/01/871-LCU-002-0009,[NNPRDu3,THIS LIC VLU ADJUSTED UALVE STRDKE AND INSTALLED HEW

{

LEAKS THRU WITH THE LIC IN THE CLDSED SDFT SEAT. CHECKED FOR LEAKS AND l

POSITIDH RETURNED TO SERVICE.

9 h

l 1

I i

i l

SUMMARY

OF WORK COMPLETED l

MODIFICATIONS - CURRENT STATUS 1

i MARCH 1987 I

i I

'l

)

I i

)

i 1

l l

1 l

'l I

l l

4 l

l

4'

+,.

Major Capital Projects:

PN7101:

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

l PN7102:

ECNs 5938, 6305, and 6571 - Replace Feedwater Heaters 3 and 4 and Eroded Pipe for Unit 1 and 2 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 1 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 The workplan for the replacement of unit 1 isolation valves was. approved.

This work was not scheduled to begin until l

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 t.o furnish inspection requirements' i

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.

PN7107:

ECN 6687 - Additional Office and Medical Facility Work is complete.

PN7108:

ECN 6720 - Crane Consistency Program Drawings received for modification to unit 2 polar crane and workplan in approval cycle. Remaining crane modifications pending drawing issue.

PN7115:

ECN 6719 - Volumetric Intrusion Detection System All fence and gate installations are complete.

Installation of microwave units and reflectors are complete.

Conduit rework to meet cable pull requirements are in process.

Cable pulls and terminations are in process.

1 I

I _ _ _ _ _ _.

\\

l

=

Major Capital Projects (cont. ):

PN7122:

DCR 1373 - Secondary Side l

Steam Generator Preservation 1

ECN 5657 - Installation of MSR Drain Valves Work is essentially complete on all the ECNs.

Some minor 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 - External Conduit Sealing Work in process.

Scheduled to complete April 3, 1987.

PN7155:

ECN 6687 - South Central Bell Environmental Unit (SCBEU)

Complete except for final drawing correction by DNE.

PN7161:

ECN 5855 - Replacement of Doors A56 and A57 The mechanical workplans are in the review cycle and engineering is trying to get door A56 exempt from the CSSC list.

This project has yet to be authorized. _ __ _-_. _ _ _

L, Major Capital Projects (cont.):

PN7172:

Appendix R - Phase II ECN 6300.- Additional Sprinklers and Draft Stops The draft stop workplan is field complete.

ECN 6300 - Sensors and Detectors Installation of detectors !s complete.

Installation of sensors and detectors'in 480V board room is not a start-up item, however, work is in process and scheduled for completion by the June 30 commitment date.

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

ECN 6319 - High-Pressure Fire Protection Rewort' Fieldwork is complete.

PN7181:

DCR 1898 - ECNs 6832 and 6596 - Dry Active Waste Building Interface workplan for potable water complete--held for material.

Fire protection interface workplan is la approval cycle.

Electrical interface workplan held for drawing release. Workplan issue for remaining portion of building under ECN 6596 held for release of final drawinge.

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.

I

. j J

1 Significant Items:

The following major significant items are under Operation and Maintenance Expense (0&M) and will continue to be until restart of unit 2.

1.

Fuse Program Work.

KAZ actuator replacement by using FLAS-5, Littlefuse is now 99 percent complete.

Only stroke testing of containment isolation valves remains incomplete.

s ECN 5880 - UNID Tags for Class 1E Fuses Field verification of Class 1E fuses and penetration cable

{

protection is approximately 98 percent complete.

Thirteen fuse blocks required to be replaced. Workplan is in approval cycle.

2.

Main Steam Valve Vault Cable and Insulation Work.

All cable has been pulled out and conduit swabbing has been completed on those conduits that will be reused.

Conduit rework commenced January 13, 1987 and completion of termination / functional tests will be February 26, 1987.

ECN 6808 - Conduit External Sealing The workplan for conduit sealing continues in progress.

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

3.

Cable Ampacity Program.

DNE has informed SQN that there are 76 cables that are required to be repulled for unit 2 restart.

DNE has completed all drawings for unit 2 cables.

ECN 6835 - Ampacity Twelve of 87 cables for unit 2 are complete.

There are 47 others in work.

4.

Raychem Cable Splicing Work.

There have been 732 of 963 splices replaced.

Current completion is scheduled for April 8, 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.

04/08/87 PAM 0120K -

L Other Items:

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

ECN 5111 - Resove Power From Old Carpenter Shop at Dry Active Waste Building Modifications Group C is holding the completion of this ECN until'the.

completion of the Dry Active Waste Building. Power is needed.for construction power.

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

Electrical conduit and wiring installation for manholes 44, 45, and 46. complete per Workplan 17262.

Manhole 42 and 43 held for information from DNE on power cable routing and terminations.

ECN 5599 - Conduit Supports for Fifth Vital Battery and Waste 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.

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

ECN 5626 - Containment Ladders, Unit 1 Workplan being written to incorporate this ECN.

ECN 5703 - Reinforcement of Block Walls Work is field complete.

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

ECN 5724 - CVCS/RHR Supports Fleidwork is complete. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 Oth:r Items (cont.):

ECN 5743 - Ladders In Containment A workplan to install additional safety gates continues in the approval cycle.

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

ECN 6005 - Replacement of AFW Air Ejector The workplan continues in the approval cycle.

ECN 6014 - Replacement of ERCW Pump Bearing Piping Resolution of piping dimensional problems is in progress.

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 Postmodification testing (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 6380 - Replacement of Barton Pressure Transmitters The unit 1 workplan is holding for resources. Unit 2 instruments are tastalled but problems have been encountered in calibrating.

3CN 6357 - ERCW Roof Access and Rails for Security Equipment Wortplan 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.

i l - - _ _ _ - _ _

- _ - _ _ _ = _ _ _ _ _ _ - -

-d Other Items (contd.):

1, ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation

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

ECN 6437 - Replace FE-2-265, and 257 The mechanical workplan was written, approved, and placed in work.

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 completed. 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 I work is incomplete.

ECN 6631 - Modify Scrubbers Work on approximately 20 hangers was transferred from Mechanical Maintenance.

ECN 6661 - Upgrade of ERCW Piping Piping was reworked.

NDE is required for existing welds. This will be completed upon receipt of DNE information QA approval.

ECN 6689 - Relocation of Mainbteam PORV The new positioners have been installed. Tube routing details have been transmitted to DNE for evaluation.

Postmodification tests are l-incomplete.

l ECN 6698 - Repull 120-Volt Cables Termination of one cable remains. - _

['.

Oth r Items (c*nt.):

ECN 6700 - Anchors Near Free Edge A workplan was written and approved and placed in work for the additional discrepancies.

ECN 6701 - Modify Foxboro Recorder Latches Fleidwork is on hold.

Completion delayed due to material which is on order.

f ECN 6706 14 Support Enhancement Fieldwerk completed on unit 2 and in progress on unit 1.

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

Unit i evaluations are continuing.

DNE is evaluatin6 contract proposals.

ECN 6707 - Replace System 74 Flow Switches Calibration equipment has been returned.

First train is calibrated I

and is wating for an' operational windor for a functional list.

ECN 6715 - D/C Random Loads Train B is complete.

Train A is in wort.

ECN 6717 - Stub Bus Fuses Workplan is on held for material.

ECN 6739 - Alternate Analysis DNE support remains incomplete and is tied to ERCW system outage. Work is in progress. The.o are 281 supports out of 282 on unit 2 completed.

DNE is evaluating contract proposals.

ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits Workplan is in work.

ECN 6746 - Install Fuses Workplan is complete.

ECN 6749 - Replacement of Bussman KAZ This ECN will be superseded by ECN 6854. Workplan 12152 will be closed and Workplan 12328 kill be written to replace KAZ to MIS-5 to FLAS 5 fuses. Awaiting DNE drawings and new fuses.

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. _

~.

~

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

I.

ECN 6762 - Modify Hanger NCR CEB8615 Fieldwork is in progress.

ECN 6763 - Add Fuses to Flow Switches Workplan is complete.

f, ECN 6768 - Rework Cable Tray Hangers Workplan remains in approval cycle.

ECN 6769 - Auxiliary Air Compressor Traps Fieldwork was completed.

I ECN 6783 - Replace Motor on 2-MOV-70-87 This ECN is superseded by ECN 6858 which will regear the MOV instead of replace the motor. Workplan is ready for work.

ECN 6787 - Inspection and Replacement of Solenoid Valve Supports I

Fieldwork is complete.

Final postmodification testing remains.

l

,ECN 6790 - Medium Energy Pipe Break The spare penetrations have been sealed. Work has not started on others.

ECN 6791 - Pipe Clamp Replacement The workplan was approved and placed in work.

ECN 6802 - Modify EGTS Filter Housing Work continues.

Completion is on hold due to postmodification testing problems.

ECN 6810 - Rework Category "C" Devices First workpInn ir in work; second workplan is in approval cycle.

ECN 0811 - Replace Heat Trace Breakers Power Circuits and Current Sensors in FP Breakers Work is complete.

ECN 6832 - Backup Control Room Cable Reroute l

1 Work is in process--schedulod to complete April 20, 1987. - _ _ _ _ _ _ _ _ _ _ _

.i,

Other Items-(cont.):

ECN 6820 - Roset Breakers Work is complete.

ECN 6821 - Screens for RCPs Fieldwork is complete for unit 2.

ECN 6827 - MELB Plugging Drainr for Control Building A workplan was written and placed in the. approval cycle.

ECN 6848 - Thermal Expansion Problems With Platforms Work continues in progress in 14 accumulator room, incore room, and RCD platforms.

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).

ECN 6853 - Installation Of Curbs And Detins For Containment Recirculation Fieldwork was completed.

ECW 6871 - External Conduit Sealing DG'8/CL/ERCW Workplan preparation in process.

ECN 6874 - CVCS Heat Trace Power Circuits

-Workplan preparation in process.

ECN 6878 - Replace PS and TS SYS 32 Workplan issue for approval held for drawing issue by DNE.

Supersedes ECN 6824 (cancelled).

ECN 6879 - Reinforcing Pipe Lateral A workp?an was written and approved for this work.

ECN 1000 - Additich of Support to Main Steam Dump Header Fieldwork is complete except final inspections during heat up.

ECN 7078 - Install Hangers - Main Steam Piping Original identified scope completed, however, additional work is required.

Some damaged hangers were identified.

Other Items (cont.):

Storage Building at Pcwer Operations Traininr. Center Complete.

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

Workplan 12208 written, but held for design drawings.

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

Control Room Bullet Resistivity - DCR 2268 - ECN 6860 Work held for Site Director on proposed boundary change.

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

Operational Readiness Report Modification inputs complete. -

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

O O

e ENVIRONMENTAL QUALIFICATION (E.Q.)

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F

l TilIS PAGE INTENTIONALLY LEFT BLANK I

i l

1

8 TENNESSEE VALLEY AUTHORITY l

Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 April 15, 1987 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Centlement SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - MARCH 1987 Enclosed is the March 1987 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.

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

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

Director, Office of Inspection i

and Enforcement Nucicar Regulatory Commission Washington, DC 20555 (10 copies)

Mr. T. Marston I

b actric Power Research Institute

<. O. Box 10412 Palo Alto, California 94304 (1 copy)

INPO Records Center l

'L/q l

Suite 1500 l

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

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

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

_ _ _

ML20237K701

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