Text

Monthly Operating Repts for June 1985
	ML20135C291
Person / Time
Site:	Sequoyah
Issue date:	06/30/1985
From:	Eddings M, Wallace P; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8509110382
	Download: ML20135C291 (34)
	v • d • e

.

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION June 1, 1985 - June 30, 1985 UNIT l' DOCKET NUMBER 50-327 LICENSE NUMBER 5DPR-77 i

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

~

P. R. Wallace, Plant Manager f

1

\\0 a

e

i 4

1 TABLE OF CONTENTS I

i I.

Operational Summary Page Performance Summary 1

Significant Operational Events 1-2 Fuel Performance and Spent Fuel Storage Capabilities 3

i l

PORCs and Safety Valves Summary 3

i Licensee Events, Special Reports and 3-5 Diesel Generator Failure Reports 5

Offsite Dose Calculation Manual Changes 5

II.

Operating Statistics A.

NRC Reports-Operating Data Reports 6-7' Unit Shutdowns and Power Reductons 8-9 Average Daily Unit Power Level 10-11 B.

TVA Reports a

Nuclear Plant Operating Statistics 12 j

Unit Outage and Availability 13-14 Reactor Histograms 15-16

?

-III. Maintenance Summary Electrical Maintenance 17-18 Instrument Maintenance 19-23

. Mechanical Maintenance 24 Modifications 25-29 6

s

?

4 s

a h

-u

..nm

,3','

,y g

,v-_

,-,c,,,

yy,

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

.,wr, rwy

Operations Summary June 1985 The following summary describes the significant operational activities for the month of June.

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

Unit 1 Unit I returned to service at 2124 CDT on June 26, 1985. The reactor was critical for 110.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , produced 82,330 MWH (gross), resulting in an hourly gross load of 834,990 kW during the month. The capacity factor for the month was 9.7 percent. There are 73.24 full power days estimated remaining until the end of cycle 3 fuel. The cycle 3 refueling / modification outage is scheduled to begin September 27, 1985.

During the month the unit experienced no reactor scrams, one power reduction, and no manual shutdowns.

Unit 2 Unit 2 was critical for 720.0 hours0 days 0 hours 0 weeks 0 months , produced 829,310 FSAI (gross), resulting in an average hourly gross load of 1,151,819 kW during the month. The capacity factor for the month was 97.4 percent. There are 204.46 full power days estimated remaining until the end of cycle 3 fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached February 26, 1986.

During the month, the unit experienced no reactor scrams, manual shutdowns or power reductions.

Significant Operational Events Unit 1 Date Time Event 06/01/85 0001 The reactor was in mode 4.

Reassembly and leak testing of the electrical generator continued.

0012 The reactor entered mode 5 so the RCS could be drained to work on number 4 reactor coolant pump number one seal.

06/10/85 1915 The reactor entered mode 4.

06/12/85 0950 1-PCV-68-334 (PORV) opened due to COMS actuations. Recently revised setpoints were not provided to the operator prior to obtaining the setpoint limit.

2136 The reactor entered mode 3.,

Signifiernt Operationzl Events (Cont.)

Unit 1 Date Time Event 06/14/85 1423 The reactor entered mode 4.

1921 The reactor entered mode 5.

The number 1 and 3 reactor coolant pump flange seals required maintenance.

06/19/85 2040 The reactor entered mode 4.

06/20/85 1243 The reactor entered mode 3.

06/23/85 1120 The reactor entered mode 4.

1635 The reactor entered mode 5 due to electrical problems with CRD J-13 connector in the head.

The center missile shield was required to be lifted.

06/24/85 1025 The reactor entered mode 4.

06/25/85 0035 The reactor entered mode 3.

06/26/85 0945 The reactor was taken critical.

1200 The reactor entered mode 1.

1519 Completed the turbine trip test.

2124 The unit was tied on-line. The duration of the ice weighing / maintenance outage was 74 days, 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , and 37 minutes.

06/28/85 0930 The reactor was in mode 1 at 80% power and increasing when the condenser backpressure began increasing. Started a load reduction.

1033 The reactor was at 50% power and holding due to condenser back pressure problems.

1042 Began power ascension.

06/29/85 0155 The reactor obtained 100% power.

06/30/85 2359 The reactor was in mode 1 at 100% power, producing 1150 MWE.

Unit 2 06/01/85 0001 The reactor was in mode 1 at 100% power, producing 1170 MWE.

06/30/85 2359 The reactor was in mode 1 at 100% power, i

producing 1150 MWE.

l,

Spent Fuel Pit Storage Capabilities The total storage capability in the spent fuel pit (SFF) is 1386. However, there are five cell Iccations which are not capable 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 276 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1105.

There was no fuel movement within the reactor. However, the final three shipments of cycle 4 fuel (36 bundles) were received during the month. A total of 72 fuel assemblies have been received, inspected, and properly stored in the new fuel storage vault. There were no reported discrepancies. An inventory was performed on June 19, 1985 per TI-1 and there were no discrepancies.

Four (4) thimble plugs (PD-217, PD-180D, PD-126, PD-72) with suspected bent pins were shipped to Westinghouse Fabrication Plant, Columbia, S.C. on June 4,1985 so that proper and professional repairs could be performed by qualified Westinghouse personnel. These repairs were made so that these thimble plugs could be used for future fuel cycles.

TVA incurred no costs regarding repairs, shipping or handling.

The four (4) thimble plugs were returned to Sequoyah Nuclear Plant on June 19, 1985. After inspection, they were found to be satisfactory. They were properly stored in the new fuel storage vau).t.

PORVs and Safety Valves Summary 1-PCV-68-334 was challenged at 0950 on June 12, 1985, by actuation of the cold overpressure mitigation system (COMS). The COMS setpoints were changed but the revised data was not given to the unit operator prior to obtaining the new setpoint limit.

Licensee Events and Special Reports The following licensee event reports (LER) were sent during June 1985 to the Nuclear Regulatory Commission.

LER DESCRIPTION OF EVENT 1-85024 Starting at 1000 CDT on May 24, 1985, with unit 1 in mode 4, the hourly firewatch for the auxiliary building supply air fan room was not performed because door A-123 would not open. The hourly fire watch resumed at 1300 CDT.

1-85004 R2 This LER was originally reported in the February 1985 Monthly Operating Report to the NRC.

The LER concerns SI-261, " Visual Inspection of Fire Doors" not being performed within the technical specification time limits.

On March 29, 1985, it was discovered that there were an additional sixteen (16) deficiencies which were inadvertently omitted from the original report and revision 1 was submitted. Revision 2 provides details and schedules for completion of the outstanding deficiencies.

., ~

Licensee Events and Special Rsports (Continued) 1-85019 A design review revealed that during a seismic event, a one-inch demineralized water pipe and a high pressure fire protection (HPFP) header could have failed. This failure could have caused water spray damage on motors i

and electrical control panels in the main control room air conditioning chiller systems. The demineralized

+

water pipe has been isolated, and there is ample-time for repair if the HPFP header should fail.

1-85020-On May 14, 1985, with unit 1 in mode 5, both trains of residual heat removal (RHR) were inadvertently isolated 4

by c3.osure of the train B suction valve <

The isolation occurred while work was being performed on the reactor vessel level instrumentation system (RVLIS) to refill the sense lines. The RCS wide range pressure transmitter l

1-PT-68-66, which is used for RHR overpressure protection, receives its process signal from the RVLIS sense lines and.was increased approximately 2000 psi during testing (RHR isolation is at 700 psi increasing). The suction

-was reestablished within approximately 16 minutes and there was no indicated change-in RCS temperature.

j 1-85021 An inadvertent main control room (MCR) ventilation isolation occured at 0705 CDT on May 23, 1985, while unit I was in mode 4 and unit 2 was in mode 3.

Radiation monitor RM-90-125 was found l

to have a bad power supply. The power supply was replaced, the monitor functionally tested and returned to service.

+

1-1-85023 This report details four inadvertent auxiliary building ventilation isolation (ABIs),

i The first event occurred at 1601C on May.30, 1985 with unit 1 in

,.l' mode 4 and unit 2 was in. mode I at 100% power. The ABI was caused by electromagnetic interference (EMI) on spent fuel pool (SFP)'

i radiation monitor RM-90-102.

The second event occurred at 0417C on May 31, 1985,~when the SFP monitor RM-90-101 high radiation-alarm-actuated. The spikes were probably caused by EMI' generated by.a combination of operation of the motor operated disconnects :(NODS) switches

}'

in the switchyard. and the replacement of filter paper in the

~

monitor.

4 The. third event occurred at 0449C on May 31, 1985, while ther ventilation system.was beingLrealigned after the previous-event.

J.

RM-90-101A spiked on particulate with the magnitude of the: spike i

of 2000 cpm. The set point was 1340' cpm. The particulate set point has been reevaluated per--TI-18 and raised to -11,040 cpm.

based on Colbolt-50 instead of Iodine 131.

j The fourth event occurred on June.7, 1985, while electrical maintenance. personnel were working on_a plug mold inside.a 4

cabinet in the main control room. The personnel inadvertently

' bumped alhigh radiation time' delay relay.

i -

,. _ ~

LER DESCRIPTION OF EVENT (Continued) l 1-85023 (Continued)

The bump and subsequent vibration from working on the plug mold caused the relay to fall out of its socket causing an ABI on the SFP radiation monitor RM-90-102.

The relay is a plug-in type which deenergize to trip.

1-85015 With unit 1 in mode 5 and unit 2 in mode 1 at 100% power, the service building radiation monitor 0-RM-90-132 was declared inoperable at 101CC on May 28, 1985. The STS requires a noble gas sample to be taken every eight (8) hours while the monitor is inoperable for up to 30 days or all releases must be suspended. On June 1, 1985, the 1810C sample was not taken until 2055C.

2-85010 On May 22, 1985, at 1329C with unit 1 in mode 4 and unit 2 at 100% power, unit 2 received a reactor trip from the reactor coolant system (RCS) overpower / differential temperature trip function. The trip was the result of a personnel error while collecting data from the RCS hot and cold leg temperature loops.

Special Reports No special reports were transmitted during the month.

Diesel Generator Failure Report There were no diesel generator failure reports transmitted during the month.

Offsite Dose Calculation Manual Changes No changes were made to the Sequoyah Offsite Dose Calculation Manual during the month.,

OPERATING DATA REPORT DOCKET NO. 50-327 DATE JULY 2 1985 COMPLETED BY M G EDDINGS TELEPHONE (615)870-6421 OPERATING STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1

NOTES:

2. REPORT PERIOD: JUNE 1985 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-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720.00 4343.00 35064.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 110.25 2577.35 23225.01

13. REACTOR RESERVE SHUTDOWN HOURS O.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 98.60 2563.70 22672.65

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 257388.60 8397224.36 73074910.31

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 82330.00 2900740.00 24637156.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 74759.00 2777899.00 23659529.00

19. UNIT SERVICE FACTOR 13.69 59.03 64.66

20. UNIT AVAILABILITY FACTOR 13.69 59.03 64.66

21. UNIT CAPACITY FACTOR (USING MDC NET) 9.04 55.72.

58.78

22. UNIT CAPACITY FACTOR (USING DER NET) 9.04 55.72 58.78

23. UNIT FORCED OUTAGE RATE 79.66 13.09 17.77

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

_ cycle _3_lefue.lingl@_df11_c.9319n _.Sentsrbst U _I_2.8.jL- _11_J)an_.

_=_---------__ _ - --__

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

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

OPERATING DATA REPORT DOCKET NO. 50-328 DATE JULY 2 1985 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6933

'OPERAT1dG STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLAV", UNIT 2

NOTES:

l

2. REPORT PERIOD: JUNE 1985 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 PESTRICTED,IF ANY(NET MWE):---_-_--

. 10. REASONS FOR RESTRICTIONS,IF ANY:____---------

- = _ _ _ _ _ _ - - - - _ - _ - - _ _ _ _ _ _ _. _ _ _ _ _ _

- - - - - = - _ _ -

=--

THIS MONTH YR.-TO-DATE CUMULATIVE-

11. HOURS IN REPORTING PERIOD 720.00 4343.00 27024.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.00 4045.22 20740.34 13.~ REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 720.00 3980.17 20250.35

15. UNIT RESERVE SHUTDOWN HOURS O.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 2444832.45 12900202.35 64899213.22

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 829310.00 4424850.00 22116530.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 796418.00 4255037.00 '21276045.60

19. UNIT SERVICE FACTOR 100.00 91.65 74.93

20. UNIT AVAILABILITY FACTOR 100.00 91.65

'74.93

21. UNIT CAPACITY FACTOR (USING MDC NET) 96.35 85.34 68.58

- 22. UNIT CAPACITY FACTOR (USING DER NET) 96.35 85.34 68.58

23. UNIT FORCED OUTAGE RATE O.00 8.22 8.52

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:

7

_----__-m_----_-

_:2 -

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

J d -

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-327 UNIT NAME Scauovah one DATE July 2, 1985-COMPLETED BY M. C.

Eddines REPORT-MONTH JUNE TELEPHONE (615) 870-6421 m

5.4 Cause & Corrective

"^

E"

..S B "E

y.5 g Event S.g g.g Action to No*

Date

~ e

.R*

$o

-g

,8 tj y Report #

g6 c3 Prevent Recurrence h

h5 5

_N E

.mg ca 2

850413

-S 235.25 H

4 Electrical Generator Maintenance Outage

?

3 850610 F

386.15 A

9

- Reactor Coolant Pump Seal Housing leak repairs and feedwater valve maintenance.

l i

1 2

3 4

F: Forced

. Reason:

Method:

Exhibit G-Instructions S: Scheduled' A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-!!aintenance or Test 2-Manual Scram.

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

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

E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5

(9/77)

H-Other (Explain)

Exhibit I-Same Source k

m e

f4 *Tf s

2 4

f4 l O

w nO D" 5 0 n C. O C %

w O

4 C

ta, r

l O

l 94 D* O M M C O D3 > *4 e e e e e e e e o l

o o > o M x =.M =

Type r' 'O C.*O O O 4 O M D* n 9 4 03 m sv. C O e4 M we M C C D we D

,N k D D wQ f* T **

r+

e=. re b wC B e w. M O r* w D 0 Duration MO r* M O 3 &

D, o u o.-n Q oo D (flours) x3 n r

n W W rv m G *r1 es wW W 4

2 wM4w0 0

H.

Reason D M 4 3 M

1 M

vm

- r, C

O 3 n en n

oo -

O o n

a Method of n

w e, r, n M

M Shutting M

FO M

3 ao

-D

o Down Reactor c:

M o

-w g

D G

w

>=

3 He D

M 3

p) y p

V O

V

g omw 2

a4n U

D D O

4 8

a 5-

=

E a

N O

tt3 f'.

Z w

d, O

D Sys cm Code 4

v

e. u ra - a "

O eu

~

e e e e e e m N

b omoO>m=c m

hi O C o G ::P r* m C,

CoDponent

r C. f D

c-D D O Code 5 E

aC = r+ o C C c.

Bk & **

Pg n oo e c

r* O k ww c

0

.H O

f*

O m m (f3 Oq D

nn ee M

M M CfJ D o

w 0 5 z

Cn uN

r'. W3 w

D oo OO

U O

2 O

=

N D

e.4 *o c= o Mu*

OMMmM a

C M t-*

2n M

* < D O X to tw M wx

.r Os O r' M D" O

4 MH e)M e*=

ea D Pt w.

D >

U M

)

7 v c' N

U 7 t' nv D* O C Z w-N w-c' W to m r+

M w'. O c

O

>>Z Z c4 M M.o 4%

O U"*C 3 O O M

N

O re m - o oD N e

oO M e C

M 14 M r9 b M

1 t'

O 19 Us rv D M O n m

9 mm o

re O

mmO f*

D

>=

u g Q t/3 u r* o D

t n

4 s

c m o to M *t C

O O

w.3 3

0

C O n oo n'< c w C

v F m f*

o ro q

M w-w.

n

1 n C O O

.a << oo t

l c g

G

w. O Q D M3 f*

m m.c

f to c 4 M D O

L.a 1

@ d

^O LJ m M C t

J O

O e

l SQNP ATTACHMENT 1 AI-18 AVERAGE DAILY UNIT POWER LEVEL Apendix A Page 3 of 8 Rev. 24 FILE PACKAGE NO. 55 DOCKET NO.

50-327 REPORT REQUIREMENTS UNIT 1

DATE Jul, 1, 1985 COMPLETED BY M. C. Eddings TELEPliONE (615) 870-6421 MONTH June-Day AVERAGE DAll.Y POWER I.EVEl.

DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(tNe-Net) i NA__ __ - _

17 NA 2

NA 18 NA 3

NA 19 NA 4

_ _ NA _ _ _ _ _ _ __ _ _ _

20 NA 5

_NA __

21 NA 6

NA 22 NA 7

NA 23 NA 8

NA 24 NA 9

NA 25 NA 10 NA 26 11 11 im 27 262 12 NA 28 890 13 NA 29 1111 14 NA 30 1116 15 NA 31 NA 16 NA l

INSTRUCTIONS l

On this format, list the average daily unit powet level in PNe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

o

l SQNP ATTACl[ MENT 1 AI-18 AVERAGE DAILY UNIT POWER LEVEL Apendix A Page 3 of 8 Rev. 24 FILE PACKAGE NO. 55 DOCKET NO.

50-328 REPORT REQUIREMENTS UNIT 2

DATE July 2, 1985 COMPLETED BY D. C. Dupree TELEPIIONE (615) 870-6933 MONTil June Day AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1_13_2_

17 1112 2

1133 18 1111 3

1129 19 1110 4

1.128 20 1110 5

1126 21 1109 6

1124 22 1109 7

1123 23 1108 8

1114 24 1110 9

1113 25 1106 10 1113 26 1103 11 1115 27 1104 12 1113 28 1106 13 1109 29 1105 14 1111 30 1105 15 1111 31 i NA 16 1114 INSTRUCTIONS I

Gn this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

l l..

TVA MMA (Dr@+81)

NUCLEAR PLANT OPER ATING STATISTICS SEQUOYAll Plant 720 JUNE 85 Period Hours Month gg Item UN1I Uhli No.

Unit No.

ONE

'1VO PIANT 1

Averace Hourly Gross Load, kW 834,990 1,151,819 1,113,657 2

Maximum Hour Net Generation. MWh 1.124 1,140 2,232 3

Core Thermal Energy Gen. GWD (t)2 10.7245 101.8680 112.5925 4

Steam Gen. Thermal Energy Gen., GWD (t)2 10.7621 102.3239 113.0860 8

5 Gross Electrical Gen., MWh 82.330 829.310 911.640 j

6 Station Use, MWh 7.571 32.892 40,463 E

7 Net Electrical Gen., MWh 74.759 796.418 871,177 0

8 Station Use, Percent 9.20 3.97 4.44 i

9 Accum. Core Avg. Exposure. MWD / Ton 11.385 6,114 17,499 6

10 CTEG This Month.10 BTU 878,467 8,344,213 9,222,680 11 SGTEG This Month,106 BTU 881,543 8,381,554 9,263,097 12 13 Hours Reactor Was Critical 110.25 720.0 830.25 14 Unit Use, Hours-Min.

98:36 720:00 818:36 15 Capacity Factor, Percent 9.7 97.4 53.5 y

16 Turbine Avail. Factor Percent 13.7 100.0 56.8 17 Generator Avail. Factor. Percent 13.7 100.0 56.8 j

4 C

18 Turbooen. Avail. Factor, Percent 13.7 100.0 56.8 19 Reactor Avail. Factor. Percent 15.3 100.0 57.7 2

20 Unit Avail. Factor. Percent 13.7 100.0 56.8 21 Turbine Startuos 1

0 1

22 Reactor Cold Startuos 1

0 1

23 Prvion HoftRS 720 g

24 Gross Heat Rate, Btu /kWh 10,670 10,060 10,120 5

25 Net Heat Rate, Btu /kWh 11,750 10,480 10,590 3

26 GHR (w.o. oil) 10,120 O

27 NTR (u.o. oil) 10.590

=

28 Throttle Pressure, psig 901.8 866.3 884.1 I

I 29 Throttle Temperature. F 531.9 527.46 529.7 j

30 Exhaust Pressure, inHg Abs.

3.24 3.2 3.22 E

31 Intake Water Temp., F 77.3 75.7 76.5 5

32 33 Main Feedwater, M lb/hr 10.6 15.0 12.8 34 35 36 37 Full Power Capacity, EFPD 370.00 363.65 733.65 38 Accum. Cycle Full Power Days. EFPD 296.7608 159.1856 455.9464 j

39 Oil Fired for Generation, Gallons 1.518 2

40 Oil Heatina Value. Btu / Gal.

138,000 41 Diesel Generation. MWh 23 47 Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor. %

3 43 2232 1200 6/30/85 53,304 6/30/85 54.21 O

Remarks: I For BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.

j 2(t) indicates Thermal Energy.

3 m

Date Submitted Date Revised

Plant Superintendent

_ ~_

+

i TVA 6560C (PP 3 76)

UNIT OUTAGE AND AVAILABILITY SEQUOYAll Nudear Plant 3'II Licensed Reactor Power MW(th)

Unit No.

ONE Generttor Ra*ing 1220,5 MW(e)

Month / Year JUNE 1985 Des gn Gross Electrical Rating 1183 MW Period Hours 720 METHOD OF UNIT CORRECTIVE ACTION Tenw Unst Avaitat%e T6me Not Avastable.

Total Cen.

Not Used Turbine Gen.

Reac tor Unit Ou N

DUR G p

D'y Hrs ! Man Hrs l Min Hrs ! Men Hrs l Men Hrs l Min Hrs l Man Hrs l Men Hrs ! Min Mrs ! Men REACTOR OUTAGE 1

00 iOO 00 ; 00 l

24 '00 24e 00 24i00 24 s00 i

i 2

00 300 co i 00 e

24 l00 24; 00 246 00 24 !00 3

oo too oo i 00 a

24 iOO 24 00 24800 24 ; 00 l

4 on ion 00: 00 l

24 soo 24' 00 24! 00 24 '00 e

5 on too 00 e 00 i

24 'oo 24: 00 24100 24 !00 8

.l 6

00 800 000 00 1

24 foo 24i 00 24a 00 24iOO f

7 no 'on 008 00 24 :00 24! 00 24l 00 24 too i

8 oo Ioo on ! Do l~

24 e00 24i 00 246 00 24 l 00 t

9 nn :nn noi no e

24 lo0 24' 00 24! 00 24 soo i

10 nn inn on i no i

24 ion 24l 00 24 ; 00 24 ! OO i

11 no soo 00' 00 l

24 800 24, 00 24e 00 24 i OO e

12 nn 800 oo! on i

24 lo0 24' 00 24 : 00 24 800 e

i 13 nn 'on noioo 24 'oo 24: 00 24 i no 24 !00 t

i 14 nn :nn nn i on 24 no 24i oo 24

00 24 : oo 15 nn ;on on ! 00 i

24 800 248 00 24 l 00 24 i 00 i

i 16 no Inn 00 no i

24 l00 24i 00 24! 00 24 100 I

8 17 on Inn on: nn 24 ion 24! og 24; 00 24!OO s

18 nn !no oo i no i

24 f oo 24l 00 24* 00 24 l 00 e

19 nn :nn not oo i

24 ion 24i 00 24i 00 24 i 00 k

00 00l00 l

2I ob'$

hYD 00 27 00 soo 00i 00 z4 8 00 24! 00 ze s u7 ze ou e

?3 00 '00 006 00 a

24 !00 24; 00 24 : 00 24 ; 00 e

a 24 00 l00 00! 00 24 iOO 24! 00 24i 00 24 i 00 8

-25 00 l00 00i 00 3

24 800 24l 00 24 a 00 24s00 i

26 o? i36 02t 36 6

21 '24 21i 24 09 ; 45 21824 21 t24 27 24 100 24! 00 I

00 '00 006 00 00s 00 00 ! OO a

28 24 800 24i 00 i

00 '00 00! 00 00 l 00 00;00 i

8 29 24 IOO 24! 00 8

00 i OO 00; 00 00! 00

00. 00 30 24 i OO 24i 00 00 :00 oni nn nn i nn nn nn i

31 e

e i

i e

Total 98 836 981 36 821 e24 621' 24 609i 45 621 l 24 ><'i ><XIX C

X X

_X

TVA 6560C (m3-76)

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

Unit No.

WO Generator Rating 1220.5 MW(e)

Month / Year JUNE 1985 Design Gross Electrical Rating 1183 MW Period Hours 720 Time Unit Avadabee T6me Not Availatde MEMOD OF UNIT CORRECTIVE ACTlON Time T6me SHUTTING STAWS OUTAGE CAUSE TAKEN TO PREVENT Total Gen.

Not Used Turtnne Gen.

Reac tor Unit Out in DOWN DURING REPETITION oav Hrs : Min Mrs ' Min Mrs I Men Hrs i Men Hrs l Min Hrs ' Min Hrs l Men Hrs ! Min Hrs ! Men REACTOR OUTAGE I

24 i00 24 l00 I

00 ' 00 00 ' 00 00 iOO 00 '00 i

e 2

24 300 24 iUU i

00 : 00 00 : 00 00 #00 00 l00 3

74 : 00 24 800 e

00:00 00 :00 00 '00 00 ;00 l

4

?4 i OO 24 i.00 l

00:00 00 '00 00 f00 00 80 0 I

8 5

24 800 24 iOO i

00800 00 :00 00 l00 00 '00 8

e 6

24 800 24 000 1

00l00 00 i OO 00 '00 00 iOO 8

~E 7

24 3 00 24 '00 00:00 00 f00 00 l00 00 80 0 e

8 74 l 00 24 '00 00:00 00 i OO 00 t00 00 l00 e

9 24 00 24 iOO 00!OO 00 800 00 !OO 00 e00 I

l 10 24 iOO 24 800 00 i OO 00 !OO 00 iOO 00 !00 11

?4 000 24 800 00 e og oo,00 og too go joo l

12 24 800 24 l00 i

00l00 00 ! OO 00 l00 00 100 i

i 13 24 l00 24 iOO 00 '00 00 l 00 00 iOO 00 !00 8

14 24 500 24 ago oo ; oo go f oo on 400 00 ho 15 24 !OO 24 !OO i

00800 00 eoo ao lco oo goo i

16 24 800 24 l00 e

00:00 00 i OO 00 !00 00 10 0 g

17 24 300 24 l00 00 t00 00 ! OO 00 l00 00 !OO I

18 24 !00 24 t00 i

00 !OO 00 l 00 00'!00 00 l00 8

e 19 24 l 00 24 t00 s

00 iOO 00 100 00 IOO 00 10 0

?

20 24 500 24 300 00 ! 00 00 !OO 00 l00 00 10 0 i

21 24 e 00 24 l00 00 !00 00 IOO 00 [00 00 100 e

i 22 24 800 24 iOO 00 800 00 !00 00 800 00 IOO i

I i

23 24 '00 24 800 1

00 !00 00 i OO 00 l00 00 l00 i

8 24 24 l 00 24 !00 f

00 t00 00 !OO 00 iOO 00 i00 8

25 24 ;00 24 l00 t

00 800 00 '00 00 '00 00 10 0 i

26 24 00 24 800 1

00 l00 00 i OO 00 I00 00 100 e

27 24 800 24 !OO I

00 soo og s oo go.0o og bo a

28 24 800 24 iOO i

00 !OO 00 !OO 00 l00 00 ;00 8

29 24 !OO 24 !OO 8

00 iOO 00 ;00 00 !00 00 no 30

,i. i nn km l

lmm imm imm i

,1 nn 31 e

e

~~ imm mm um

"" r~

mm i

Tot t no ! w 720 po i

>CMAN

_z X

X y

TvA 6%0C (PP 3-76)

UNIT OUTAGE AND AVAILABILITY SEQUOYAH Nuclear Plant 34II Licensed Reactor Power MW(th)

Unit No.

ONE Generttor Rating 1220,5 Mw(e)

Month / Year JUNE 1985 Design Gross Electrical Rating 1183 MW Periorf Hours _ 720 Time Unit Avaesame T6rne Not Avadatdo METHOD OF UNIT CORRECTIVE ACTION

^

Total can.

Not Uwd Turtnne Gen.

Reactor Unst Ou N

DUR G PETIT Day Hrs ' M n Mrs ' Men Hrs ! Men Hrs i Men Hrs l Men Hrs ' Min Hrs [ Mon Hrs ! Men Hrs !M6n REACTOR OUTAGE 1

00 iOO 00i 00 1

24 !00 24' 00 24 i 00 24 a00 i

i 2

00 !00 00 00 t

24 l00 24: 00 24800 24 ! OO 3

00 '00 00s 00 e

24 i00 24: 00 24 8 00 24 ;00 l

4 00 iOO 00 l 00 l

24 s00 24' 00 24! 00 24 e00 e

e 5

00 100 00s 00 i

24 '00 24: 00 24 l 00 24 !00 1

6 00 800 003 00 1

24 l00 24i 00 24! 00 24 i 00 Y

7 no 'On 008 00 24 !OO 24! 00 24l 00 24 e 00 e

8 00 l00 00 l 00 m

24 800 24: 00 24100 24 l 00 e

9 nn Mn on i no 24 foo 24! 00 24 ! 00 24 s00 I

10 on ino 00 e no 24 iOO 24l 00 24 i 00 24 ! OO l

8 11 on 100 00! 00 24 '00 24: 00 24000 24 i OO I

l i

12 00 800 00 l 00 i

24 l00 24! 00 24; 00 24 000 I

13 on Inn on i 00 24 '00 24l 00 24t00 24 !00 14 nn inn on I on 24 l00 24i no 24* 00 24 l 00 15 no inn on ! 00 i

24 800 248 00 24l 00 24 t00 i

i 16 nn inn on: 00 e

24 l00 24i 00 24 ! 00 24 100 1

17 na Inn onl no 24 t00 24! 00 24 l 00 24 ! 00 I

18 no !On on 00 24 !OO 24 l 00 24 ! 00 24l00 e

19 on Inn 001 on 24 iOO 24i 00 24 i 00 24 i 00 20 nn nn nn i nn 24 !00 24! 00 24I 00 24 100 l

21 00 iOO 00; 00 l

24 ;00 24; 00 24 ; 00 24100 22 00 100 00 j 00 24 000 24a 00 24 UU 24 ; UU e

23 00 !00 001 00 s

24 !00 24i 00 24 ' 00 24 ; 00 e

24 00.00 00! 00 24 iOO 24! 00 24 ; 00 24 i OO e

25 00 ;00 00i 00 g

24 800 24l 00 24s 00 24100 26 02 i 36 021 36 1

21 l 24 21i 24 09 : 45 21124 21 e 24 27 74 #00 24! 00 00 e00 00s 00 00 00 00 s00 e

i 28 14 800 24i 00 i

00 !OO 00! 00 00; 00 00 ; 00 I

29 74 IOO 24! 00 1

00 #00 00l 00 00 ! 00 00i 00 l

30 24 i00 24i 00 l

00 l 00 noi nn nn i nn no t nn i

n 31 e

i i

e i

Total 98 ! 36 98l 36 621624 621l 24 609i 45 621' 24 XXXX

~

_~

~X

_X

~

l c

f 9,

i Tt9A oS60C (PP 346)

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

Unit No.

1220.5 MW(e) -

Month / Year JUNE 1985 Geraator Rating Design Gross Electncal Rating 1183 MW Period Hours 720 EBOD OF UNIT CORRECTIVE ACTION Time Unit AvailaWe T6me Not AvailaWe SHUTTING STATUS Time T6nve OUTAGE CAUSE TAKEN TO PREVENT Totae cen.

Not Used Tintune Gen.

Reactor Unst Out en DOWN DURING REPETITION Dw n l u.n Hrs ' Men Hrs ! Min Has l Men Hrs l M.n Hrs l Men Hrs l Min Hrs ! Man Hrs

Men REACTOR OUTAGE I

24 soo 24 ;oo l

00 ' 00 00 ' 00 00 soo 00 'on i

i 2

24 400 24 iou 00 : ou oo 00 00 soo 00 !ao 3

2.

00 24 '00 a

00, 00 00,00 00 100 00 ;00 l

4 24 J 00 24 ;00 00 a 00 00 800 00 !00 00 '00 e

e 5

24 #00 24 soo i

00 ' 00 00 :00 00 :00 00 '00 6.24 400 24 IOO I

00 '00 00 i OO 00 !00 00 iOO 7 '24 ' 00 24 800 00 : 00 00 f oo 00 l00 00 80 0 e

i 8

24 l 00 24 '00 l

00 :00 00 i OO 00 800 00 l00 i

9 a4 : 00 24 ioo e

co t oo 00 '00 oo 'oo oo 800 i

10 24 ;00 24 800 e

oc i 00 00 l 00 00 ico oo 'oo i

11 24 #o0 24 '00 00 ' 00 00 i OO 00 800 00 iOO 12 24 '00 24 l00 t

00 : 00 00 !o0 00 :oo 00 loo t

i 13 24 l00 24 iOO 00 '00 00 l00 00 ioo 00 foo 14 24 ; oo 24 800 00 : 00 oo ion no 800 00 :no 15 24 i OO 24 !00 i

00 800 00 800 00 Ioo 00 too e

i-16 24 s oo 24 lo0 i

oo : 00 no 100 00 foo on 10 0 e

17 24 000 24 lo0 00 i oa 00 !oo 00 l00 00 foo e

18 24 !OO 24 i00 oo ? 00 00 !oo 00 800 00 lo0 e

i

_ ).1_26 :00 24 600 e

oo i co 00 s oo on ino no ino 20 24 ;oo 24 loo 8

00 t oo oo f oo 00 !oo ao 100 21 26 n 00 24 500 I

00 i Oo 00 IOO 00 l00 00 bo e

00800 00 foo 00 soo 00 foo e

i 22 26 800 24 iOO i

23 24 'o0 24 800 i

00 f oo 00 ioo 00 foo 00 ;oo e

00 ioO 00 !o0 00 ioo 00 ioo 8

24 2a ' 00 24 !Oo 25 24 ;00 14l00 i

00 ' 00 00 '00 00 '00 90 10 0 i

26 31 ; oo 24 800 8

00 : 00 00 ioo 00 l00 00 too i

37 24 e 00 24 !00 00 800 00 800 00 '00 00 bo i

a 38 24 000 24 iOO e

00 !OO 00 !00 00 l00 00 bo 39 24 !00 24 !o0 8

oo 6 00 00 lo0 00 'on oo co l

31 e

i e

_ i_

i

nn imm i_

r

e 30

,, ; nn

,, inn mm m

nn i

,v X

'><fX Z-X X

y

_c Totas 720 vu 720 p0 e

A

=

4 SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -

IM 90 -

14 80 -

11 70 -

W I

60 -

63 50 -

II O

40 -

g O

b 30 -

6 E

20 -

9 3 10 -

1 2

3 45 67 89 101J12 0

=

-10 O

4 8

12 16 20 24 28 32 JUNE 1985 SEQUOYAH TWO REACTOR HISTOGRAM 110 100 -

90 -

h 80 -

U 6

70 -

a.

y 60 -

a 50 -

eO 40 -

U h

30 -

20 -

l-10 -

t O

O 4

8 12 16 20 24 28 32 JUNE 1985 1-

Reactor Histogram Comments I

June 1985 Unit 1 1.

0012 The reactor entered mode 5 to repair the #1 seal housing on reat tor coolant pump #4.

2.

1915 The reactor entered mode 4.

3.

2136 The reactor entered mode 3.

4.

1423 The reactor entered mode 4.

5.

1921 The reactor entered mode 5 to repair the flange seals on reactor coolant pumps #1 and #3.

6.

2040 The reactor entered mode 4.

7.

1243 The reactor entered mode 3.

8, 1120 The reactor entered mode 4.

9.

1635 The reactor entered mode 5 for repairs to CRD connector J-13.

10.

1025 The reactor entered mode 4.

11.

0035 The reactor entered mode 3.

12.

0945 The reactor was taken critical.

13.

2124 The unit tied on-line.

14.

0930 Began power reduction to 50% power due to loss of condenser vacuum.

Unit 2 The reactor maintained 100% power the entire month.

1 l

i l t i.

+ ~ - -, - -

m--*

s 11: 41: 4 06-26-85 ELECTRICAL MAINTEMAICE 1113mLY REPGtT FGt dBE PAGE 1-DATE....

(IN00ENT..'...

FC.ILLRE DE90tIPTION.....

CAUSE OF FAIListE.........

CORRECTIVE ACTION........

MR.NO..

~

05-0l>45 2-ffTRB-3-47 DISCGBECT fETGt Ale IECHANICAL FAILURE DISCODBECTED fWTOR Ate A539164 RECGBECT AFTER RECODBECTED AFTER fECH.

fECHANICAL REPAIR REPAIRED 05-16-85 1-HS-3-173A-B HAfGGUITCH BRGEN CAUBE UMNNOWI REPLACED HAfG8 WITCH A528872 05-22-85 2-910tC-099-((C/

BRONEN CONTACT ON BACK OF BAD CONTACTS INSTALLED CIFTACTS ADO A526430 319 BYPASS BREANER TOOK "B" BYPABB BREANER i

(FF 05-29-85 1-flV0P-003-004 DISC 000ECT WIRIls TO _

110 TOR TO BE INSTALLED

' INSTALLED fMGt ADO :

A542212 l

7 VALVE-WIRING AfD 57: LIMITS i

l

'05-29-85 2-CNt-313-B LOW DIL LEVEL CAUSE UNNN0l#4 CHARGED 8 GALLONS 4GS DIL A535231 1

05-30-85 '1-LCV-3-156A LCV IS FILL (PEN WITH SNORTED DIODE IN JACTION REPLACED DIG)E A531067 i

ColmMLLER IN AUTU Afe BOX-fETIM DRIVEN AUX' lq FEEDWATER Pttp (FF

.i 06-03-G5 1-LCV-003-0164 IB(ILE PDtFGtMItC WORK ON

_ BAD BLOCKING DIODE REPLACED DIGIE PER A542217 A-A 1-LCV-3-156 FDLBC 45N1630-56 USDC F18AI 12 i

BLOCMDE DIGIE FRG115624

' A6C MI 6.20 TO 15625 IN A3076 WAS i

DET DETALLED PGt 45N1630-56 R5 YALVE WILL j-NOT PASS SI 276 l

06-03-85 1-ZS-68-03404-RED LIMIT LIGHT WILL NOT POSSIBLY BREANER HAD_BEEN Foule BREANDt 24 OPEN ON A531166 14 CGE (M IAEN ! PRAY VALVE LEFT OPEN LAEN PREVIOUGLY 120V AC VITAL INSTRIDENT OPENS WIRNED DN PAIEL I-1 n nwn BREANDt l

Ale OEDED F(R PROPDt l

j OPDtATI(M i

J 06-03-85 1-LCV-3-156-A VALUE OPENS lAEN DEFECTIVE DIODE REPLACED DICDE PER PRINT A527725 AUXILIARY FEEDWATER PLN 65N1630-56 I

i i

i t

11:41: 4 ' 06-26-85 ELECTRICAL FIAINTENANCE PE3m t.Y REPORT FOR dl M PAGE 2

~

DATE....'

(INOMMENT.....

FAILlRE DESCRIPTIIBt......

CAUSE OF FAIL 15tE.........

CORRECTIVE ACTION........

F5t. DO,.

~

Rt90tIls WITH LESS THAN 500 PSIG IS SIPRLATED VALVE SN0lLD (PEN LSWER TDE!E CODGITIIBS 06-05-85 2-FCV-43-175 VALVE BACM FEATS M (PERATOR WAS REPLACED BY.

PERFORPED Sit! 2-317-19 A300111 (PDED FR(fl HA6SSWITCH FSG WITH A FASTER GEAR.

AfG ADJUSTED TtE OPEN RATIO MAKING IT A LIMIT lTO 90%

FAST-SPEED VALVE i

06-05-85 1-fCV-69-333 CRYDED4 RELAY.. DEFECTIVE LEAKING REPLACED CRYD(Dt RELAY PER A100641 tlI 4.20 l

06-05-85 1-FCV-68-332-9 CRYDIDI RELAY DEFECTIVE LEANING-REPLACED CRYDON RELAY PER A100640 MI 6.20 a

06-06-85 1-FCV-401-0183 LIMIT SWITCH SNOWS BOTH LIMIT SWITDI OUT OF ADJUSTED LIMITS A531023

. RED AfD GREEN WITH VALVE ADJJSTFENT

~1.

' CL0 LED oo 3

4 06-07-65 1-fCV-68-334 RED ADO EltEEN LIGHT ON BAD REED SWITCH.

REPLACED REED SWITCH A543974 WITH VALVE IN CLDEED POSITION

}

06-11-65? 2%V-3-818 -

DECK VALVE F(R LEAN Tt5tU ' VALVE LEAN CIIA6ED ALL' PARTS AIG A103625 j

REINSTALLED 06-1 HI5 0-GATS-82-C-S.

REFGWE JARS Fittfl BATTERY PREVENTIVE 11AINTENA>CE REMOVED 9 CELLS FROM A291971 l

LSITIL IBt.Y 63 CELLS ARE

- BATTERY ADJtETED FLOAT j

IN BATTBtY AIG ADalBT VOLTAGE AfG EtuALI2E CHARGE

. VILTAGE i'

i.

06-14-85 2-ffTRS-30-74 BREANER IS TRIPPIDS OUT SAD it0T0ft REINSTALLED PENDR AIG A528704 j

131 OWERLORD DECKED Ft3t PR(FER OPERATION 7

c 1

i 1

4 l.

4 m

INSTRUMENT MAINTENANCE Unit 1 During startup of unit 1, while the operators were attempting to take the reactor critical, a problem developed in the Rod Control System. As shutdown bank B was being withdrawn, rod J-13 lagged behind and quit moving at 50 steps out.

The operator then drove shutdown bank B back in.

Rod J-13 fell in about 10 steps, moved in a few steps and then fell in to O steps. During trouble shoccing by Instrument Maintenance, the movable gripper coil / cable set appeared to be open.

It should have indicated ~ 10 ohms. The unit was taken to mode 5, and the center missile shield remc eed.

Electrical Maintenance inspected the connector and found the movable circuit pins burned. The connector was replaced and the problem resolved.

The following events occurred during startup of unit 1 following the ice weighing outage.

The turbine driven auxiliary feed water pump was declared inoperable. The level controller would not control in automatic and was replaced. Following replacement of the controller, the governor controls would not control speed. Two modules in the control circuit were replaced and the governor recalibrated. The LCV-3-148A would not operate properly and was declared inoperable. The I/P on the valve had a low output and was replaced.

Unit 2 Containment Sump Level Transmitter, 2-LT-63-176 required refilling of the sealed system. PRO 2-85-89 was initiated.

The turbine driven auxiliary feed water pump was declared inoperable because of a failure of the governor controls dropping resistor. A modification is being proposed to provide ventilation of the resistor to eliminate prolonged overheating which has been determined to be the root cause of the failure.

This is the second failure of the dropping resistor this year.

Common Three UHI level switches were identified as having been replaced with wrong QA Level material. Switches 1-LS-87-22, 1-LS-87-23, and 2-LS-87-23 were replaced per MRs with QA Level 2 material. These switches are Class IE equipment and have been replaced with QA Level I switches.

Employees of the section participated in the walk down of the 5th diesel generator.

The computer staff is upgrading the PRIME to process computer link to provide a faster scan rate and include disk resident calculated values. Hardware has been tested and software development is in progress. Assisted in the setup of the Health Physics dosimetry computer (HPDC) and development of software for the HPDC. Assisted in the checkout and startup of the TSC computer system. _

-, ~

O H6 D

G3 O

M K

3 T

D U8 3

5 t

D E

R K

DEER OS SO NR4 F

E GO5 D

F 5

W S

S D T

F D

R T

r I

5 T

M D

N E

M E

OO TE EL KT t

I UR RO C

n P

R O

NEAER A

X R

DI t

D 9

P E

AC CU D

ETA CP PR GF EN R

H MI E

RI V

G I TI T E

B I SE SO L

O CI N R

O T

VTVNVE R

I O

TRNR RR L

O AOB AT VP TD KO O

F NRNEEEEE O

DDDA PPU W

O E

RA F

RRRC H

E T

T TO TR EED P

AF ESMSNSO M

AAAE T

RV RN OL NI TLE P

O N

G P

O O

NSMOGOI OA CCCR I

LG EE O

EAVF C

O L

OI GTI TLT N

U HVN TR RF RPRATA L

HI L

A B

E LLL T

IERR O

REE OL N

DTLDAD DI K

AAA.

W INR( EL T

F RSONP B

L D

L O

CCCB S

WIEI VC O

( N C

N O

O AEDEEEA E

B F R R

EEEI TRN P

O DL VR O

TEETOE OI D.TOL t

L EDRERI RC 5

RRRL D

C GIBF SC D

J T

L A

DPEI I I FI E

A E

D FVR T

E DR ED E

(

N A

C E

IT FTITO SD

.C VA TR0S C

TO EOEDeF 1

I O

C RLFEI ERED AO..

I D

I AI RRRERA WRLLLFRL W

E0 SB A

AP RP l

T D

E ACR E

V TAAAOEP SGPAEI L

E I URLuI PEEOVO OD ECCCC SE NO RL P

SK WOI B0D C

E I

A I

F F

I R

M M E NE EI T

R EIRLPA E

MC RTOF E ERV FF(FUD ERPA C

R CA KGER F

( l E

CDE AR C

RPD K

I R

OENENI DTE MTD TRR B

AR f

O(

B4 G RE t

R E

I T

MOOOONI L CDTTTSDO HEE D E.

D LE0OA B

I E

V IAEEEUUUAEN1CF LET

.TT TE BT N

D T

V D

NINI 0

T CLCDOOW

.U LIN C

E1

.T.T RO CI RA

.GAFEBEP EF CE

.EO E

P 7 A

A

.A

.I EA R

NF D9EEEEEEERDPRRRTTE0 ENTI RI V PI B

E E

t 2

R R

R V

LDDDRL f

VE O

NRERD R

D OSRRLND SR L

RO O

O A9OPOPOPOELEAAAF EOR ( RNEUAOA UE OOI OTA f

C N

N B2NONONONSORCCCXRNFNWI VCCCB SV FCWNSB 1

M FF F

D R

R R

R 3

E N

0 O

2 2

E E

2 R

I 9

O N

P P

I N

N O

DB 7

A H

2X I

N1 R

R R

R 8

PE E

7O E

1 M

A1 E

E E

E EB R

E E

K E

7 3L1 L

L L

T l&

SP S

K O

E L

L L

L S

RL I P O

O R

G 4

6 C

C t

C EG N

A L

R T

A 1

1 28 R

R R

R DD 1

E N

3 C

T S

P 8

6 T

T T

T RR ON P

9E S

31 3N N

N N

N AA H

I O

E T

P R

1 I M O

O O

O CC T

HR W

3A 1f R

E T

T T

C C

E I

TE Y

C P

E P

FLF31 D

BLL W

I T L

N NI PYO 1

E E

O I AAR WE L

OO T

OLR I

222PF T

T T

T R

LCCT 3

O RRP F

I T0 ALALA ALT A

M 2

T F

S LD N

PE F2F R ARAR RAC CRRX UR E

V PR 01 0TB BUBUB BUE EE 7

OE T

LS L

ROO f

P NI I NI NI I NL RPPF 8

P O

0 R

L ORF BTBI L LALAL LAE E

0 UO N

C DO I

FP I

I OA Af AMA Af PDD S

SR ET W

V 1

1 LTLPC C

C C

C E

RRB L

P L

1 TA VGL f

ANA D

D DC DAAI E

L R

AC V

LNV CI CTE IE3E8 8EA RCCL 2

EL I

A CI L

VI O

S T

T TL A

A L

W L8I O V

TK AP CBBC MA A7O D XAC YPYET NAMA4 4

5 F

FT GDC DQ QDE I I HT V

n ESE C E EEEEC LLLLLALL R, LLLX A

CS C

nID 8

I TI K

I I I II LI I I

RSR AAAC L

N F.

IS L

m E C, 9

V,T V,T E A, VA A. VA A, NU A,V 5 C,C,C,E AA P1 nI m

nV C,R A 0

EUI A

,RI L A

7 7O3O C.

2 3

4A5 0

EEDC, R, 1

,4 6

0F

,R 6

4 4

m8 4

0Om 4

8AB 7S7D7F 7S2 401 1

f 0

N 4T6TF 1 E1 E1 1 E -

7889 3041 1

0G3 1

1 S1 5N9E O

1 1

1

- R - R -. - R3 3336 2R2 -

- V -

I

- P - P-3U3U3L3L 4

- F - 3 3

- I - T 3

3L3 T

3U3L 8 0T0T0A0T0 8888 7

70 0

2T3O 0

0V0 P

0 0

6 0C0C0V0C -

6666 6D60 0

9A0 0

0 0

Y I

0A0A0

- A - A -

- AN 0000 0E0 -

0R04

- L

- E -

R R 3 -

CFCFC.CFA

- V - V V

- B -

VA VRV t

A C

T4T6i I L I UI UI J

t t MT S0SC CO IIIN CJ CL C R L f f 1

R 1

S F1 F1 T LNLNLNLP C TTTP L! LL FT XLLE LP LSL M

E

- A - A - A - A -

- E - -

- U

- A -

F 1 0

1 1 1 1 2R1 1 1 A 2C1 A A - A

- N -

D 23231 1 1 1 1 1

1 1

1 E1 1E1 I

f F

F I

f S

5 5

5555 5

55 5

5 5

5 Y

8 8

8888 8

88 8

8 8

8 L

/

////

/

//

/

I 0

0 1

4 4

4 7772 2

70 3

5 1

0 0

0 TPE 1

1 2

0 0

1 0001 1

12 0

0 2

2 2

2 NMT

/

////

/

//

/

0OA 6

6 6

6 6666 6

66 6

6 6

6 1 CD 0

0 0

0 0000 0

00 0

0 0

0 f

E C

S N

S A

E N

R A

A 0

A A

EED E

D 7

3 2

3 4

5 5

01 8

4 0

4 8

8 T

D 4

6 F

7 7

0 7889 3

44 6

0 3

6 4

4 N

A 1

1 1

2 3336 2

21 1

5 9

1 1

1 IA S

3 3

8 3

3 3

8888 7

73 3

2 3

3 3

3 M

Y 0

0 6

0 0

4 6666 8

80 0

9 0

0 0

0 S

0 0

0000 0

00 0

0 0

0 TN C

N E

N C

C C

C A

V V

V f

U T

T M

I I

L MMMT S

SC C

I I

C C

C l

F F

F T

L L

C I T T P L

L L F

X L

L L

L RT 2

2 1

1 1

0 1 1 1 1 2

1 1 1

2 1

1 1

1 S

U N

p 4

6 2

5 6

7 8

0 5679 0

04 4

0 6

7 3

4 I

4 8

8 9

9 9

9 6

6666 8

23 6

9 9

5 5

m f

4 7

4 4

1 2222 7

67 0

0 8

8 9

9 3

3 2

8 8

9 9999 0

1 1 C.

8 8

8 3

3 9

9 9

9 9999 0

00 z

2 2

2 2222 3

33 5

5 5

5 t1 A

A A

A AAAA A

AA A

A A

A f

s@'

I j{

l j-J

INSTRLfENT 11AINTENANCE 110NTILY Slft1ARY 07-09-85 PAGE 2 Cow tR.COE U FINC SYS ADOR ESS. DATE.... DESCR IP T ION..................................... CORRECTItE ACTION.............

ENSURE VLV IS SEATING PROPERLY AIO RECAL PER THIS FR A528955 1 LEV 003 164 06/20/851-LCV-003-164,CECX VLV FOR PROPER STROKE Af0 VLV STRONE WAS NOT CALIB PROPERLY.

ENSLRE VLV IS SEATING PROPERLY RESTROKED ULV AIO RETURED TO SERV

(.528957 i LIV 003 164A 06/20/851-LCV-003-164A,CEIX VLV FOR PROPER STROKE Am PACKING WAS BAD IN VLV. REPHC,KED SEATIE VLV-LLERICATING STf1 AM) RESTROKED VLV AM) RETLRED TO SERV A528972 1 tfV 003 148A 06/25/85 1-LCV-003-140A,u!N NPFRDu VLV IS LEAKING TEU CLRRENT TO PRESS CONVERTER WOLLDH'T CALIB. REPLACED TE CLRRENT TO PRESS CONVERTER A528973 1 LIV 003 148 06/25/851-LCV-003-148, NIn VLV IS LEAKING TEU NOE. VERIFIED PROPER CAL STROKE Af0 PRESSLRES (529094 2 PS 003 150A 06/08/85 2-PS-003-150A, REPLACE DAMAGED INSTRLFENT TEE WAS BAD ON SENSE LIE. REPLACED INST LIE TEE; A SHORT SECT OF PIPING; AfC RETLRED LOOP TO SERV A329618 1 LIC 003 174 06/19/851-LIC-003-174 IM) 72% WEN LVL IS ABOUT 33%

PLLLEYS THAT CONTROL Ito WERE BIM)ING.

ADJUSTED CCHTROLLER NOUSING TO PREVENT BIlOING A531024 1 LT 003 174 06/04/85 1-LT-003-174, min LI 3 174 It01 CATES ZERO WHEN 4 WIRIlO WAS C0hpECTED TO TE WRONG b

OTER NARROW RA>CE FOR TE SATE LOOP DOICATES TERMINAL. CCRRECTED TE WIRING AlO T

41%

RETLRED TO SERVI A531185 1 PI 003 132A 06/09/851-PI-003-132A, mIE l@RDu PRESS Il() IPOICATING 930 PRESS XITTR AELIFIER CARD HAD A BAD PSIG WITH PfF ICT RL9e(ING REGLLATCR IN TE PLR SUPPLY SECT OF TE CARD. REPLACED REGLLATOR IN PWR SLPPLY;REDtLIB XMTR AIO RETURED LOOP TO A531193 1 LI 063 109 06/11/85 1-LI-063-109 VERIFY PROPER CALIB AIR IN SENSE LIE. VENTED UPPER AM) uuR BEu0uS A531194 1 LI 063 99 06/11/851-LI-063-99, VERIFY PROPER CALIB AIR IN SENSE LIES. VENTED IFPER AM)

LOER BELLOWS A531195 1 PI 063 100 06/11/851-PI-063-108, VERIFY PRESS IM)

ROOT VLV CLOSED AM) DRAIN VLV OPEN.

CLOSED DRAIN VLV AIO OPEED ROOT VLV A531315 2 085 ft2 06/10/85 2--085-ft2,RPI IS DRIFTING )12 STEPS FROM 228 CORRODED CGGECTION ELDED CABLE PER STEPS IMI 85

.A531321 2 LI 063 174 06/24/85 2-LI-063-176, min CI)MTAIPfENT SLFF LVL IM) IS OUT XMTR WAS F0Lse OUT OF CALIB AM) WOLLDH'T OF TCLERANCE/SI 2 CALIB. REDtLIB XMTR AFTER BACKFILLING FILLED SENE LEG AM) RETLRED TO SERV A338637 1 099 TR>M 06/20/851--099-TRNA,DutDC FT 18 SI 93 SSPS FT TE LBOER REACTIR TRIP BKRS ERE RACKED OUT DURING VG.TAGE FETER DID NOT GO TO 'O' VOLTS TEST LMIOf CAUSED PROBLEM. CHANCED TE t#OER VG.TAGE CARD BEFORE REALIZING CAUSE CF PROBLEM A541768 2 XX 092 5005 06/12/85 2-XX-092-5005, REPLACE GAIN POTENTICRETER ON 8 DIRTY GAIN POT. REPLACED CAIN POT ON B

j E

D D

B EE B

I E

T I

R N

V H

S S

S CR E

O N

R t1 T

S N

AL P

O E

F TE I

G LT D

T S

D

' R N

PE F

O R

R O

T L

E NP L

I ER A

P EE O

P O

OG A

C O

1f R

ACL F

P

.TE C

A L O E

R O

T I L N

p L

E L

T N

O TF N

TVO RE n_ T I

N rD R

P A

F NA EENRR EC A

I PED E

H R

E f CEET DV I

I G

A NE R

R N

C E

f R F I t SN G

FRL T

RE P

iO GVe O

R D

OUL M

ER L

GT I RCOC OE E

D TI X

TR A

ELI A LEI T TS C

E EEF E

RU C

LALC ASL L

A C

GRE RW V

EC E

I CAI ADA EO L

A R

R TO I

V R

HE O

DO C

VT ETDEE P

L HPAO.

ML T

NE WRDP A

E P

XF C

O}

EI F

ERR GD CAE R

E E

CT DDI RDI L DEL A.

E SD C

PAIL FEIFTO 0 E L

F M

E f N

R FE I

S O

I E

R I

f I

CL D

SE P

RB RRRRA AI T

Y T

I EA EC F

IWEA EL E T

NLm RC C

T O

S RA O

REVI PTV0DTSE A

R P

A PL TR R

E AESOR I

f I

Dl

.F W

P T

SC A

R EP E

D N

ELFEI EO RRTRR(U OE SEVEE C E IEDf C G

I W

OMLEAA I

I N

A UL CT EE E

EDO.I O f

T I

G

( AF U

TTT TL REl SVNAHI ARE C

RAR RLTO FO RRN.RE CC SR T

RW EGEYE E

S O

LEEEBE SA. EE 8

.A

.R E

O UT NS ATARAEIS PAVVRI VP UOEOMLRLNA TPEOCSEIEEEG' R

L R

KI TOCN R

L OV EEORODAOPONOE O

RORI RI EO AOH C

DPDDDLRL OLRCCCCCC SRI PTI CHOHETR R

R R

R P

D E

E E

E 9

D E

P P

N 8

B 1

E T

I 2

T N

R R

N N

I N

E W

E E

Y 3

O O

S E

V E

S L

L L

/

V S

L L

L R

R R

7 1I B

N O

O O

O E

E E

E 8

1 A

O R

R R

R P

C T

T 2

R C

T T

C A

E E

D mT I

D N

N N

N R

P r

r I

E H

L E

O O

O P

I 0

0 S

L t

X P

P C

C C

C I

I L

I F

P P

L T

T i.

I FWF A

I E

E E

E O

N N

t F

0. O R

T T

R E

E e

S 1 R

T A

A A

A T

T T

r S

E EFS E

S R

R R

R N

O O

N T

P B

BLBLBLO P

P T

I HAB A

W I

I AI AI AC O

I LXFI E

S E

L LULULU N

N H

L E

L P

I LR A

ANANANT I

I G

LA E

HAC C

CACACAO A

A S

G NGLC R

CS 1

1 1

N F

f f

G G

E N

I DA B

T D

D D

D O

I SL T

T I f E N

NDNDNDS f

E E

D S

NBHO O

LRS A

AEAEAEE C

C N

E TH N

AP T

T TO A

A T

E SDI C

C NL WDQDCDAHAD A4 5

L L

S LUL L

2P GA 8

P P

N KE L

L n9I I U I II I I I V E

E I

K CI MI I

I K

LN LLLLLLL 9

R, HFW W

mI C C

E S,0 A R

l A, f A, VA A,VA A,VA V, A

0 0

E C

1

,rO 7

0 0

2 C.

C,2 0 8 7I 6

7 0

H A

8 6

4 1

8 L,

4S 5S6S7S1 4

0 0

N 0

0 2404 6

0F2 1 E 1E1 E1 E1 O

5 5

3 1

0241 1

5O2

- R

- R R

R-I 4

3L 3

3 l 3L 2 I

T 2

2 0

7Y70 3

3 2S7 0T 0T0T0T6 P

9 9

7L73G0 0

9N8 0C 0 C )H AC0C0 R0R0R"S Y

I 0R00N0 0

0O0

- A

- A -

- E - - I -

- I -

CE CFCFCFV EXEXE2CTPTTWM R

R A

C 1f XTS I

I L I UIL CO 1

4 AXAXAHE4ROPFOL L

XCL 44 4HLN4NLT S

T E

R - R - R - P

- - H -

- E -

A - A A - U J

D D2D2D1 S1 P1 1 S1 1

2S2 1 f 1

1 1 1

1 1

1 r1 A t

f 1

S 5

5 5

5 55 5

5 5

Y 8

8 8

8 88 8

8 8

L

/

//

/

I 2

2 3

1 1 0 0

0 8

1 4

4 4

TpE 1

1 0

0 02 2

2 2

1 0

0 0

Nr T

/

//

/

OoA 6

6 6

6 66 6

6 6

MCD 0

0 0

0 00 0

0 0

E C

S N

S A

E N

~

6 7

A A

7 E

C 0

0 0

2 G

4 0

8 6

4 1

8 T

D 0

0 0

24 4

6 0

2 4

5 6

7 1

N A

5 5

2 1

02 1

1 5

2 1

1 1

I A

S 2

2 3

7 70 3

3 2

7 3

3 3

3 2

M Y

9 9

4 7

73 0

0 9

8 0

0 0

0 6

S 0

0 0

0 00 0

0 0

d T

e N

C N

t E

N A

C C

V s

F U

X X

2 T

TT 1

1 f

1 X

S I

I I

I E

i L

F X

X H

L PF L

L X

L L

l RT 2

2 1

1 1 1 1

1 2

2 1

1 1

s S

U d

N r

P 9

0 5

0 1 9 6

8 9

5 3

4 5

6 7

o I

6 7

79 3

3 7

5 6

6 6

c r0 7

7 8

9 99 8

8 7

9 8

8 8

e C.

1 1

1 3

33 5

5 8

8 4

4 4

r 4

4 4

4 44 4

4 4

4 6

6 6

R S

S 5

5 55 5

S 5

5 5

1 F

A A

AA A

A A

5

,wY

INSTRLFENT MAINTENANCE fl0NTM.Y SurtlARY 07-09-95 PAGE 1 Corp

^

l

_ tR. HIST U FINC SYS ADDRESS. DATE.... DESCR IP TION,.................................... CORRECTIE ACTION.......................

A233485 2 FT 003 155 06/03/85 2-FT-003-155 VERIFY CALIB 0F 2 FT 3155 ADO 2 FM OUT (F CAL I/I RECAL 2 FM 3 155A 3155A UP TO TE REST POINT TP13 IN 2 L 11A A530605 1 PM 068 690 06/03/851-Pft-068-690,1668UT TO RVLIS IS READING LOU.

DUT OF CAL I/I RECAL PM 68 69D CECK CAL 2 records listed.

+

9

.=

e--

f

[

?

i Machtnical Maintentnce Section June 1985 l

Unit 0 1)

Repaired the potable water line to the Field Services' Building.

2)

. Completed the monthly inspection of the diesel generators.

. 3)

Completed the 1-BB diesel generator annual inspection.

Unit 1 1)

Replaced the.0-ring below the #1 seal housing on #4 reactor coolant pump.

2)

Completed reassembly of the main generator.

3)

Installed, adjusted, and/or aligned 38 damage hangers in the Turbine Building:on the steam dump line.

4)

Replaced the solenoid valve on 1-LCV-62-118.

5)- Replaced the main flange 0-ring and installed an additional 0-ring in the bore below the #1 seal housing on reactor coolant pumps #1 and

3.

6)

Applied RTV to the #1 seal housing and main flange on #1 and #3 reactor coolant pumps to avoid any oil which could seep in between the main-flange'and the #1 seal housing.

7)

Replaced a defective regulator on 1-FCV-1-182.

8)

Installed an isolation valve on the relief. valve-discharge to build up the auto stop_ oil. pressure on the EHC system.

Unit 2 1)

~Furmanited 2-FCV-3-100, 2)

Installed a furmanite box over a leaking-gland ' seal water elbow to stiffen the piping and prevent shearing of the piping at the threaded ~ joint.

I h'

SUMMARY

OF WORK COMPI.ETED MODIFICATIONS r

JUNE 1985 NUREG 0588 ECN 5970 - MOV Operator Replacement One remaining operator will be replaced the first week of July.

ECN 6278 - ABGTS and EGTS Heater Controller Replacement Two rubber hoses were replaced the first week in June.

Appendix R ECN 5435 - Install Weatherstripping on ABSCE Doors We started replacing the weatherstripping on several ABSCE archi-tectural-doors. Materia? was ordered for heavy equipment doors.

ECN 5484 - Emergency Lights This work is complete.

ECN 6235 - Reroute Various Ca,bles Work continues with five workplans in work.

ECN 6305 - Elevation 714 Fire Barrier' We are in the process of removing interferences required to install wall.

W'e are also laying out the wall _and installing the baseplates.

ECN 6319 - Fire Protection Piping We have rerouted approximately 30 percent of the heads required to be relocated. ';isrk is ongoing to plug sprinkler heads that are to be abandoned (approximately'70 percent complete).- We are adding heads

. on elevations 734 and 749 and are laying out work on elevation 714 for relocation. Work continues on the workplan to install two new deluge valve systems.

,1 i

Other Items f

ECNs 2783 and 5202'-:Fifth Diesel Generator 3

Permanent' power tie-in will be made in July. The ERCW discharge 4

(ECN 5202) project has been completed, and the backfilling has been done. Work on permanent power.to the building is continuing. A punchlist'is being prepared for the incomplete items.

s

.jk 14

.t

' y

Other Items (Continued)

ECN 5009 - ERCW Piping Changeout from Carbon Steel to Stainless Steel The changeout for the auxiliary feedwater/ boric acid area cooler (train B) is complete. Work has started on train A.

ECNs 5111 and 5503 - Office and Power Stores Facility Work is continuing to complete the remaining punchlist items by July 15, when Power Stores will begin moving into the new facility.

Interior items include wiring for alarms and fire protection, cleanouts for subdrain, high pressure fire protection, and completion of the pallet stacker system. Exterior items include yard grading, catch basins, sidewalks, handrails, and manhole covers.

ECN 5119 - Install Radiation Monitor Cables in Conduit Final tie-ins are underway. Five monitors remain.

ECN 5194 - Iodine Monitor Doors A230 and A231 have been tied in and are awaiting acceptance testing.

ECN 5200 - Postaccident Sampling Facility Rework of postmodification test deficiencies is in hold for the final design of one level loop.

ECN 5237 - Laundry Facility Remaining work is on hold until the last wall is built.

ECN 5373 - Condensate Demineralizer Air Compressor This project is almost complete, with the exception of the installation of the motor coupling and pressure control instrument. Functional testing of the air compressor will be done with the help of a vendor representative during August. Construction is trying to buy a control box to replace a faulty one.

Compressor startup is awaiting this new control box.

ECN 5599 - Fifth Vital Battery The' Appendix R-related conduit wrap is almost complete. Labels for the breakers have arrived. The protective coating in the battery room is to be done during August.

ECNs 5609 and 5610 - Makeup Water Treatment Plant This project is near completion. Remaining punchlist items include modifications to the demineralizer system and tank, interior potable water work,'and installation of a septic tank.. -

(1 Other Items (Continued)

ECN 5613 - Installation of Emergency Lights Work has commenced to install emergency lights in the Service Building.

Five of nine are complete.

ECN 5657 - Installation of Isolation Valves, Moisture Separator Reheaters The unit 2 workplan to install approximately 150 isolation valves is written and in the approval cycle.

Insulation reinstallation on unit I still remains incomplete.

ECN 5664 - Replace Relays in Wells Fargo Alarms O

Remaining work has been restarted and will continue during Power Block reconfiguration.

ECN 5795 - Field Services Building Fire detection system work is in hold for materials.

ECN 5841 - Hot Machine Shop All work is complete with the exception of the hallway on elevation 706.

This will be completed when Power Stores is moved to their new facility.

We are still awaiting drawings on the monorail to be added to the decontamination room.

ECN 5855

-Replace Air Lock Doors A56 and A57 We have started working on chipping concrete columns between doors to ready wall for air tanks. Workplans are being written to install doors and hardware.

ECN 5878 - CDWE Outage Work The CDWE outage is in progress, and the modification work is going well.

We are'in the process of expediting some material that is slowly coming in.

ECNs 5932 and 5935 - Power Block Implementation Work is continuing on Power Block-related cameras, fence sectors, gates, doors, and E-fields. Most of the primary work for. Power Block-related roads is underway. Also added to the scope of the project are the installation of high mast lighting and painting of ERCW cofferdam for improved visibility. A workplan has been initiated for the high mast lighting.

Other Items (Continued)

ECN 5938 - Feedwater Heater Replacement Monorail and electric hoist work required to handle feedwater heater Nos. I and 2 has been completed. Work is in process on the platforms needed to bring the feedwater heaters into the Turbine Building. All the Nos. 3 and 4 feedwater heaters from Hartsville have been modified and are being hydrostatically tested and flushed.

ECN 5990 - CDWE Outage Work The CDWE outage is in progress, and the modification work is going well.

We are in the process of expediting some material that is slowly coming in.

ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced.

ECN 6202 - Component Cooling System Surge Tank Instrumentation All mechanical work has been completed.

ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete. We are waiting for a Technical Specification change to place the circuits in operation.

ECN 6326 - CDWE Outage Work The CDWE outage is in progress, and the modification work is going well.

We are in the process of expediting some material that is slowly coming in.

ECN 6342 - Health Physics Calibration Facility This project has been completed.

ECN 6351 - CDWE Outage Work The CDWE outage is in progress, and the modification work is going well.

We are in the process of expediting some material that is slowly coming in.

ECN 6362 - CDWE Outage Work The CDWE outage is in progress, and the modification work is going well.

We are in the process of expediting some material that is slowly coming in. -,,,

=0ther Items (Continued)

ECN 6417 - CDWE Outage Work The CDWE outage is in progress, and the modification work is going well.

We are in the process of expediting some material.that is slowly coming in.

We are waiting on the Office of Engineering to complete their work on ECN 6417.

Training Buildings Exterior work is near completion. The sidewalks are almost finished.

Corapleted interior items include lighting, walls, ceilings, doors, and windows. The HVAC system is approximately 75 percent complete. This project is running on schedule to be completed by July 29, 1985.

Miscellaneous Yard Work Roads have been paved to the cooling towers and the Health Physics Calibration Facility, near the switchyards, west of the Office and Power Stores Facility, and leaving the plant along access highways. The pavers have left the project for now and will return in August.

Power Block-related fencing and road work are being done. A workplan has been initiated for completion of the staff parking lot.

1 L J

~

h e

TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 July 15, 1985 Nuclear Regulatory Commission f

Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - JUNE 1985 Enclosed is the June 1985 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Mant.ger Enclosure cc (Enclosure):

Director, Region II Director, Office of Fbnagement Nuclear Regulatory Commission Information and Program Control Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Marietta Street Washington, DC 20555 (2 copies)

Suite 3100 Atlanta, GA 30323 (1 copy)

INPO Records Center Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway and Enforcement Atlanta, CA 30339 (1 copy)

Nuclear Regulatory Commission Washington, DC 20555 (10 copies)

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

Mr. R. C. Goodspeed MNC 461 Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, PA 15230 (1 copy) 4 6

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

Sequoyah Nuclear Plant i

1983-TVA 50H ANNIVERSARY An Equal Opportunity Employer

-

ML20135C291

Text

SUMMARY

Navigation menu

Search