ML20135B124

Monthly Operating Repts for June 1985

ML20135B124
Person / Time
Site:	Browns Ferry
Issue date:	06/30/1985
From:	Jones G, Motter R TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20135B118	List: ML20135B115 ML20135B124 ML20135B130 ML20135B140 ML20135B150 ML20135B154 ML20135B169 ML20135B233 ML20135B237 ML20135B240
References
NUDOCS 8509100433
Download: ML20135B124 (29)

Text

f 7

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR. POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATINO REPORT TO NRC June 1, 1985 - June 30, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submittedby:b

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1 TABLE OF CONTENTS Operations Summary............. '............

1 Refueling Information.. '...................

3 Significant Operational 71structions..............

5 Average Daily Unit Power Level.................-

8 Operating Data Reports.....................

11 Unit Shutdowns and Power Reductions..............

14 Plant Maintenance.......................

17 Outage Maintenance & Major Modification............

24 Addenda............................

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Operations Summary June 1985 The following summary describes the significant operation activities during the reporting period.

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

There were five reportable occurrences and no revisions to previous occurrences reported to the NRC during the month of June.

Unit 1 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 refueling outage.

Unit 2 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

Unit 3 The unit was in cold shutdown the entire month on an administrative hold to resolve various TVA and NRC concerns.

Prepared principally by B. L. Porter.

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2 Operations Summary (Continued)

June 1985 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.23910 0.17629 0.14326 NOTE:

This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.

Common System Approximately 8.25E+05 gallons of waste liquids were discharged containing approximately 4.02E-02 curies of activities.

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3 Operations Summary (Continued)

June 1985 Refueling Information Unit 1 Unit I was in shutdown for its sixth refueling on June 1,1985 with a scheduled restart date of March 31, 1986. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and environmentally qualify instrumentations. The unit was shut down on March 19, 198$, and remained in cold shutdown until June 1,1985, because of unfinished modifications to meet environmental concerns.

There are 764 assemblies in the reactor vessel. The spent fuel storage pool presently contains 252 EOC-5 assemblies, 260 EOC-4 assemblies; 232 EOC-3 assemblies; 156 EOC-2 assemblies; and 168 EOC-1 assemblies. The present fuel pool capacity is 3,471 locations.

Unit 2 Unit 2 was shut down for its fifth refueling outage on September 15, 1984 with a scheduled restart date of December 15, 1985. This refueling outage will involve loading additional 8X8R (retrofit) assemblies into the core, finishing torus modification, turbine inspection, piping inspection, TMI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.

There are no assemblies in the reactor veseal. At month end, there were 273 new assemblies, 764 EOC-5 assemblies, 248 EOC-4 assemblies 352 EOC-3 assemblies, 156 EOC-2 assemblies, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 77 locations. All old racks have been removed from the pool and new HDR's are being installed.

4 Operations Summary (Continued)

June 1985 Unit 3 Unit 3 is scheduled for its sixth refueling outage approximately November 30, 1985, with a scheduled restart date of November 10, 1986. This refueling involves loading 8X8R (retrofit) assemblies into the core, and complete reinspection of stainless steel piping. The unit was shutdcwn on March 9, 1985, and will remain in cold shutdown until August 28, 1985, on an administrative hold to resolve various TVA and NRC concerns.

There are 764 assemblies presently in the reactor vessel. There are 248 EOC-5 assemblies, 280 EOC-4 assemblies,124 EOC-3 assemblies,144 EOC-2 assemblies, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacit/ of the spent fuel pool is 914 locations.

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5 Significant Operational Events 1

Date Time Event Unit 1 4

6/01 0001 End of cycle 6 refuel outage begins.

J 6/30 2400 End of cycle 6 refuel outage continues.

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Significant Operational Event _s Date Time Event

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Unit 2 6/01 0001 End-or-cycle 5 refuel and modifications outage continues.

6/30 2400 End-of-cycle 5 refuel and modifications outage continues.

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7 Significant Operational Events Date Time Event Unit 3

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6/01 0001 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.

a 6/30 2400 The unit has been placed on adainistrative hold until various TVA and NRC concerns are resolved.

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8 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferry 1

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DATE COMPLETED 8Y R. W. Motter TELEPHONE (205)~729-2508 MONTH June DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Netl lMwe. Net) 1

-0 17

-11 2

-13

-1[

13 3

-10

-11 g,

4

-10 20

-9 5

-10

-11 6

-10

-10 22 7

-10 23

-10 3

-10 24

-10 9

-10

-10 25

-10 10 26

-10 1I

- 10 27

-10 12

-10 23

-to 13

-10

~9 29 14

-10 30

-10 15

-12 3,

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'9 INSTRUCTIONS On ihn format, list the average daily umt power feelin MWe Nel for each day in the repurring month. Compute to the nearest whole megawatt.

19/771 8

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 2

UNIT

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7-1-85 DATE COMPLETED BY R. W. Mott u TELEPHONE (205) 729-2508 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL iMWe Net)

IMWe Net)

-3

-3 g7 2

-3 18

-3 3

-3 19

-3 4

-3 20

-3 5

-3 3,

_3 6

-3 22

-3 7

-3 23

-4 8

-2 24

-3 9

-2 25

-3

~3 10 26

-1 11

-2 37

-3 32

-3

-3 35 33

-3

-3 39 14

-3

,10 15

-4 3,

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-2 INSTRUCTIONS On this format,hst the average dul) unit power few!in MWe Nel for each day in the reporting numth. Compute to the nearest whole megawatt.

til/77)

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10 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 3

UNIT DATE ~7-7-85 COMPLETED BY

_R. W. Motter TELEPilONE (205) 729-2508 MONTit June DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe NetI (MWe-Net) g

-9

-9 37 2

~9,3 3

-8

_9 4

-9 20

-8 5

-9 21

-9

~9 6

22

-9 7

-9 23

-6 8

-9 24

-8 9

-9 25

-9

'9 10 26

-10 II

-8 27

-10

~9 12 28

-10 13

-9 29

-10 14

-9 30

-11 15

-9 16

-8 INSTRUCTIONS the ne. ire I hlA y J ih urut liiwcr leselin Mwe. Net for each day in the fcPutting inienth. Compute to i

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11 OPERATING DATA REPORT DOCKET NO. _50-259 DATE 7-1-85 COMPLETED BY _ R.

tL Mntter TELEPHONE r 9eMi 7'4-25CL OPERATING STATUS

1. Unit Name:

Browns _Fetry One N08'5

2. Reporting Period:

June 1985

3. Licensed Thermal Power (Mwit:

3293

4. Nameplate Rating 8.Grou MWe):

1152

5. Design Electrical Rating (Net MWe):

1065

6. Masimum Dependable Capacity (Geois MWe):

'109R 4

7. Masimum Dependable Capacity (Net MWe):

1065

8. If Changes Occur in Capacity Ratings (1: ems Number 3 Through 71Since Last Report. Gi e Reasons:

N/A

9. Pnwer Level To which Restricted.lf Any (Net MWe):

N/A

10. Reasons For Restrictions. lf Any:

N/A This Month Yr..to Date Cumulative

11. Houn in Reporting Period 720 4343 95.743

12. Number Of Houn Reactor Was Critical 0

1,6 7.78 59,521.38

13. Reacto.c Reserve Shutdown Hours 0

512.22 6.997.44 14 Hours Generator On Line 0

1.626.67 SR_267'26

15. Unit Roede Shutdown Hour, 0

0 0

16 Grnu Thermal Energy Generated (MWHI O

4_950 R21 16 R _066. 7 R 7 17 Grow Electrical Energy Generated (MWHI O

1.652.650 55.398.110

18. Net Electrical Energy Generated eMWH)

-7.213 1,582,606 53.796,427

19. Unit Sersice Factor 0

37.5 60.9

20. Unit Asailability Facto, 0

37.5 60.9

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21. Unit Capacity Factor (Using MDC Net) 0 la_2 52.8

22. Unit Capacity FactorIUning DER Net) 0 34.2 52.8

23. Unit Forced Outage Rate 0

55.1 23.6

24. Shutdowns Scheduled Oser Nest 6 Months IType. Date,and Duration of Eacht:

25. If Shut Duwn At End Of Report Period. Estimated Date of Startup:

9/14/86

26. Units in Tot Status arrior o Commercial Operationi:

Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCI AL OPER ATION 19/77i

12 OPERATING DATA REPORT DOCKET NO 50-260 DATE 7-1-85 COMPLETED BY R. W. Mottet TELEPflONE o n ca 7 7 9-2 '. '

OPERATING STATUS

1. Unit Name:

Browns Ferry Two N"8'S June 1985

2. Reporting Period:

3. Licensed ThermalPowerIMWI).

3293 1152

4. Nameplate Rating (Gross MWe):

5. Dewsn Electrical Rating (Net MWe):

106S

6. Maximum Dependable Capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A N/A

9. Power Lesel To which Restricted.lf Any (Net MWg:

10. Reasons For Restrictions.If Any:

This Month Yr..to Date Cumulative 720

_4343 90,630 II. Hours in Reporting Pen. d e

12. Number Of Houn Reactor was Critical 0

0 55,860.03

13. Reactor Newne Shutdown Hour, 0

0 14,200.44

14. Houss Generator On Line 0

0 54.338.36

15. Unit Resene Shutdown floun 0

0 0

16. Grou Thermal Energy Generated (MWH) 0 0

153,245,167 17 Gros Electrical Energy Generated (MWH) 0 0

50,771,798

18. Net Electrical Energy Generated (MWH)

-1.914

-15,601 49,287,372

19. Unit Senice Factor 0

0 60.0

20. Unit Availability Factor 0

0 60.0

21. Unit Capacity Factor (Using MDC Net) 0 0

51.1

22. Unit Capacity Factor IU>ing DER Net) 0 0

51.1

23. Unit Forced Outage Rate 0

0 23.0

24. Shutdowns Schedtled Over Nest 6 Months iType. Date,and Duration of Eschi:

25. If Shut puun A End Of Ret =>rt Period. Estimated Date of Startup:

2/24/86

26. Unit In Test Status IPrior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL EL-ECTRICITY COMMERCIAL OPER ATI(fA (4/77) i

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OPERATING DATA REPORT DOCKET NO 50-296 DATE 7-1-85 CO%IPLETED BY R. W. M6tter TELEPHOSE (20s) 729-25

OPERATING STATUS

1. Unit Name:

Browns Ferry Three NO '5

2. Reposting Period; Tima 19A5

3. Licensed Thermal Power (Mwt):

3293

4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWe):

inAs

6. Maximum Dependable Capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

8. If Changes Occur in Capacity Ratugs (items Number 3 Through 7) Since Last Report. Gi e Reasons:

N/A'

9. Power Leirl To which Restricted.lf Any (Net MWe):

N/A

10. Reawns For Restrictions. lf Any:

N/A This Month Yr. to Date Cumulative

11. Hours la Reporting Period 720 4343 73,055

12. Number Of Houn Reactor Was Critical 0

1,517.65 45,306.08

13. Reactor Rewne Shutdown Huurs -

0 508.05 5,149.55

14. Houn Generator On.Line 0

1,496.96 44,194.76

15. Unit Rewne Shutdown flour, 0

0 0

16. Grow Thermal Energy Generated (MWil) 0 4,649,840 131,868,z67 17 Gran Electrical Energy Generated (MWH) 0 1.572.770

_43,473,760

18. Net Electrical Energy Generated (MWH)

-6.394 1'505.662 42.171.423

19. Unit Senice Factor 0

34.5 60.5

20. Unit Asailability Factor 0

Ws An s

21. Unit Capacity Factor (Using MDC Net) 0 32.6 54.2

22. Unit Capacity Factor (Using DER Net) 0 32.6

_54.2

23. Unit Forced Outage Rate 100 65.5 21.6

24. Shutdowns Scheduled Oier Nest 6 Months iType. Date and Duration of Eacht:

November 85

25. If. shut Down At End Of Report Period. Esti:nated Date of Startup:

8/28/85

26. Units in f est Status tPrior ea Commercial Operation 1 Forecast Achiesed INIflA L CHIIICALITY INITIAL ELECTRICITY C041%IERCIAL OPER ATION (9/77) t

UNIT LilUIpOWNS AND POWER REDUCTIONS.

DOCKET NO.

50-259 UNIT NAME B rrwna Fe rry 1 4

DATE 1 a5 REPOR T MONTil June COMPLETED BY

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TELEPHONE - 205/729-2509 We::

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6.5 x Licensee g *'.,

Cause A Correceive No.

Date p

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jg5 Event s9 a?

Astmn to

$3

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• N 0 f0 Prevent Recurrence 6.

315 6/1/85 S

720 C

2 End of Cycle-6 Refuel Outage Begins E

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4 1-: Forced Reason:

Method:

Estubit G Instructituis S Scheduled A Equiprnent Failure (Explain)

! Manual f or Preparanon of D4i.i B Mainterunice ai Test 2-Man ual Sera m.

I nar) Sheets far Licerisce C Refuehng 3-Autonutic Scram.

Ewns Report (l i RI Fde int >RI G-D-Regulator) Restriction 4-Ot her il Aplain) 0161) i Operator Training & lisense l'urr.ination F. Ad runist rati'.e 5

G-Operational Error il.'xplain)

Exhibit I - Same Souree (9/77) llothes (Ext lain)

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3 50-260 UNil SilulDOWNS AND POWER REDllC110NS DOCKET NO.

UNIT NAME Browns Ferry 2 DATE 7-1-fl5 REPOR T MONiil __ Jime COMPIETED gy T. Thom IELEPHONE 205/729-2509

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Cause & Corrective No.

Date E

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Prevent Recurrence 3 7. j HeporI 8

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305 6/1/85 S

720 C.

4 EOC-5 Refuel Outage Cont.

(Controlled Shutdown 9/15/84)

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F. Forsed Reau>n Methed:

Exhibit G Instructions

$ Ss hedule<l UE.juirinen: Fa: lure il srlaml 141sni:21 for Prepasation of Data B Maintenan;e.a les 2 Manual S.;rarn.

Entry Sheets for Li,ensee C-Refochr.e 3-Autornanc S* rain.

Esens Repose (l.f RI Fde INURI:G-D Regulatan Rest'ict,, n 3 Othes illsplaan) 0161) i Operator luinniy A I s.cn c I sa.niaan n 1 Adnumst uit..

5 G-Operatsunal Le nn (laplaia l Exlubit 1 - Sanw Source 19/77) ll Other ( tiplain!

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-296 UNIT NAME R ros.m a Ferry 3 DATE 711/M REPORT MONTH Juno COMPLETED asY T '. G. Thom 11ELEPHONE (205) 729-2509 "w.

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yjf I8censee 51, g4 Cause & Correceive Date e:

4 2 ; ce I.vens s7 9.?

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156 6/1/85 F

720 F

The unit remains on administrative Cont.

hold until various TVA 'and NRC 4

concerns are resolved.

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Method:

Exhibii G. Insisocinms S: Scheduled A Fquipment Failure (l.splain) 1 Manual for Preparation of Data li Maintenance of Tes 2 Manual Scram.

Entry Sheets for Licensee C-Refueling

3. Automatic Scram.

Evens Repost (IJR)I de int!RI G.

D Regulatin) Resiniction 4 Other (1:xplaud OItil I l Operator Training A thcose lhamination 17-Adminnerasi.e 5

- G-Operational tirne il Aplain t lalubit ! - Same Souice 19/77) 11 Oiher (E splain) 8 e

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g Appendix B CSSC EQUIPMENT E!.ECTRICAL ltAINTOIANCE SD0iARY 9/29/82 For the Pfonth of June 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Hesults of To Preclude D t's System Component Maintenance The Reactor Malfunction Malfunctinn Recurrence 1985 l'

6/4 Radiation RM-90-251 Troubleshoot None RM-90-251 motor Breaker 208 tripped Monitor was put monitoring radiation cause of breaker was upgraded from after 30 minutes run on spare breaker monitor 208 tripping 1/3 IIP to 1 HP.

time 235 and returned when RM-90-251 Breaker could not to service.

is put in carry load service MR 558560 TACF 3-85-16-90 l

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CSSC EQUIPMENT ELECTRICAL tt\\INTE'JANCE SCDiARY 9/29/82 For the tranch of June 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude Dat9 System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1985 5/30 Fire PNLA-39-25-286 Found while None Defective relay Relay would not seal Replaced reley l

protection fire protection performing (K-6) in and drop out when panel, zone "W" S1 4.11.C.3 & 4 reset at pnl 25-286 MR 565256 relay 6/24 Standby BKR-63-6B Found while None Defective test Cannot test breaker Replaced switch liquid SLC pump 2B performing closed switch control motor breaker SM R00741 MR 589711 6/25 Fire pro-XA-39-25-311 Performing None Defective coil Alarm bell did not 3eplaced relay tection fire protection SI 4.ll.C.3&4 in K1 relay ring panel bell step 2.A MR 563540 i

alarm co 1984 l

11/5 HPCI BKR-73-0064 Found during None B-phase lug Breaker taken out of Replaced breaker breaker for scheduled screw stripped on service FCV-73-64, maintenance breaker MR 320369 IIPCI turbine item RO-0806A l

exhaust vacuum relief valve 1

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h CSSC EQUIPMENT ELECTRICAL MAINTENANCE St00tARY 9/29/82 For the Month of June 19 85 3-i Effect on Safe Action Taken 1

Nature of Operation of Cause.of Results of To Preclude

! D^ts System Component Maintenance The Reactor Malfunction Malfunction Recurrence

1985 I6/2 Neutron RLY-92-7CK9C Check relay None Defective coil Lost of pogition Replaced coil

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monitoring SRM-IRM drive 7C-K9C in panel indication on control control relay 25-14 in Rx room panel 9-5 MR 519098 i

b1dg 6/4 Control CHR-31-0007 Replace com-None Bad compressor Purge unit would not Replaced compressor bay heat-control bay pressor on due to purge operate ing vent chiller 1-B purge unit unit running MR 565428 and AC purge unit while lines valved out 6/9 Neutron RLY-92-7CK9F Check relay None Burned up coil Loss of position l Replaced coil.

monitoring IRM "B" de-7C-K9F in panel indication on IRM "B"'

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tector relay 25-14 in Rx detector (CR panel 9'-5 ) MR.559614 b1dg.

6/12 PCIS RLY-64-16AK19 Investigate fuse Actuation of Bad coil in Fuse blew on panel

- Replaced coil drywell floor failure engineered safet y relay 16AK19 9-42, causing drywell drain sump feature (ESF) sump inboard isolatior MR 555562 pump interlock v1vs and TIP ball

. LER 259-85024 relay valves to close 6/23 RPS RLY-99-5AK6D Investigate None Burned up coil Loss of relay functior Replaced relay reactor vessel and locate low level source of MR 519359 Scram trip burned odor relay in auxiliary instrument room 4

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a." TS PLSR-l aidci.r.l.2 Pt.% ' I!iri T g3.g,,};g, gg Appendix B CSSC EQLIIPMENT ELECTRICAL MAINTENANCE SLI:OtARY 3

9/29/82 For the Month of June 19 85 I

Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude D~te System Component Maintenance The Reactor Malfunction Malfunction Recurrence

'i 1985

'. 6 /19 480V control BitR-266-00A/

Troubleshoot None Defective coil in Causing fuses to blow Replaced coil bay vent 04A control cause of ground 42N relay when attempting to boards bay vent and correct transfer breaker MR 559687 board A problem normal supply breaker a

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BROWNS FERRY NUCLEAR PLANT UNIT CSSC EOUIPMENT MECHANICAL MAINTENANCE

SUMMARY

' For the Month or June 19 85 I

EFFECT ON SAFE ACTION TAKEN DATE SYSTEH COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE ll MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

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BROWNS FERRY NUCLEAR PLANT UNIT 2

'CSSC EQUIPMENT MECHANICAL MAINTENANCE

SUMMARY

-For the Month of June 19 85 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MAf_ FUNCTION MAI. FUNCTION RECURRENCE

'6/9/85.

69 2A RWCU Pump Rebuilt Pump Use and wear Pump seals Disassembled /

leaked rebuilt purr.p MR 520542 e

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BROWNS PERRY NUCLEAR PLANT UNIT CSSC EQUIPMENT MECHANICAL MAINTENANCE

SUMMARY

For the Month of J"""

19 85 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NAIURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION NATFUNCTION RECURRRMCE 6/6/85' 82 3B diesel Repair cracked wel l Bracket cracked Bracket removed generator on fuel filter repaired & re-manifold installed MR 182497 U$

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4 24 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT June 1985 MAJOR WORK COMPLETED A.

Unit 1 1.

'the official refueling outage start date is June 17, 1985. As of June 30, the drywell head was removed and preparations were underway to detension the reactor vessel head. The modification to ensure seismic integrity of the crane during vessel head lift with the first five inches _of travel has been deferred until reassembly of unit 2.

2.

Disassembly, rotor removal and decontamination of "B" low pressure (LP) spindle will start after main steam line plugs are seated. Work completed includes partial layout to support removal, sandblast and inspection of the spindle.

B.

Unit 2 1

Repairs to the "A" jet pump instrument lines were completed, vessel head and internals were removed, and the cavity floodup was completed on June 17, 1985.

2.

Turbine Floor - The lifting beam was transported to unit 1 floor to support disassembly of 1B LP turbine.

3 Drywell/ Torus - The torus paint compactor demobilized on June 5, 1985. Overlay of GR-2-15 was performed between June to and 17.

Followup inspection indicated a flow which will require reworking the weld. Weld DSRHR-SA was evaluated as unacceptable and. will require repair.

4.

Balance-of-Plant - Limited condenser work. The Condenser Circulat-ing l

Water system was closed up to prepare for hypochlorite treatment.

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OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT June 1985 MAJOR WORK COMPLETED B.

Unit 2 (Continued) 5.

Valves - No significant work was completed.

"B" I/B Main Steam Isolation Valve (MSIV) and both "C" MSIV's will require disassembly and rework due to vendor error.

6.

Major Modifications - Electrical modifications progress was significantly restricted by lack of Quality Control (QC) inspector coverage due to prioritization of this coverage on unit 3 Machanical

~

modifications' progress was more severely impacted due to direct impact on engineering and craft efforts, as well as the forementioned problem with QC inspector coverage.

a.

ECN P0392 (SCRAM Discharge Header Modifications): Vent lines installation is in progress and electrical work i,s 40%

complete.

b.

ECN P0533 (TORUS Temperature. Monitors): Conduit installation is 70% complete.

c.

ECN P0324 (Drywell High Range Radiation Monitor):

Hanger fabrication is in progress. Conduit installation is 55 complete.

d.

ENCs P0322/P0323 (Drywell and TORUS Wide Range indicators): 40%

overall complete.

e.

ECN P0354 (Effluent High Range Radiation Monitors): 155 complete.

i f.

ECN P0085 (Drywell Temperature / Pressure Monitors):

15% complete.

g.

IE Bulletin 79-01B modifications are 65 complete.

1

26 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT June 1985 MAJOR WORK COMPLETED B.

Unit 2 (Continue'd) 7.

Critical Path a.

ECN P0126; Replace transmitters with analog / trip system.

Conduit Installation Location June 1 July Auxiliary Instrument Room 905 995 Elevation 593 205 80%

Elevation-541 605 Tot b.

ECN P0361;. Torus attached piping hanger modification.

No progress this month.

8.

Return to Service Date:

July 1: December 5, 1985 June 1:

October 5,1985 a.

Schedule slip reflects projected impact of unit 3 short outage on i

unit 2 work.

b.

The increased duration of the unit 2 outage will require Inte-l grated Leak Rate Testing (ILRT) during this outage in lieu of the cycle 6 outage. The increased duration will also require l

additional Local Leak Rate Test (LLRT) of most previously tested

~

valves due to Appendix "J" testing periodicity requirements.

i l