ML20215C171

Monthly Operating Repts for Jul 1986

ML20215C171
Person / Time
Site:	Sequoyah
Issue date:	07/31/1986
From:	Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8610100134
Download: ML20215C171 (58)

Text

-.

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

" JULY 1986" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 s

DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:

M 8

/t7 P. R. Wallace, Plant Manager i

8610100134 860731 DR ADOCK 05000327 PDR l

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c TABLE OF CONTENTS 4

4 I.

Operational Summary Page Performance Summary 1

Significant Operational Events 1

Fuel Performance and Spent Fuel Storage Capabilities 2

PORVs and Safety Valves Summary 2

Licensee Events and Special Reports 2-3 Offsite Dose Calculation Manual Changes 3

II.

Operating Statistics A.

NRC Reports Unit One Statistics 4-6 Unit Two Statistics 7-9 B.

TVA Reports Nuclear Plant Operating Statistics 10 Unit Outage and Availability 11-12 Reactor Histograms 13 III. Maintenance Summary Electrical Maintenance 14-16 Instrument Maintenance 17-24 Mechanical Maintenance 25-29 Modifications 30-38 IV.

Environmental Qualification (EQ) Summary 39-45 l

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4 OPERATIONAL SLMfARY

9 PERFORMANCE SlHMARY July 1986 6\\

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

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 I has been off-line 343 days.

Unit 2 has been off-line 344 days.

SIGNIFICANT OPERATIONAL EVENTS l

Unit _1 Date Time Event j

07/01/86 0001C The reactor was in mode 5.

The administrative

]

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

07/31/86 2400C The reactor was in mode 5.

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

Unit 2 Date Time Event 07/01/86 0001C The reactor was in mode 5.

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

07/31/86 2400C The reactor was in mode 5.

The administrative i

shutdown due to design control review, config-uration control updating and resolution of l

significant employee concerns continues.

t FUEL PERFORMANCE Unit 1 2A The core average fuel exposure accumulated during July was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.

Unit 2 The core average fuel exposure accumulated during July was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.

SPENT FUEL PIT STORAGE CAPABILITIES The total storage capability in the spent fuel pit (SFP) is 1,386. However, there are five cell locations which are incapable of storing spent fuel. Four locations (A10, All, A24, A25,) are unavailable due to a suction strainer conflict and one location (A16) is unavailable due to an instrumentation con-flict. Presently, ihere'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

Ks FORVs or safety valves were challenged in July 1986.

LICENSEE EVENT REPORT (S)

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

1 l

LER Description of Event i

1 1-86026 On June 29, 1986, at 0724C, the sudden pressure relay failed i

on common station service transformer (CSST) D.

As a result of this occurrence, all four diesel generators started and the fire suppression system also actuated spraying "D" CSST with water. A microswitch inside the relay housing had shorted by either condensation or a leaking gasket.

The relay was replaced and "D" CSST was returned to service.

1-86027 During a technical specification (TS) review, it was discovered that Surveillance Requirement (SR) 4.8.1.1.2.s.4.c was not being performed as required. This requires a diesel generator (D/G) start from a simulated loss of offsite power (LOP) in conjunction with an engineered safety feature (EFS) actuation test signal. This surveillance cannot be performed l

due to the logic circuitry at Sequoyah. However, verbal agreement with the NRC and TVA was reached, each knowing that i

this SR could not be performed.

It was also agreed to i-leave the SR in the TS.

A TS change was submitted to the L

NRC to remove this SR.

These understandings were in effect l

prior the initial start-up of Sequoyah. Another change for this SR will be submitted to the NRC.

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SPECIAL REPORT (S) 4 There were no reports submitted to the NRC in July 1986.

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

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OPERATING STATISTICS (NRC REPORTS)

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7 OPERATING DATA REPORT A

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. DOCKET NO. 50-327 DATE AUGUST 11,1986

w COMPLETED BY D.C.DUPREE i "

i TELEPHONE (615)870-6544 7 -

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,2 OPERATING STATUS

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W " f tl, UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1

, NOTES:

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y 2.' REPORT PERIOD:. JULY 1986 y

fg3. l LICENSED THERMAL POWER (MWT):

3411.O 4.

NAMEPLATE RATING',(SROSS MWE):

1220.6 q;

5. t DESIGN ELECTRICAL RATING (NET MWE):

1148.O 76.' MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1183.O

, s 7.. MAXIMUM DEPENDADLE CAPACITY (NET MWE):

1148.O C.'. 8.MIF CHANGES OCCUR IN CAPACITY. RATINGS (ITEMS NUMBERS 1

'['

[3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:

1 I

9.

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

10. ~ REASONS FOR RESTRICTIONS, IF ANY:

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THIS MONTH YR.-TO-DATE CUMULATIVE

'11. ' HOURS IN REPORTING PERIOD 744.00 5087.00-44568.00

. 12.NLMDER OF HOURS REACTOH WAS CRITICAL 7 213.i'. REACTOR RESERVE SHUTDOWN HOURS

~

O.00 0.00 24444.91 0.00 5-O.00;

- 0.' 00 V714.#i HOURS GENERATOR ON-LINE O.00 O.00 23871.13 l E'115.-UNIT 1 RESERVE' SHUTDOWN HOURS 0.00 '

'O.00

0. O0'

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4 116. GROSS THERMAL ENERGY GENERATED (MWH)

O.00 O.00 77060971.91 l ~

17. GROSS ~ ELECTRICAL ENERGY GEN. (MWH)

O.00 O.00 25976386.00

18. NIT ELECTRICAL ENERGY GENERATED (MWH)

-3653.00

-24034.00 24918703.00 19.' UNIT SERVICE FACTOR O.00 O.00 53.56 i

-20.

UNIT AVAILABILITY FACTOR O.00 0.00 53.56

' 22. UNIT ~ CAPACITY FACTOR (USING DER NET) 0.00 0.00 48.70

21. UNIT CAPACITY FACTOR (USING MDC NET)

O.00 0.00 48.70

23. UNIT FORCED OUTAGE RATE 100.00 100.00 30.39 24.-SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):,

i

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^)

2 5.'

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

l STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, l

CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT ElPLOYEE CONCERNS.

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~ NOTE THAT THE THE YR. -TO-DATE AND A..

Ti N:',

CUMULATIVE VALUES HAVE BEEN UPDATED.

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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL

., g DOCKET NO. : 50-327 UNIT : ONE DATE : AUGUST 12,1996 COMPLETED BY : D. C. DUPREE TELEPHONE :CG15)S70-6544 MONTH: JULY 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWe Net)

DAY CMWe Net) 01 0

17 0

02 0

18 O

03 0

19 0

04 0

20 0

05 0

21 O

06 0

22 O

07 0

23 0

08 0

24 0

09 0

25 0

10 0

PG O

l 11 0

27 0

t 12 0

28 0

13 0

29 0

14 0

30 0

l

[

15 0

31 O

r 16 O

i l i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah One DATE August 5, 1966 COMPLETED BY D. c. Dupree REPORT MONTlf JULY 1986 TELEPHONE (615)870-6544 m

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o Cause & Corrective 5O "c

$u Licensee E 2, go, Action to No.

Date g,

3g gtg Event gg gj o

N 2:O 2

fgN Report #

gu gu Prevent Recurrence 5~

$05 R

Design Control, Configuration Updating, and 7

851220 F

744 F

9 Employee Concerns.

1 4 Exhibit G-Instructions 2

3Hethod:

IF: Forced Reason:

i 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 i

D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161) i E-Operator Training & License Examination Outage F-Administrative 5-Reduction 5 Exhibit I-Same Source G-Operational Error (Explain) 9-Other

!!-Other (Explain)

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OPERATING DATA REPORT S;, }

DOCKET'NO. 50-328 DATE AUGUST 11,1986 COMPLETED BY D.C.DUPREF TELEPHONE (615)B70-6544 2

I OPERATING STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2

NOTES:

, 2.

REPORT PERIOD: JULY 1986 3.

LICENSED THERMAL POWER (MWT):

3411.0 (4.

NAMEPLATE RATING]QROSS MWE):

1220.6 2 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.

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

10. REASONS FOR RESTRICTIONS, IF ANY:

5 '

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 5087.00 36528.00

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

13. REACTOR RESERVE SHUTDOWN HOURS 0.00

O.00 O. OO

'14. HOURS GENERATOR ' ON-LINE 0.00

'O.00 21'494.42

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

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

17. GPOSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 23536780.00

18. NET ELECTRICAL ENERGY GENERATED (MWH)

-5769.00

-34539.00 22597418.60

19. UNIT SERVICE FACTOR O.00 0.00 58.84 1

20. UNIT AVAILABILITY FACTOR O.00 0.00 58.84

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 53.89

22. UNIT' CAPACITY FACTOR (USING DER NET) 0.00 0.00 53.89

23. UNIT FORCED OUTAGE RATE 100.00 100.00 32.06

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:

THE RESTART OF UNIT-2 HAS DEEN SCHEDULED FOR JANUARY 1987.

1

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

'N.

. CUMULATIVE VALUES HAVE DEEN UPDATED.

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O SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL 73 DOCKET NO. : 50-328 UNIT : TWO DATE : AUGUST 12,1988 COMPLETED BY : D. C. DUPREE TELEPHONE :C615)B70-6544 MONTH: JULY 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CMWe Net)

DAY CMWe Net) 01 0

17 0

02 0

18 0

03 0

19 0

04 0

20 0

05 0

21 O

OS O

22 0

07 0

23 0

08 0

24 0

09 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

i 15 0

31 O

i 16 0

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4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE August 5, 1986 COMPLETED BY D.

C.

Dupree REPORT MONTH JULY 1986 TELEPHONE (615)S70-6544 a

So Cause & Corrective l$ oo O Licensee E <r cs m

30 t8 5 E Event 0 E!

Action to

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No.

Dat,c e

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SU$

Report #

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7 850821 F

744 F

4 Design Control, Configuration Updating, and Employee Concerns, a

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4 Exhibit G-Instructions 3F: Forced Reason:

Method:

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 D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction S

G-Operational Error (Explain) 9-Other Exhibit I-Same Source H-Other (Explain)

4 4

'h OPERATING STATISTICS (TVA REPORTS)

iV A 7382A (ONP4-84 NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant A

Period Hours 744 Month July gg 86 Item No.

Unit No.

UNIT ONE UNIT TWO PLANT I

Averaoe Hourly Gross Load. kW 0

0 0

2 Maximum Hour Net Generation. MWh 0

0 0

3 Core Thermal Eneroy Gen. GWD (t)2 0

0 0

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

0 0

8 5

Gross Electrical Gen., MWh 0

0 0

5 6

Station Use, MWh 3,653 5,769 9,422 h

7 Net Electrical Gen., MWh

-3,653

-5,769

-9,422 5

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

Accum. Core Avg. Exposure, MWD / Ton!

0 0

0 10 CTEG This Month,106 BTU 0

0 0

11 SGTEG This Month,106 BTU

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

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

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

0 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 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 Startuos 0

0 0

22 Reactor Cold Startuos 0

0 0

23 g

24 Gross Heat Rate, Btu /kWh N/A N/A N/A 25 Net Heat Rate, Btu /kWh N/A N/A N/A 5

26 D

27 g

28 Throttle Pressure, psig N/A t.'/ A N/A l

29 Throttle Temperature. F N/A N/A N/A l

d 30 Exhaust Pressure, InHg Abs.

N/A N/A N/A l

g 31 Intake Water Temp., F N/A N/A N/A i

F-32 1

33 Main Feedwater, M lb/hr N/A N/A N/A y

34 k

35 36 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.841(

j 39 Oil Fired for Generation, Gallons 19,470 2

40 Oil Heatino Value. Btu / Gal.

138,000 41 Diesal Generation. MWh 295 d?

Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor. %

3 43 N/A N/A N/A N/A N/A N/A Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.

j 2(t) indicates The mal Energy.

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m Date Submitted Date Revised o,_m..,....-...

TVA 6560C (PP 3 761

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UNIT OUTAGE AND AVAILABILITY SEQUOYAll Nuclear Plant i

Licensed Reactor Power 3411 MW(th)

Unit No.

ONE Generator Rating 1220.5 MW(e)

Month / Year July 1986 Design Gross Electrical Rating 1183 Mw Period Hours 744 I

Teme Unet Avaelable T6me Not Available M

F UNIT CORRECTIVE AC1 TON Total Gen.

Not Used Turbene Gen.

Reactor Un.t i

N DUR DJV Hrs l Men Hrs ! Men Mrs ! Man Has Man Hrs l Men Hrs ! Men Mrs l Men Hrs ! Min Mrs ' Men REACTOR OUTAGE PTTO I

00s 00 00 ; 00 l

246 00 24a 00 24 joO 24 s00 i

Design Control, Configuration N/A Mode 5 1

2 OOL 00 00,00 t

24l 00 24' 00 24 #00 24 ! OO 8

Updating, and Employee Concerns 3

00' 00 008 00 4

24 00 24: 00 24 800 24 ; 00 l

4 00i 00 00 l 00 l

248 00 24 ' 00 24!OO 24 800 s

e 5

00 00 00,00 i

24' 00 24l 00 24100 24 ?OO i

6 005 00 001 00 i

24' 00 24i 00 24800 24 i OO 7

00! 00 00 ' 00 24l 00 24 ! 00 24 l 00 24 800 l

8 00: 00 00' 00 l

24: 00 24i 00 24 a00 24 l 00 i

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00 l 00 00i 00 e

24' 00 248 00 24 ! 00 24 #00 3

e 10 00i 00 00800 3

24i 00 24l 00 24 iOO 24 !00 e

11 001 00 00 3 00 l

248 00 24, 00 24 100 24 iOO e

_ 12 006 00 00 ! 00 1

24l 00 248 00 24!00 24 500 t

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13 00 00 00 i 00

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24' 00 24i 00 24a00 24 400 e

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17 001 00 00; 00 24i 00 248 00 24l00 24 ! OO s

18 00! 00 00i 00 24? 00 24 l 00 24 800 24 l00 6

i 19 00l 00 003 00 i

24i 00 241 00 24iOO 24 iOO

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24! 00 24! 00 24!00 24 100 i

l 21 00i 00 00I 00 l

24; 00 24 i 00 24,'00 24 300 i

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24! 00 24i 00 24l 00 24 ;00 t

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248 00 24 l 00 24800 24300 i

26 00 00 00s 00 1

24; 00 24i 00 24 l 00 24 000 t

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27 00 00 00! 00 l

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d 30 00i 00 00i 00 24l 00 24i 00 24 i 00 24 800 i

1 31 00, 00 001 00 i

24i 00 241 00 24 ? 00 24 100 8

e Total 00! 00 00] 00 7446 00 744! 00 744 i 00 744 l 00 J

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4 SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -

90 -

80 -

70 -

60 -

50 -

40 -

30 -

20 -

10 -

0

-10 0

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

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HAINTENANCE

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, ELECTRICAL MAINTENANCE MONTHLY

SUMMARY

04-86 PAGE 1 COMP s

{ MR. COMP U FUNC SYS ADDRESS. DATE.... DESCRIPTION............................. CORREC TIVE AC

.[B1057982MVCP070 0140 03/03/86 2-MV0P-070-0140-Br[*NPRD*3,VLV POSSIBLY THE CLOSED AUX CONTACT WAS

$10CFR50.49* NOT STROKE OPERATE DIRTY. CLEANED AUX CONTACTS USING MAINTENANCE INSTRUCTION 10.40

B108275 2 MV0P 074 0012 05/19/86 2-MV0P-074-0012-A,[*10CFR50.498,1NPRD*], VLV WAS OVERSEATING ON CLOSE CYCLE DUE VLV IS SEATING WITH EXCESSIVE THRUST TO TOROUE SW SETTINGS BEING OUT OF ADJUST PER M111.2A AND MOVATS ADJUSTMENT. ADJUSTED TORQUE SW FROM

^

OPEN 2iCLOSE 2 TO OPEN liCLOSE 1.

PERFORMED MTR OPERATED VLV ANALYSIS TEST USING MAINT. INSTRUCTION 10.43. WR B108275. REFER. WR B115186.

B108276 2 MV0P 074 0021 05/13/86 2-MV0P-074-0021-P,Ct10CFR50.498,8NPRD*], POSSIBLY VLV WAS OVERSEATING ON CLOSE VLV IS SEATING WITH EXCESSIVE THRUST \\ CYCLE DUE TO TORDUE SW SETTINGS PEING A

• ADJUST PER MI11.2B AND M0 VATS PER OUT OF ADJUSTMENT ; BALANCED AND RESET c! mil 0.I3

/ CLOSE TOROUE SW SETTING USING MAINT.

INSTRUCTION 11.2B. PERFORMED MTR OPER VLV ANALYSIS TEST. WR B108276 JB108278 2 MV0P 003 01798 03/17/86 2-MV0P-003-0179B-B,[*10CFR50.49*e*NPRD*] TOROUE SWITCH WAS BAD DUE TO CYCLIC -

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eVLV IS SEATING WITH EXCESSIVE THRUST FATIGUE. REPLACED TOROUE SWITCH USING ADJUST PER MI11.2A AND MOVATS PER MAINTENANCE INSTRUCTION 11.2A. RAN MOT 0R mil 0.43 OPERATED VLV ANALYSIS TEST.

B108281 2 MV0P 00 0153 05/16/86 2-MV0P-063-0153-B,[*10CFR50.49t,*NPRD*), LIMITOROUE SETTINGS WERE DUT OF VLV IS SEATING WITH EXCESSIVE THRUST ADJUSTMENT POSSIBLY DUE TO NORMAL WEAR.

ADJUST PER MI11.2A AND MOVATS PER ADJUSTED LIMITOROUE SETTING USING mil 0.43 MAINT. INSTRUCTION 11.2A AND RAW MTR OFERATED VLV ANALYSIS TEST USING MAINT.

_f INSTRUCTION 10.43. WR B108281 P110360 2 MV0P 070 0133 02/23/86 2-MV0P-070-0133-A,[*NPRD*3,TR000BLE TOP BRG CAP WAS CRACKED THE DRIVE SLEEVE 4

j SHOOT AND REPAIR VLV LIMIT SWITCHES EEVEL GEAR WAS PROKEN AND THE HANDWHEEL ATTN FRED MILLS AUX 714 WA12 WAS STRIPPED OUT POSSIPLY DUE TO NORMAL WEAR. REPLACED HANDWHEEL SEAL AND J

GASKETSIDRIVE SLEEVE BEVEL GEARi TOP PRG CAP AND TRIPPER SPRING. CLEANED AND 4-REPLACED GREASE IN OPER WR B110360.

18112359. 1,CHR' 313 0458 07/21/86 1-CHR-313-0458 1B-B 480 VOLT ELECT BD a

RM CHILLER AUX 763. UNIT WILL NOT RUN REPAIR AS NEEDED

'B114568 2 MV0P 001 0016 04/23/06 2-MV0P-001-0016-A,C*NPRD*,*10CFR50.49*3, DIRTY LIMIT SWITCH CONTACTS. CLEANED P0 CONTACT #11 ON ROTOR 3 IS OPEN WHEN CONTACTS AND ADJUSTED THE SPRING TENSION VLV IS FULLY CLOSED AUX U2 W.VLV RM AND CAP DN STATIONARY CONTACTS USING MAINTENANCE INSTRUCTION 11.2A STEP 13.22 B115337 2 BtRA 250 NH /24 05/31/86 2-PERA-250 NH /24-Fr[rNPRD*],FFEAKER FREAKER WAS PAD PROBAPLY DUE TO N9RNAL 824 FAILED SI258.2 TRIP TIME REPAIR OR WEAR OR AGE. REPLACED PREAKER 824 AND i

REPLACE PKR SFEC'S PERFORMED SI 258.2 B117812 2 GENB 082 0002B 06/02/86 2-GENB-082-0002B-P,[*NPRD*],2P-P D/G ENGINE IDLE SFEED WAS OUT OF ADJUSTMENT IDLE SPEED CONTROL - /.D.".'2T IDLE SPEED FOSSIBLY DUE TO NORMAL CYCLING. ADJUSTED TO 400 RFM.

IDLE SFEED ON ENGINES 2B-1 1 2B-2 TO 400 O

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08-04-86 PAGE 2 COT;P

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' B120033 2 BKRB 250 NF /13 05/28/86 2-BKRB-250-NF /13,C*NPRD*3 REPLACE BKR BREAKER WAS BAD PROABLY DUE TO NORMAL

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DUE TO DEFICIENCY OF SI 258.2 BKR WDULD WEAR OR AGE. REPLACED BREAKER 413 AND 5 i NOT TRIP ON DVERCURRENT. AB 734 PERFORNED SI 258.2 B121169 2 BKRB 250 NF 26 05/31/86 2-BKRB-250-NF 26,C*NPRD*],HEINEMANN BKR WAS BAD PROBABLY DUE TO NORMAL WEAR BREAKER TUPE CF2-Z51-1 2 POL 2 15 AMP OR AGE. REPLACED BKR 426 AND PERFORMED R

' CONTROL 734. BREAKER FAILED S1258.2 OVER SI 258.2 WR B121169 0

. CURRENT TRIP TEST 120 VAC VITAL INSTR W-POWER BOARD 2-II BREAKER 426

.B121170 2 BKRB 250 ND /23 05/31/86 2-BKRB-250-ND /23 C*NPRD*3rHEINEMANN BKR WAS BAD PROBABLY DUE TO NORMAL WEAR BREAKER TYPE CF2-251-1 CONTROL BLDG 734. OR AGE. REPLACED BKR 23 AND PERFORMED BREAKER FAILED SI258.2 DVER CURRENT TRIP SI 258.2 WR B121170

• TEST 120 VAC VITAL INST POWER BOARD 2-1 a.

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B124468 1 BCTA 068 0341A 06/13/86 1-BCTA-068-0341A-A C*NPRD*], SPRING SPRING CHARGING MTR WAS BURNED UP CHARGING MTR WOULD NOT CHARGE SPRING.

PREVENTING SPRING FROM CHARGING CAUSING

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MTR FND RUNNING CONINUOUSLY UNTIL IT GOT MTR TO RUN CONTINUOUSLY PROBABLY DUE T0 c 4',g y

EXCESSIVELY HOT. AUX 734 1AA 6.9 KV SD NORMAL WEAR. REPLACED MAIN TOGGLE a

m BOARDS LINKAGE PIN AND SPRING CHARGING MTR. WR B124468 B124477 2 GENB 082 00028 06/02/86 2-GENB-082-0002B-B,C*NPRD*3,2 B-B DIESEL THE CANNON PLUGS WERE DIRTY. INSPECTED GENERATOR D/G 722 DOES NOT GO TO 400 RPM GOVERNOR AND CLEANED THE CANNON PLUG S.

AFTER NORMAL STOP FROM C ROOM D/C WENT FUNCTIONALLY TESTED DIESEL GENERATOR TO 980 RPM FOR 10 MIN AND THEN ST0FFED MAKE NECESSARY REPAIRS AS REQUIRED TO

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CORRECT PROPLEM

B131345 2 BKRB 250 NF /25 05/31/86 2-BKRB-250-NF /25,C*NPRD*3sINSTR POWER BKR WAS BAD PROBABLY DUE TO NORMAL WEAR BOARD 2 II BKR 25 CONTROL 734. REPLACE OR AGE. REPLACED BKR 25 AND PERFORMED SI DEFECTIVE DN 012 258.2 WR B131345.

'16 records listed.

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SUMMARY

08-04-86 PAGE 1 l

COMP IR. HIST U FUNC SYS ADDRESS. DATE.... DESCRIPTION............................. CCREECTIVE ACTI0N....................

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8100158' 2 BKRB 068 0341F/4 06/26/86 2-BKRB-068-0341 0 4,TFE AMP FREAKER f4 CIRCUIT PREAKER WAS BAD PROBAPLY DUE TO El y

WILL NOT STAY CLOSED IN. PLEASE REPAIR NORMAL WEAR. PEPJORMED SI258.2 AND

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SI. REPLACED 100 AMP PREAKER WR B100152

.-B115549 1 GENB 082 0001A 05/27/861-GENB-032-0001A-Ar[tNFRDt],D/G B'_DG GOV. IDLE SPEED DID NOT MEET I

722. ADJUST TI'E IDLE SPEED TO 400 RPM SURVEILLANCE TEST SPECIFICATIONS.

ADJUSTED GOV IDLE SPEED TO 400 RPM ON

. ENGINES 112 UR B115549

'B127261 0 CHGB 250 GK 06/30/86 0-CHGB-250-0K-S, SPARE 480V VITAL PATTERY ELECTRO CAPS UERE PAD. VARIABLE FESISTOR CHARGER 2S AUX 749. EQUALIZE CONTROL ON WAS OUT OF ADJUSTMENT. REPLACED ELECTRO CHARGER 2S WILL NOT VARY VOLTAGE ON CAPS IN CHARGER 25. ADJUSTED VARIAELE SI303 CHARGER WILL NOT LOAD TO 150 AMPS RESISTOR ON AMP BOARD WR P127261 r

3 reco'rds listed.

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MAINTENANCE

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INSTRUMENT MAINTENANCE MONTHLY REPORT FOR JULY 1986

A Documentation was received during the month on five Beckman controllers that were purchased as spares or replacements without the proper Certificate of Compliance (C0C) stating that they were the same as the originally purchased controllers.

Testing of the manual safety injection handswitch was completed during the month.

This closed out CATS item 86-018. The tests were performed to verify that the reactor trip signals were initiated by the handswitches, HS-63-133A and 133B.

Six PR0s were submitted against systems 68 (Reactor Coolant System - RCS) and 87 (Upper Head Injection - UHI) compliance instruments due to out-of-i tolerance values.

Received Westinghouse re-analysis of the UHI isolation valve closure tolerance time. This analysis increased the tolerance on the isolation valve closure from 0.05 seconds to 0.14 seconds.

FSAR review of preventative maintenance recommendations was continued and was 95% complete at end of month.

Continued work on the revised setpoint methodology report. Coordinated with Westinghouse to resolve comments and finalize the analysis.

During a technical review of ESF response time test IMI-99, RT-699B, it was discovered that previous testing had not considered the 1 second time delay associated with the 6900V shutdown board undervoltage relays.

PRO-1-86-161 was initiated and evaluation of reportability is currently unde rway.

Began review and evaluation of Nuclear Plant Reliability Data System (NPRDS) equipment failure reports. Evaluations are expected to help identify corrective actions needed to increase the reliability and cperability of plant instrumentation.

Reopened six closed EQ hinders (IFT-00-1, I LCV-00-1, IPT-00-1, IXT-00-1, XMTR-00-1, and XMTR-00-4) to include new requirements that were added due to recent revisions to the Qualified Maintenance Data Sheets (QMDSs).

Vendor manual review of 10CFR50.49 devices with any EQ requirements that have not been addressed was continued this month and was approximately 80% complete at the end of the month.

INSTRUMENT MAINTENANCE MONTHLY REPORT FOR JULY 1986 24 UNIT 1 Surveillance Instruction (SI)-83; (Channel Calibration for Radiation Monitoring System), was reviewed against the SNP's review check sheet, difficiencies corrected and revision to SI-83 submitted.

UNIT 2 Received new Eberline post-accident radiation (RAD) monitor printer assembly model CT2B and printer was installed on 2-M-31.

During performance of SI-484, (Periodic Calibration of Reactor Vessel Instru-mentation and RCS Wide Range Pressure Channels), it was discovered that the train B RVLIS upper plenum sense line lost its fill.

Work request B102618 submitted to refill sense line.

COMMON PRO 1-86-177 was initiated for failure to perform the functional test require-ment for testing automatic isolation of release pathway froa steam generator blowdown (1,2-R-90-120 & 121) and condensate demineralizer (0-R-90-225) liquid effluent rad monitors due to instrument downscale failure. The logic of these monitors was never designed to perform this function. A technical specification change has been submitted to delete the automatic isolation function on radiation monitor downscale failure for these radiation monitors.

Revisions for SI-480 (Eberline Accident Monitoring System), 480.1 and 480.2 were submitted for calibration requirements on the radiation monitoring system. These revisions incorporated new changes for the control room printer assembly and were checked against SQN's SI review checksheet.

Category (CAT) "D" field change request (FCR) 4477 submitted, engineering change notice (ECN) 6701 issued, and WP 12114 written to install seismic latches on main control room Foxboro recorders.

Work plan 12072 (FCR 3110R1 for ECN L5199, U-1 ECN 2779, U-2) was completed. This WP re-labeled reactor coolant drain tank rod monitors (R-90-275 & 276) to reactor building and equipment sump rod monitors (R-90-275 & 276). Reactor building and equipment sump rad monitors (R-90-277 & 278) re-labeled to reactor coolant drain tank rad monitors (R-90-275 & 276). This WP also cleared Temporary Alteration Change Forms (TACFs) 2-84-122-90 (U-2) and 1-84-123-90 (U-1).

Instrument Maintenance (IMI)-99-RT-4.5, -RT-4.6, -RT-4.7 and -RT-4.8 (Response time test of pressurizer pressure channels I, II, III & IV) were revised to make procedure comply with current plant guidelines and to add steps to response time test the auto shut trip feature of the reactor trip switch gear, as required by CATS85-040 and NRC generic letter 83-28.

As a result of these revisions, CATS item 85-040 was closed.

IMI-156.17, (Procedure for Replacement of LT-3-43, 539) was revised and approved for the replacement of LT-3-93 (LT-539) under 10CFR50.49.

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'PAGEo2 ER. COMP U FUNC SYS ADDRESS. DATE.... DESCRIPTION............................ - CORRECTIVE ACTION.................

CALIBRATED WITH A RID INDICATOR IE83817

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LAB B125639 2 RR 090 253 07/14/86 2-ER-090-253,RECDRDER STRING APPEARS TD DRIUE CARD BROKEN. REPLACE PRINT HEAD BE BRDKEN DRIUE CORD B125903 1 XM 092 5001 07/11/86 1-XM-092-5001,THE CHANNEL 1 SOURCE DIRTY CONNECTORS UN CABLES. CLEANED RANCE IS ERRATIC CDHNECTORS B125904 1 EM 090 1000 07/14/86 1-EM-090-100B, TEST POINT 83 IS BRCKEN. ABNDRMAL STRESS. REPLACED TEST POINT PLEASE INVEST AND REPAIR STICKER

~B125912 1 LT 003 106 07/07/86 1-LT-003-106,EuMPRDu,N10CFR50.49m],ulu SENSING LINES NEEDED BACKf!LLING '.

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REPORTABLE B125916 2 TR 068 2A 07/21/86 2-TR-068-2A,CmMPRDmLUNEN' THE CECEN PEN THE PRINT NEAD ARM MAS BENT AND' CAUSED REACHES UPPER SCALE (50 MA) IT APPEARS THE HEAD TO BIND UP. THE ARM WAS i

THAT THE CONNECTING ARM IS HITTING A STRAIGHTENED AND THE RECORDER WAS SCREW HEAD RETURNED TO SERUICE B126459 0 CLAN 043 205A 07/18/86 0-CLAN-043-2054, PLASTIC CDUER CRACKED ;0BNDRMAL STRESS. REPLACED PARTS PILDT LAMP SOCKET LOOSE WORK DURING WEEKLY SCHED SI-240 THRU' ij8126403 2 LR 003 98 07/21/86 2-LR-003-98 min RECORDER IS INDICATINC 'DUT OF CALIBRATION. RECALIBRATED l

APPRDX 80% WHER IN ACTUALITY SHDULD BE READING SOMEWHERE ARDUND 15Z TO 202 i B127074 1 LT 003 39 07/29/86 1-LT-003-39-f,[uMPRDu,n10CFR50.49uL PAND INSTALLATION ERRDR. ROTATED PANEL 180 EL MOUNTED UP SIDE DOWN ROTATE PANEL 180 DEGREE REINSTALLED RETURNED TO SERVICE DEGREE AND REMOUNT TRANSMITTER NOT NPRDS REPORTABLE B127703 1 RM 090 106 07/31/86 1-RM-090-106, PULL RELAYS THAT GIVE ISOL NONE. HONE SIGNAL FRDM 1-RM-90-106 ALB REPLACE WHEN

, m.

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-B127711 1 FS 001 100 07/23/86 1-fS-001-10B-E,EmHPRDd], LEGITIMATE UNKNOWN, BACKFILLED LEGS NOT NPRDS READING AT LEVEL TRANSMITTER APPRDX 13 REPORTABLE MILS BACWFILL DR CALIBRATE AS REQUIRED

, B129167 1 LS 087 24 07/28/86 1-LS-087-24, MEASURE AND RECORD THE HIGH NONE. NONE NOT NPRDS REPORTABLE

'?1 AND LOW LEGS Of THE UHI SW FRDM THE

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CALCULATE SETPOINTS PRIOR TO CDMPLETION OF WORK i

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INSTRUMENT NAINTENANCE MONTHLY

SUMMARY

08-04-86.

7-PACE 4;

~~

• W. "

-s COMP l

MR. COMP U FUNC SYS ADDRESS. D ATE.... DESCRIPTION............................ CORRECTIUE ACT!0N.......................

SMI-0-317-26 REPORTABLE B132376 1 PT 063 126 07/02/86 1-FT-063-126,UERIFY MOUNTING PER' UNKNOWN. UERIFIED MOUNTING J

SMI-0-317-26

! B132377 i PT 063 128 07/02/86 1-PT-063-128,UERIFY MOUNTING PER UNWHOUN. UERIFIED MOUNTING. NOT 'NPRDS SMI-0-317-26 REPORTABLE i B132388 i PT 068 68 07/02/86 1-FT-048-68,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING NOT NPRDS i

SMI-0-317-26 REPORTABLE i B132392 1 PT 068 301 07/02/86 1-PT-068-301,UERIFY MOUNTINC PER UNXNOWN. UERIFIED MOUNTING. NOT NPRDS SMI-0-317-26 REPORTABLE B132393 1 PT 068 311C 07/02/86 1-PT-068-311C, VERIFY MOUNTING PER

' UNKNOWN. UERIFIED MOUNTING. NOT NPRDS

?

SMI-0-317-26 REPORTABLE B132394 i PT 068 336C 07/02/86 1-PT-068-336C,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT NPRDS SNI-0-317-26 NEPORTABLE i

B132395 1 LT 068 325C 07/02/86 1-LT-068-325C,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTINGS.'NOT MPRDS

~

SMI-0-317-26 REPORTABLE

• 'B132396 1 LT 068 3260 07/02/86 1-LT-068-326C,UERIFYING MOUNTING PER UNWHOWN. UERIFIED MOUNTING. NOT HPRDS REPORTABLE SMI-0-317-26 j

B132397.1 PT 068 337C 07/02/86 1-PT-068-337C,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTINC. NOT NPRDS SMI-0-317-26 REPORTABLE i B132398. 1 PT 068 07/02/86 1-PT-068-,UERIFY MOUNTING PER UNNNOWN. UERIFIED MOUNTING. HDT HPRDS SMI-0-317-26 REPORTABLE B132676 '1 LT 077 411 07/28/86 1-LT-077-411, REMOVE FLANCE CONTAINING ' HONE.MONE i

LT-77-411 OH U1 FLOUR AND EQUIPT. DRAIN 1

SUMP B132810 2 FR 003 90 07/21/86 2-FR-003-90,ENNPRDw3,FOUND FT 00T OF UNKNOWN. NO PROBLEM FOUND NOT NPRDS i

TOLERANCE SUSPECT A PROBLEM IN LDDP REPORTABLE 2-F-3-904 OR 2-F-3-900 i; B132812-2 LIC 003 140 07/15/86 2-LIC-003-148, CONTROLLER WILL NOT &

RIBBON CABLE LOOSE. RECONNECTED RIBBON TRANSFER FROM AUTO TO MANUAL. ALSD CABLE GUTFIT WILL NOT CHANCE IN AUTO MODE.

l

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2 INSTRUMENT MAINTENANCE MONTHLY

SUMMARY

08-04-86 i

FACE 2 COMP NR. HIST U FUNC SYS ADDEESS. D ATE.... DE!CRIPTIDN............................ CORRECTIVE ACTION......................

B130389' 2 HIC 063 396 07/01/86 2-HIC-068-396-B, LOST +15 PWR TO DEFECTIVE URI REGULATOR. INSTALLED NEW CONTROLLER FHD ON SI 199-REGULATOR B132352 1 PT 001 9A 07/02/86 1-PT-001-9A-0,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT HPRDS SMI-0-317-26 REPORTABLE B132353 1 PT 001 90 07/02/86 1-PT-001-9B-E,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT HPRDS SMI-0-317-26 REPORTABLE B132355 1 PT 001 204 07/02/86 1-PT-001-20A-D,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT NPRD SMI-0-317-26 REPORTABLE 18132356 '1 PT 001 200 07/02/86 1-PT-001-20B-E,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT HPRDS SMI-0-317-26 REPORTABLE B132359 1 PT 001 5 72 07/02/36 1-PT-001-72-E.UERIFY MOUNTING PER 1 UNKNOWN. UERIFIED MOUNTING. NOT RPRDS SMI-0-317-26 REPORTABLE B132360 1 PT 001 73 07/02/861-PT-001-73-D,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT l'8EDS SMI-0-317-26 REPORTABLE B132379

'l FT 068 60 07/01/86 1-FT-068-6B-E.UCERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT HPRD:

SMI-0-317-26 REPORTABLE B132382 1 FT 068 29B 07/01/86 1-FT-068-29B-E,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT NPRDS SMI-0-317-26 REPORTABLE B1323851 1 FT 068 48B 07/01/86 1-FT-068-48B-E,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT NPRDS

?

SMI-0-317-26 REPORTABLE B132390 1 FT 068 71C 07/01/86 1-FT-068-71B-E,UERIFY MOUNTING PER UNKNOWN. UERIFIED MOUNTING. NOT NPRD 3MI-0-317-26 REPDRTA9tE 26 records listed.

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.5 MAINTENANCE

SUMMARY

(MECHANICAL)

MECHANICAL MAINTENANCE MONTHLY REPORT FOR JULY 1986 COMMON

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1.

Essential raw cooling pump 'RA' was reassembled to allow ' A' train diesel generator to be run.

2.

A field change request (FCR) was initiated to upgrade bolting material on post-seal butterfly valves to a material less succeptible to stress-corrosion-cracking.

3.

An evaluation of the degradation of red rubber gaskets inside containment was completed.

4.

The inspection / teardown of the 'A' auxiliary building chiller has begun with assistance from a factory representative from York.

5.

The installation of a new wet washer has begun.

6.

The 'A' gas stripper feed pump was rebuilt.

7.

A special maintenance ice condenser task force attended a meeting in Columbus, Ohio along with a representative from WBNP.

8.

An INPO sponsored workshop in Chattanooga on human factors in maintenance procedures was attended by a management group.

9.

An engineering task force participated in a Reactor Coolant Pump (RCP)

Cartridge Seal class at the Power Operating Training Center.

10.

Charcoal trays from Post Accident Sampling Facility (PASF) were installed in Control Building

'A' train emergency air clean-up system.

11.

The C-zone on elevation 734 was cleaned.

12.

A spare low pressure spindle was shipped to Westinghouse by rail for disc modification.

13.

The existing fire door, A-9, was replaced with new one.

14.

The training of welders / foremen / engineers on welding requirements was completed.

t.

4

.s-MECHANICAL MAINTENANCE MONTHLY REPORT FOR JULY 1986 UNIT 1 1.

Pre-drilling has begun on the RCP motor stands for the articulated arm 1

modification.

2.

A disc block on 1-BLB-70-692 was repaired.

3.

Installation has begun on the main turbine vibration brackets.

4.

Boric acid piping work was completed due to stress-corrosion-cracking.

5.

The waterboxes have been opened for visual inspection.

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MECHANICAL MAINTENANCE MONTHLY REPORT FOR JULY 1986 UNIT 2 1.

The pre-drilling of the RCP motor stands for the articulated arms was completed.

2.

The inspection and repair of the long cycle valves (2-FCV-3-191,192, 193, 194 and 2-VLV-3-458) was completed.

3.

The repairs / retests of containment isolation valves continue.

4.

The clean-up of lower containment has begun.

S.

The #2, #3, and #1 steam generators were opened for eddy current testing /

tube plugging.

6.

The steam dump header hangers to DNE supplied values were reset.

7.

The disassembly of the #4 reactor coolant pump to replace the #1 seal housing 0-ring has begun.

8.

On upper and lower compartment coolers, the tubes were cleaned.

9.

The installation of the spare PORV (2-PCV-68-340A) was completed.

10.

Miscellaneous work was performed during glycol outage.

11.

The repairs on LLRT valve 2-FCV-70-87 was finished.

12.

The repairs to 2-FCV-26-240 were completed.

13.

A new cavitating venturi on the discharger of 2AA auxiliary feedwater pump was installed.

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O id MAINTENANCE SUNIARY (MODIFICATIONS) 1 i

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SUMMARY

OF WORK COMPLETED MODIFICATIONS

.A JULY 1986 NUREG 0588 ECN 6231 - Remove Interferences The remaining work will be performed under ECN 6681.

ECN 6552 - 0588 Solenoids Fieldwork was completed.

ECN 6616 - Damper Fusible Link All fieldwork was completed.

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

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

OTHER ITEMS ECN 2783 - Installation of Fifth Diesel Six electrical-related workplans for the fifth diesel installation have been placed in the workplan closing cycle.

ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of isolation valves remains in the approval cycle. Some insulation activities remain incomplete.

DNE is revising the USQD.

ECNs 5034 and 5743 - Various Platforms in Lower Containment Because of new weld inspection requirements. Modifications Group B is waiting on DNE to furnish inspection requirements on tack welds to hold down grating.

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

Caps have been installed on the valve nipples.

ECN 5703 - Reinforcement of Block Walls Restraints have been installed; unit 2 is complete.

ECN 5713 - Various Platforms in Lower Containment The first trolley was modified by the vendor.

Power Stores has been unable to receive it because of paperwork problems. The remaining trollies are being prepared for shipment to the vendor for modification. Work will continue when the trollies are returned.

ECN 5724 - CVCS/RHR Supports One hanger and one notification of indication remain incomplete--waiting on DNE.

ECN 5880 - UNID Tags for Class 1E Fuses DNE is to furnish an approved fuse listing by August 15.

Meanwhile, the preparation of workplans is in progress.

ECNs 5938, 6305, and 3571 - Replace Feedwater Heater and Eroded Pipe Modifications Group B is supporting postmodification testing (PMT) on heaters 1 and 2 on both units as requested.

Insulation work on unit 1 continues.

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

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

ECN 6064 - Various Platforms in Lower Containment This work is complete.

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

ECN 6185 - Offsite Paging System i

Functional tests of the remote mobile units remain to be completed, i

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

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

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

1 i

31_

O ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement Insulation activities are continuing on unit 1.

All bundles have been removed on unit 2.

Modifying unit 2 internals has been completed on two bundles with new bundles inserted. Work continues on others.

ECN 6380 - Replacement of Barton Pressure Transmitters The transmitters were returned to the vendor for retesting (expected to be returned on August 4, 1986). The workplan has been approved, and work will continue when the transmitters are returned.

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

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

ECN 6417 - Install Alternate Seal Water for Pumps, CDWE Modifications Group B is waiting for design to be completed and materials to be received.

ECN 6459 - Declassify Certain IE Equipment The workplan is in writing.

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

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

FCR approval is pending for Workplan 12104 to go to approval cycle.

ECN 6513 - Support of HVAC Expansion Tank All fieldwork is complete.

ECN 6556 - Replace Solenoid Hangers Work is in progress.

ECN 6573 - Shutdown Board Alternate Foeder The workplan is complete.

ECN 6599 - Unit 2 Shield Building Anchor Problem An SMI procedure is being prepared to test the holding capacity of the small anchor bolts that were added to the original scope.

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

4 ECN 6606 - Additional Penetration Fuses The workplan has been completed.

ECN 6610 - Modify Air Return Fan Supports Work was completed on unit 2.

ECNs 6631 and 6683 - Snubber Replacements / Modifications Workplans are in the approval cycle for ECN 6683. The workplan was approved, and work was started on ECN 6631.

ECN 6636 - Replace Cable in Valve Room The workplan is in writing.

ECN 6637 - Control Air Drawing Discrepancies The workplan is in the approval cycle. Another ECN is being released.

ECN 6648 - Time-Delay CCS Pump The workplan is in the approval cycle.

ECN 6661 - Upgrade ERCW Piping The workplan is being rewritten to include the replacement of piping that could not be upgraded.

ECN 6667 - Delete Torque Switch MOVs The workplan is still in the approval cycle.

It is being held pending the resolution of PORC comments.

ECN 6672 - Modify Hangers in High-Pressure Fire Protection in Unit 2 Elevation 690 Pipe Chase The workplan has been approved, and work has been started.

ECN 6681 - Supports for ERCW to Upper Compartment Coolers (Annulus)

Soven support modifications are to be done. The workplan is in the approval cycle.

ECN 6693 - Primary H 0/ Control Air Interaction 2

The workplan is in the approval cycle.

ECN 6698 - Repull 120-Volt Cables The workplan is in writing. -

ECN 6700 - Concrete Edge Distance Hangers The workplan is being prepared.

ECN 6701 - Modify Foxboro Recorder Latches The workplans have been written and are in the approval cycle.

ECN 6999 - Remove Caps and Valve Stems Work is in progress.

Dry Active Weste Building (DCR 1898)

Work continues on the insulation and metal siding for the outside walls. The purchase of material for ladders and access platforms is in progress in order to sandblast and apply carbozine before fabrication.

Additional Office Building Building A is complete, including restrooms and lunchroom. Moving of employees is in progress.

The cubicle installation for building B is complete except for the 80-inch cubicles, which are due onsite August 1.

Electrical wiring and communications to the cubicles are in progress.

Miscellaneous outside work, including fire-protection piping, is in progress. Hydro testing of the installed fire-protection piping is to be performed on August 4.

The installation of dry wall in the Medical facility is in progress. Limited modifications requested by Medical Services are being performed.

Additional Office Building at Power Operations Training Center t

l The east wing and restroom facilities are complete. Personnel l

occupancy is complete.

The west wing interior painting is complete. Negotiations are being j

conducted with the vendor to start carpet installation as soon as possible. The connection of the heating, ventilating, and air-conditioning unit is in progress and is expected to be complete August 4.

Electrical wiring and junction boxes are being purchased I

for the installation of power poles and electrical extension. This is a new requirement based on the decision for DNE personnel to also i

occupy the wesc wing.

f PavingActivitkes l

Paving three additional lanes in parking lot No. 2 is complete.

Curb installation is scheduled to begin August 1, followed by lane striping.

4 Paving the Power Operations Training Center parking lot was completed on July 31.

After cure time, the curb installation and lane striping will be performed. This is scheduled to start August 4.

Welding Project Support was provided to Welding Project personnel as requested.

Walkdown Fleid Verification Support SMI-0-317 79-14 Enhancement--The number of hangers requiring inspection now totals 318 for unit 2.

Preliminary inspections are complete on 298 supports on unit 2 and 1,648 supports on unit 1.

Twenty-five unit 2 supports require fieldwork, while 51 unit 1 supports have fieldwork required to date. Discrepancies totaling 105 on unit 2 are being evaluated. Work is continuing.

SMI-0-317 Concrete Edge Distanco--Complete; DNE continues to evaluate the results (reference ECN 6700).

Alternate Analysis Walkdown Work is continuing.

SCR Resolution Many man-hours were spent resolving SCRs.

Repair of Railroad Crossings The repair of railroad crossings at eight locations along the Sequoyah Access Road was completed by the contractor on August 4.

0 MODIFICATIONS ECN DCR SYS DESCRIPTION UNIT ~

24 19255 077 Install a clean-out tee with a 2

draw viv.

In the piping as shown in DWG 47W852-4R13, prior to the piping entering the collection header. TACF 1-86-001-77.

L5397 D0741 070 Modify the inst. loop ground 1

from net side of transmitting to neg. side of power supply i

for affected instrument rack in control room and the backup ctrl rm TACF mod. U2 ECN2879 DCR-10.

l L5577 D0947 030 Change suction dampers for the 1

CRDM cooling units. REF ECN 3006 Ref ECN 5246.

TACF 80-670-30 dampers 1-TC-30-81, -84, -89,

-93.

L5729 D1312 043 Correct DWGs 47W625-11 and 2

47W470-2 for location of pene-tration X-92 to agree with 48N06. 2-HZ AN-43-210 sample line penetration at AZ 346 and EL700 11".

Documentation chg only.

L5984 D2075 013 Replace 25 watt lamps on each 1

unit with 10 watt tungstenthalogen cycle quartz lamps, GE NAH-7552 Thus upgrading tl.c nameplate rating from 3 hrs. continuous oper. to 8 hrs. Replace existing batteries.

L6287 D2075 013 WRC commitment (appendix) to add 0

additional emergency light packs in areas that must be manned for safe shutdown and for access and egress routes to and from all fire areas.

(NCR SQN MEB 8304)

L6313 D2133 363 Replace circuit breakers, re-1 assign circuit breaker loads.

Document circuit breaker trip settings, and replace / document motor starter overload heaters l

to correct 10CFR50 deficiencies.

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j MODIFICATIONS ECN DCR SYS DESCRIPTION UNIT 2

L6315 D2133 363 Replace fuses, and reassign fuse 1

load circuit to correct 10CFR50, Appendix R associated circuit (type I, II) deficiencies.

L6344

-D2133 363 Provide 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated door 1

for opening thru "S" line wall leading into spare room no.

669.0-A31 at el 669.0.

L6379 D2133 000 Revise instrument tabulations 1

to identify all Appendix R required equipment by an "R" designated systems 001, 003, 30, 31,32,33,62,63,67,68,70,72,74, 77,87.

L6412 F3441 026 To correct discrepancies in the 1

DWGs (correct symbols, part num, flow lines) viv desc.

L6438 D2133 000 Add fuses to 6.9 and 480V shut -

1 down boards for breaker status lights in the auxiliary control room to correct type II spurious associated circuit deficiencies.

L6503 F3796 063 1-VLV-63-697, replace Rockwell 1

Edward 1" TS8 viv with Rockwell Edward 3/4" TS8 viv. 1"viv is not available.

L6505 F3557 410 Add note to TVA DWGs 46W454-1 0 as follows: Door closers Russwin 2820 series may be used inter-changeable with Russwin 2810 series closers.

L6513 F3819 031 Modify supports for expansion 0

tank, system 31 unit 0 at el.

733-3 8-8"S.

. = _ -. -..

MODIFICATIONS ECN DCR SYS DESCRIPTION UNIT 7

i L6544 F3874

317 Chg DWGs to delete jumpered out' 1

limit switches, add design infor-mation, correct DWG. Discrepan-cies and reduce field wiring for valves. Being qualified under j

10CFR50.49.

i

]l _

L6552 D0972 000 Replace solenoid vivs listed in 1

(SQN EQP. 8526R) and R1 with v1vs.

)

Qualified for inside containment i

environment.

Systems 43, 62, 63, 87.

NCR SQNEQP 8526 RO & RI.

l L6618 D0972 317 (No predecessor ECN,S) replace 1

j cable IV7973B, the portion inside viv vault, with mark NC.WHC cable, purchased on contract 824443-2 REF:SQNEQP 8609RO.

J L6627 D0972 317 Corrective action required to 1

i environmentally qualify cable PP711B per 10CFR50.49 (No prede-j cessor ECNs) REF: SQNEQP 8603RI.

4 L6628 F4210 030 Install an access door / plate in 1

the duct above each containment 1

air return fan and motor unit on i

unit 1.

For maintenance purposes, this would allow the fan and motor to be accessible.

i L6638 F4208 074 Show location of drain v1vs 74-2 3

549 and 74-552 inside missile barrier on flow diagram 47W810-1.

Doc chg only.

1 NOT REQ D0926 099 Modify circuit to insure maximum 1

l voltage to transmitter is limited r

to 52 IV DC at all times U2

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completed under WP10532.

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ENVIRONMENTAL QUALIFICATION (E.Q.) SUM %'lY

~. _.

O Date: 8/5/86 0041E o

Estimated Date of Ca eletion SCR No.

Description ECN Engineer biorkplan No.

11-1 U-2 Ccaments EQP 8501 Disconnect 1-and 2-HS-6?-61 6524 Peters 11901 C

C U-2 QIR submitted.

EQP 8502 Replace penetrations 23 and 48 6490 Peters 11801, 11802, C C

Complete QIR submitted.

11810, 11811 i

]

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

EQP 8504 Splice methods not correct N/A Stockton 83 MRs C

C Complete QIR submitted.

EQP 8505 Drawing N/A N/A N/A N/A N/A 4

i i

EQP 85CS Seal containment isolation 6514 Kimsey 11880 C

C valve b

f EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C

f EQP 8508 JB weepholes (press) 6523 Alas 11898 C

C Conplete QIR submitted.

{

EQP 8508R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C

I EQP 8509R2 Conduit seals 6615 N/A N/A N/A No field work renaining.

i EQP 8510 Disconnect local handswitches 6527 Peters 11901 C

C EQP 8511 Submerged JB inside 6549 Peters 11901 C

N/A containment i

i i

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a i

Date: 8/5/86 0041E Estimated Date of Caeletion SCR No.

Description ECN Engineer niorkplan No. 11-1 U-2 Comments EQP 8512R2 Rewire JB N/A Mburn 11855, 11856 C C

All boxes rewired.

EQP 8513 niecp holes (soisture) 6547 Alas 11898 C

C Cusplete QIR submitted.

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

C Couplete QIR submitted.

EQP 8514 Motor insulation 74-1, -2 6540 Pranhan 11906 N/A C'

Couplete QIR submitted.

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

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

Maint.

EQP 8517 ABGTS hunidity control 6578 Gonzalez N/A C

L

?

EQP 8518 Submerged cables 6533 Various/6 Various C

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

C Complete QIR submitted.

Maint.

EQP 8520 Expired cables 6553 Gonzalez 11902 C

C EQP 8521 Delete 18 and rework splices 6550 Stockton 11914, 11915 C C

EQP 8521R1 Delete TB and rework splices 6551 EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C

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

C Maint.

A h

Date: 8/5/86 0041E i

Estimated Date of Completion SCR No.

Description ECN Engineer Workplan No. U-1 U-2 cm ts EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C

4 eM misplaced brackets EQP 8524 Change setpoints 6551 Instrument 11916 C

C Maint.

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Reter1ninate hydrogen N/A Electrical N/A C

C Completed by Electrical Maint.

j EQP 8525 j

recorrbiner (MR)

Maint.

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

C Mods.

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

(MR)

,e Y

EQP 8528 Solder strain gauge Barton IMI Instrtsnent N/A C

C QIR submitted 1/24.

transmitters Maint.

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

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

C (M)

Maint.

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

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

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

o f

Date: 8 / 5,116 0041E Estimated Date of Completion SCR No.

Description eof Engineer Workplan No. U-1 U-2 Comuments EQP 8534 Resplice valve positioner

N/A Maxwell MR C

C Complete QIR sutunitted.

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

C U-1 10, u-2 12 11928, U-1 EQP 8536 Valve rocan submergence 6561 Mechanical 11939 C

C Cap drains 6632 Mods.

C C

EQP 8536R1 Valve room submergence 6612 Electrical C

C Mods.

EQP 8537 Rebuild or replace JB 3018 6579 Asburn N/A C

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

y FCD-31-475, -476 EQP 8539 Replace capacitors N/A Instrtsment C

C Maint.

EQP 8540 Replace pigtails to Target 6649 Peters 8/15 8/15 Rock solenoid valves EQP 8541 Delete brakes 6582 Branham 11980 C

N/A EQP 8542 Replace unqualified cables 6600 Hall 9/30 N/A Two cables will be replaced in accordance with a new issue.

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

2 Je

Dat2: 8/5/86 0041E Estimated Date of Completion SCR No.

Description ECN Enoineer Workplan No.

11-1 U-2 Consnents EQP 8601 Replace 1, 2-PT-1-2A, -27A; 6588 Elkins 12014 C

C upgrade 2-PT-1-2B, -278 EQP 8602 Reroute control cables for "au "aa"aaaaaaaaaa'aaaaaaaaaaaaaaaaaaaaaaa No longer an issue.

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

EQP 8604 Cable IPt3241A not qualified Aaa " " aa aaaaaaa " " aaaaaa**a " a " aaaaaaaaAAA No longer an issue.

EQP 8605 1

2-TS-74-43, -44, -45, 6589 Branham C

C

-46 not qualified EQP 8606 Undervoltage concern on 6611 Rutledge 9/5 9/1 Holding for drawings.

1 feecheater isolation valve 6676 y

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

C

-27A Maint.

EQP 8608 Enable / disable MOV brakes 6621 Rutledge 8/30 8/30 On ECN 6686, 8 of 20 items are 6622 conplete. Holding for material.

6665 6686 EQP 8609 Replace cable IV7973B 6618 C

N/A EQP is revising ECN for technical correctness.

EQP 8611 JB has weephole in top N/A Ant > urn N/A C

t

/

Date: 8/5/86 0041E Estimated Date of coupletion SCR No.

Description ECN Engineer Workplan No. U-1 U-2 Comments EQP 8612 Replace zone switches 6669 N/A C

EQP 8614 Weep holes in JB 6652 C

C EQP 8615 Replace FT-72-13 -34 EQP 8617 Junction box internal wiring EQP 8618 Relocate arc suppression network EQP 8619 Valve room submerged cables EQP 8620 Relocate steam generator g

level transmitters s~

B EQP 8621 Resolve conduits and fittings that may be submerged in Auxiliary Building EQP 8622 Replace terminal blocks with spliced cables EQP 8623 Replace limit switch on FCV-3, -21 EQP 8624 Junction box 2145 may be a a a e a a e a a e a e a a e a******* *********************** No longer an issue, submerged, unit I s

Date: 8/5/86 0041E y

Estimated Date of Caeletion SCR No.

Description ECN Engineer Workplan No. U-1 U-2 cmts N/A Move surge suppression 5773 Kinsey 11833 C

C U-2 couplete. On U-1, 1-PCV-68-340 network for PORV in hold. Holding for maintenance to ca plete.

EEB 8523 Penetration overcurrent 6606 Legg C

C N/A Work FCR to delete 1,

5083 Hall C

C Need SI-166, 2-PS-3-1604, -1608, -165A, and -1658 N/A Replace 1-FT-1-3A, -38, -104, 6347 Instrument N/A C

N/A Transmitters changed need response

-108, -21A, -21B, -28A, -28B

Maint, test.

NEB 8510 Relocate LT-68-320, 6439 Carrasquillo Various C

C 1

PT-68-323, -320 Peters Y

Renount 63-71,68-308 64 %

Legg 11865 C

C Replace LS-65-4, -5 6504 Legg 11865 N/A C

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

Delete brakes FCV-62-61 6521 Branham 11905 C

C EEB 8517 Replace pressure transmitter 6488 Branham 11931 C

C PDT-65-80, -82

-90, and -97 Y

e' lb THIS PAGE INTENTIONALLY LEFT BLANK i

i l

g TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 August 14, 1986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

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

Very truly yours, TENNESSEE VALLEY AUTHORITY

'711. J'le$At' I. R. Wallace P

Plant Manager Enclosure cc (Enclosure):

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

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

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

Mr. K. M. Jenison, Resident NRC Inspector 9 pf O&PS-2, Sequoyah Nuclear Plant t

7 l

( \\

An Equal Opportunity Employer

_ _, _. -