ML20129G323

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1985
ML20129G323
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/30/1985
From: Jones G, Motter R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8507180023
Download: ML20129G323 (30)
v • d • e


Text

--

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT _,

MONTHLY OPERATI,NG REPORT TO NRC April 1, 1985 - April 30, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 J

Submitted by: LM.d7^

f Plant Manager

(,

c 9 '\ s t 8507180023 DR 850430 ADOCK 05000259 PDR

tab:3 0F CONTENTS Operations Summary. . . . . . . ... ... . . . . . . . . . . 2

~

Refueling Information . . . . . . . . . . . . . . . . . . . . . 4 Significant Operational Instructions. . . . . . . . . . . . . . 6 Average Daily Unit Power Level. . . . ... . . . . . . . . . . 9 Operating Data Reports. . . . . . . . . . . . . . . . . . . . . 12 Unit Shutdowns and Power Reductions . .

. . . . . . . . . . . . 15 Plant Maintenance . . . . . . . ... .... . . . . . . . . . 18 Outage Maintenance & Major Modification . . . . . . . . . . . . 25 e

=e h

m e a O

9

~, - _ . - . - . --

2 -

/

Operations Summary April 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 six reportable occurrences and one revision to previous occurrences reported to the NRC during the month of April.

Unit 1 The unit' was in cold shutdown the entire month as it undergoes several modifications including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588.

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.

4

. 3 Operations Summary (Continued)

Apr.il 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 2.21E+06 gallons of waste liquids were discharged containing approximately 1.09E-01 curies of activities.

0 4

,e- - ,-- -cr, -,- , ,- , , - , - -

4 -

Operations Summary (Continued)

April 1985 Refueling Information Unit 1 Unit 1 is scheduled for its sixth refueling approximately 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, 1985, and will remain 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 August 1,1985. '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 vessel. 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.

. 5 Operations Summary (Continued)

April 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 shutdown on March 9, 1985, and will remain in cold shutdown until June 4, 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 E00-2 assembli'es, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spe,nt fuel pool is 914 locations.

6 9

6 -

Significant Operational Events Date Time Event Unit 1 4/01 0001 The unit remains in a shutdown condition until it undergoes several modifications including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588.

4/30 2400 The unit remains in a shutdown condition until it undergoes several modifications including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588.

3 y

(

. 7 Significant Operational Events Date Time Event Unit 2 4/01 0001 End-of-cycle 5 refuel and modifications outage continues.

4/30- 2400 End-of-cycle 5 refuel and modifications outage continues.

6 Oe 4>*

O

8 -

Significant Operational Events Date Time Event Unit 3 4/01 0001 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.

4/30 2400 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.

e 9

f l

l l

l 1

i

9 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT Browns Ferry One

~

DATE '_5-1-85 COMPLETED BY _R. W. Motter TELEPHONE (205) 729-2508 April MONTH

= .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) (gwe. Net) .

~

1 -7 37 -6 2 -7 (g -6 3 -7 39

-8 4

-8 9

-9

-7 -8 5 21 6

-7 ' -7 22 7 -8 23 -8 g -8 -8 24 9 -7 -8 25

~ ~

10 26 II -6 27 -7 12

-7 3g

-8 13 -6 29

-7 .

g4 -6 --

3g 15 -6 3, 16

-7 INSTRUC110NS ,

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

19/77)

~-

10 < .

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 B'r owns Ferry Two UNIT DATE 5-1-85 COMPLETED BY R. W. Motter TELEPHONE (205) 729-2508 MONTH April DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL iMWe-Net) (MWe-Net) 1

-6 37

.-6 2 -6 3 -6 3

~7 -4 19 4 -6 20 -3

-0 -4 5 21

-6 -5 6 -

22 7 -6 23

-5 g -6 3

-5

-6 ~

9 25

-6 -5 10 26 II -6 27 -5 12

-6 28

-5 ,

13

-6 -5 29 g4 -6 '

~

~'

~30

~

15 3 16 -6 INSTRUCTIONS .

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

(9/77)

_ _ _ _ _ - _ _ _ _ - _ ._ .__________w____.

'^ ~

- ;, m .m . ..v= - . _ - --

=

~ 11

. . i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT Browns Ferry Thrt.

5-1-85 DATE COMPLETED BY R. tJ. Mot t e r TELEPHONE - (205) 729-2508 MONTH April DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (ywe. Net) 1 -16 ,7 _11 2 -10 ,3 _1f 3

-11 i, -10 4 -10 20 -11 5 -11 -11 23 6 - 10 22 -10 7 -11 23 -10 3

-11 -11 24 9 -10 25 -11 10 *

- 10 26 -11 1I -10 27 -11 12 -10 yg _11 13 -10 29 -10

~

14 - 10 -11 30 15 -11 3g 16 -10 INSTRUCTIONS .

On thit. format. list the average daily unit liower lesel in MWe Net for each day in the reporting month. Compute to the nearest whole nwgawait.

(9/77)

12 , ,

OPERATING DATA REPORT DOCKET NO. 50-259 DATE 5-1-85

- COMPLETED BY R. Motter TELEPHONE 7?o-?snR OPERATING STATUS

1. Unit Name: Browns Ferry One Notes
2. Reporting Period: April 1985
3. Licensed Thermal Power (MWI): 3293
4. Nameplate Rating (Gross MWe): 1152
5. Design Electncal Rating (Net MWe): 1065 ,_,
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 Thmugh 7) Since Last Report. Give Reasons:

N/A N/A

9. Power Level To which Restricted,1f Any (N/ANet MWe):
10. Reasons For Restrictions,if Any:

This Month Yr.-to-Date Cumulative i1. Hours in Reporting Period 719 2,.879 94,279

12. Number Of Hours Reactor Was Critical 0 1647.78 59.521.38
13. Reactor Reserve Shutdown Hours 0 512.22 6,997.44
14. Hours Generator On.Line 0 1,626.67 58,267.26
15. Unit Reserve Shutdown flours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 4.982.9,81 168.144.427 17 Grow Electrical Energy Generated (MWH) 0 _,_ _, 1.652.650 55.398,130
18. Net Electrical Energy Generated (MWH) -6,223 1,596,808 53,810,629
19. Unit Senice Factor 0 56.5 61.8
20. Unit Availability Factor 0 _ . 56.5. 61.8
21. Unit Capacity Factor (Using MDC Net) 0 52.1 53.6
22. Unit Capacity FactorIUsing DER Net) 0 52.1 53.6
23. Unit Forced Outage Rate 100 43.5 22.9
24. Shutdowns Scheduled Over Nest 6 Months (Type. Date, and Duration of Each):

June 1, 1985 - Refuel outage begins.

25. If Shut IMwn At End Of Report Period. Estimated Date of Startup;.
26. Unitiin Test Status IPrior o Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77)

13 f

OPERATING DATA REPORT DOCKET NO. 50-260 DATE 5-1-85

. COMPLETED BY R. W. Motter TELEPilONE (205) 729-2508 OPERATING STATUS

1. Unit Name: Br wns Ferry Unit Two Notes
2. Reporting Period: April 1985
3. Licensed Thermal Power IMWil: 3293
4. Nameplate Rating (Gross MWe): 1152
5. Design Electrical Rating (Net MWe): 10 65
6. Manimum 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) S'iiice Last Report, Give Reasom:

N/A

9. Power Level To Which Restricted,if Any (Net MWe): N/A
10. Reasons For Restrictions.lf Any: /A This Month Yr..to.Dat e Cumul.itive
11. Ilours in Reporting Period 719 2879 89,166
12. Number Of Houn Reactor Was Critical 0 0 55,860.03
13. Reactor Reserve Shutdown Hours 0 0 14,200.44
14. Hours Generator On.Line 0 0 54.338.36
15. Unit Resene Shutdown flours 0 0 0
16. Crow Thermal Energy Generated OIWH) 0 0 153,245,167 .

17 Grow Electrical Energy Generated (MWH) . 0 , _ , , , _ _ _ ,

0 50,771,798

18. Net Electrical Energy Generated (MWH) -3,880 -12,112 49,290,861
19. Unit Service Factor 0 0 60.9

~

20. Unit Availability Factor 0 ~0 60.9
21. Unit Capacity Factor (Uning MDC Net) 0 0 51.9
22. Unit Capacity Factor (Using DER Net) 0 0 51.9
23. Unit Forced Outage Rate 0 0 23.0
24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date, and Duration of Each):
25. If Shut Down At End of Reimrt Period Estimated Date of Startup:

September 1985

26. Units in Test Status (Prior io Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION tu/77 )

14 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 5-1-85 COMPLETED BY _R. W. Motter TELEPHONE (20s) 729-2508 OPERATING STATUS

1. Unit Name: Browns Ferry Unit Three Notes
2. Reporting Period: April 1985
3. Licensed Thermal Power (MWt): 3293
4. Nameplate Rating (Gross MWe): 1152
5. Design Electrical Rating (Net MWe): 1065' --
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

9. Power 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. Hours In Reporting Period 719 2879 71591 0 1517.65
12. Number Of Hours Reactor Was Critical 45,306.08
13. Reactor Rewrve Shutdown Hours 0 508.05 5,149.55
14. Hours Generator On.Line 0 1,496.96 _44,194.76
15. Unit Rewrve Shutdown flours 0 0 0 16 Gross Thermal Energy Generated (MWH) 0 4,649,840 _131,868,267 17 Gross Electrical Energy Generated IMWH) 0 1,572,770 _43,473,760
18. Net Electrical Energy Generated (MWH) -7,63F,___,,, 1,518,837 42,184.598 U 52.0 61.7
19. Unit Sersice Factor
20. Unit Assilability Facto, 0 --

- 52.0 61.7

21. Unit Capacity Factor (Using MDC Net) 0 49.5 55.3
22. Unit Capacity Factor IUsing DER Net) 0 49.5 55.3
23. Unit Forced Outage Rate 100 48.0 19.5
24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date,and Duration of Eacht:
25. If Shut Down A End of Report Period. Estimated Date of Startup:, May 10, 1985
26. Units in Test Status IPrior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMM ERCIAL OPER ATION 19/77)

UNIT SilUIDOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT NAME Browns Ferry Three DATE 5-1-85 REPORT MONTH April COMPLETED BY . Ted Thn=

TELEPHONE _(205) 729-2171 w.

_ E E

-o .E_ ? 'h jY3 Licensee ,E n, . Cause & Corrective No. Date g g 4 2gE Event  :; ? {*?

c- Action to

  • j~ $ e~5g u Report
  • N0 $' Prevent Recurrence O

c 156 4-1-85 F 719 F The unit remains on administrative Cont hold until various TVA and NRC concerns are resolved.

G s

I 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G . instructions A Lyuipment Fadure(Explamp l-Manual for Prepasation of Data It Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LER) File (NtlREG-D Regulaini> Restriction 4-Ot her ( Explain) 0161) i Operator Tiainig & liense I:xanunation l' Administrati.e 5 G-Operatioaa! Lisor (IN itaioi n 19/77)

Eshibit I Same Source s Il-Oiher t iTpland I

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAME Browns Fetry Two DATE 5-1-85 April COMPT.ETED BY ' TaA Tha=

REPORT MONTH TELEPHONE (205) 729-2171

= ri 3 sa . - ,

. .2 _e E 7 .s X Licensee g *, E"L Cause & Corrective No. Dale g g  ; ,3 5 Event s7 g'E a Action to

  • 5

$5 j di g Report n (N C

[O Prevent Recurrence b

305 4/1/85 S 719 C 4 EOC-5 Refuel Outage Cont (Controlled Shutdown 9/15/84)

E a

i 2 ~

3 4 F: Forced Reason: Method:

S Schedulett Exhibit G-Instructions A Equipment Failure (Explam) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3- Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriezion 4-Ot her ( Explain) 0161)

F-Operator Tr.sining & 1ivnse I xamination F Administrati.e 5 G-Operational Eiror II.xplain Exhibit I - Same Soince -

19/77) Il-Ot her ( L xplain) I

UNIT SilUTl) OWNS AND POWER REI)UCT:ONS DOCKET NO. 50-2so UNIT N AME . Browns Ferry 1 DATE 5-1-As REPORT MONTH April COMPLETED BY - TaA Th -

TELEPHONE (205) 729-2171 n.

O P$ 7 a;g, y' ' ,' 93,,,

~

y 55 5 5 .5 'd Licensee j.g, ja'1, Cause & Correcthe J- 3.g g ggg Evens g,7 97 Ay, ion io o: E Report e in v g D5 j ]O Prevent Recurrence 6

314 4/1/85 F 719 D .

The unit remains in a shutdown Cont condition until it undergoes several modifications, including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588. C 4

1 2 3 4 F: Forced Reason: MethuJ:

S: Scheduled Exhibit G -Instructions A. Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram. Entry Sheets l'or Licensee C-Refueling 3 Autom:stic Scram. Event Report iLLR FileiNL'RL6 D Regulatory Restriction

  • 4-Ot her ( Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explaial Exinbn 1 - Same Somce 19/77) s Il-Other ( Explain)

U '

M anUW.W FERRY NUCLEAR PLAhT UNIT g"a C CSSC EQUIPMENT ELECTRICAL MAINTENANCE St?DtARY 9/29/82 For the Month of April 19 85 i '

Effect on Safe I *

.\etion Taken Nature of Operation of Cause.of Date System Component Maintenance Results of To Proclude The Reactor Malfunction Malfunction Recurrence 1984

,11/20 480V OXF-219-TDA Troubleshoot None Bad fen motor Fan tripped after e Replaced fan motor

. Diesel Aux d/g transformei exhaust fan short running time

! Bds TDA exhaust fasi motor

'1985 MR 321021 4/2 Standby FS-065-042B Troubleshoot None Bad flow switch Flow switch inop. "

Corrected wiring-gas treat- SGT fan B flow switch; Also, wires found ment DR 85-0206; disch flow correct wiring terminated on wiring Replaced flow switch panel & components MR 555502 found labeled incorrectly .

4/6 EECW ZS-067-0088 SI 4.2.B-67 None Actuator not A-1 RHRSW pump failed

  • 3 Adjusted actuator limit switch step 3.1.1.f striking limit *

, to start during SI to strike limit on EECW pump A switch (out of supply valve adjustment) switch g MR 179150 4/6 EECW ZS,-067-0089 SI 4.2.B-67 None Actuator was nqt B-1 RHRSW pump failed Adjusted actuator limit switch step 3.1.1.g striking limiti to start during SI to strike limit on EECW pump switch (out of switch B supply valve adjustment)

MR 180456 4/24 RHRSW 4160 Time delay re- SI 4.2.B-14 None Relay TD2C did. RHRSW pump B3 was Replaced relay logic lay TD2C not pick up as declared inop MR 566564 controls auto starts required in .

pmp B3 28 sec- 28 ! I second

'onds after accident signal '

D 4

9 l

BROWNS FERRY NUCLEAR PLANT UNIT I F RM ,

CSSC EQUIPMENT ELECTRICAL HAINTENANCE St?DtARY 9/29/82 For the Month of April 19 85 1

1 Effect on Safe *

.\etion Taken i Nature of Operation of Cause.of Results of To Preclude

! D'to System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1985 4/19 Annunciatoi XA-55-4A Performing None Persohnel error Resulted in' loss of Replaced 35 "4000"

& sequen- annunciator SI 4.1.A.9 when jumpering annunciation panel cards. Repaired tial panel 9-4 relay SAK3C 9-4 events power supply cards.

Relamped panel.

recording Verified proper operation MR 557624 9

A G 4

a 9

e f 9 e '

e O 9

.9 1

l l s k l

I  ;

'T 3 l

, BROWNS FERRY NUCLEAR PLANT UNIT 2 BF IL 30

.: CSSC EQUIPMENT App ndix B ELECTRICAL MAINTENANCE St3DtARY 9/29/82 For the Month of April 19 85 Effect on Safe Nature of Operation of l Action Ta.'<en Cause.of Results of '

To Preclude D'tm System Component Maintenance The Reactor Malfunction '

Malfunction '

Recurrence 1985 3/28 Control HCU-85-58-23 EMI 50 None Bad level switch rod drive hydraulic Found during pre- ' Replaced level control unit ventative maintenanco switch MR 556103 4/2 Neutron RLY-92-7CK9K Replace relay None monitoring IRM channel F Relay coil burned Rod block would not Replaced relay coil or coil. Found out clear bad on MR55753 MR 558123 4/3 Neutron RLY-92-7CK7B Troubleshoot None Relay coil burned monitdring relay Replaced relay -

, *MR 555761 E$

4/8 Neutron RLY-92-7CK7J Replace coil None Relay coil burned monitoring Replaced relay coil on relay out MR 554134 4/11 Rx bldg RLY-64-16AK72 Relay found None Relay coil burned #6 fuse in pnl 9-43 ventilation drywell diff smoking. Repair Replaced relay out blown MR 180469 Press intik  !

& control rm ,

LER 259-85011 i isolation  ?

f

- I

- e

.O

- l l'

. .il

~ . . .

, 25KUWNS FERRY NUCLEAR PLAST UNIT , [p g37g 33

? CSSC EQUIPMENT ELECTRICAL HAINTENANCE SL? DIARY 9/29/82

} For the Month of April 19 85 i

Effect on Safe i

  • Action T.Uen 6

Nature of Operation of Cause.of

} D*to System Component Results of To Preclude Maintenance The Reactor l Malfunction Malfunction Recurrence j 1985 l 3/1 Rx b1dg Penetration Repair pene- None Marirtite board Degradation of primary Repaired penetra-ventilation Rx bldg. el tra tion pushed back, containment isolation tion. QA smoke 593 north leaving penetra-tested repaired area wall at cable tion open to Rx e

tray UAJ side MR 182735 3/27 Diesel Diesel gen Troubleshoot None Relay contacts False annunciation generator Replace relay alarm pnl invalid alarm stuck closed 9-23D "D/G 3D control MR 176680  ;

, circuit ground" 4/2 RHR MVDP-74-46 Troubleshoot None Motor leads were Valve would not

  • Relugged motorg leads RHR sys I-II valve *

. pulled out of operate after post- per EMI 58.2 -

crosstie viv stak-on lugs maint test step 10.3 of SMMI 15.0-B MR 558122 4/13 Control RbY-85-3AK8 Troubleshoot, None Bad coil in rel.ay Blowing fuses rod rod control relay 3AK8 Replaced relay drive relay MR 556601 4/21 Diesel RLY-82-SSP 2 Replace speed None generator diesel gen Relay had defective F und during Replaced relay sensing relay circuit- SI 4.9.A.l.d 3B speed SSP 2 MR 554116

sensing relay

~ 4/22 Diesel ,RLY-82-SFD2 Replace time None Set point drift helay had erratic Replaced relay generator diesel gen. delay relay '

timing during EMI 3

. . 3B time SFD2

io delay relay MR 554118 4/25 Door Door 260-249 Troubleshoot None Door did not Both doors (249 & 248) Replaced electric interlock personnel cause of door latch when closed ,open at same time - strip

& alarm airlock malfunction

  • Bad electric strip causes breach of door el 565 secondary contain- MR 556486 ment LER 296/85012

]

BROWNS FERRY NUCLEAR PLANT UNIT 1 CSSC EOUIPMENT MECHANICAL MAINTENANCE

SUMMARY

For the Month of April jg 85 ,

i EFFECT.0N SAFE ACTION TAKEN DATE SYSTEM COMPONENT NA'nlRE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MalRUNCTION RECURRENCE 68-85 268 1DN LPCI MG Change bearing None None Replace bearing set between motor and -

flywheel ,

4-8-85 67 FCV-67-50 Replace broken Normal use Replaced nipple; nipple to control water strainer to FCV-1-67-50 U

G S

e

(

  • i .

e W

I

  • . N EE KDE AUC .

~

TLN e U CE NER n ORR o IPU N T C COE ATR FN OO I e ST l TC sb L! aa UU f

wre SF pp EL RA mo M un Pi g

N n O i FI r OT r C

! a Ef e SU UF w  !

AL n CA e M k o

r B

Y 5 R 8 E 2 A FF 4

0 AOR f S O T U NT I S NOC N OIA e U E TE n C TAR o T N CR N N A l EEE A N i FPH L E r FOT -

P T P E N A

  • R I A A r E M o ,

L d C L h E n U A t FC a N C n ON s I o A pr Y N M El l mi R A RE ua R H e UT P p E C h Tl l e

F E t AI er M NA v S r M oe N o mk J

E F ea O Rm R

B T

N p E m H u 0 P P '

i

! R 0 H C R B

2 M

E s T

T S 4 N Y 7 E S M

P I

U Q

E C

S S E 5 C T 8 A -

D 4 1

3 1t 6 i! IlI jfiI!  !!i .l . ,  ! il

,:  ;! ' i . , I

N p

. EE mw

. KDE ue AUC png TL!i n CE tli NER ll r ,

ORP i a IPU T C ut r COE b sa ATR ene Ri w FN OO I

ST e l

TC sb LN aa UU wre SF EL pp RA i mo l

un Pi . I*

N O

FI OT C

EN SU e ,

UF s AL U CA M

e Y

3 R E A FF M AOR M 9 S O T U 1 NT I S NOC N OIA TE e

U E n C TAR o T N CR N N A EEE A N FPH L E FOT P T ' E N .

R I A A r d E H o n L a .

C L h E

  • U A t FC g r N C n ON n fo I o A i Y N M EN p R A RE ip R H e 1 T p m E C h TN u F E t AI e pri M iA l vl a S r M olp N o m l F e ue Rpr O'

R B

p T m N u E P N

O U P C ,

M U O R C

A 3

M E

T T S N Y E S M

P I 9 U 6 Q .

E C

S S E C T 5 A 8 D -

8 4

g!  !! i.Ii j . ,I4

25 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT April 1985 MAJOR WORK C0MPLETED A. Refuel Floor

1. Westinghouse fuel was received (4 rods, 1 dummy) on April 3, and was transferred to the refuel floor on April 23
2. Fuel shuffle started on April 15; reported complete on April 30, 1985.

3 The reactor building crane was released for lifting.on April 23

4. Vessel drain preparations included portable pumps installed April 23,

, moisture separator set April 25, cavity drained, vessel head and HEPA filter installed, and drywell shield plugs set on April 28.

B. Turbine No major work completed; awaiting release of turbine building cranes.

C. Drywell

1. Post-IHSI in-service penetrant tests were completed on April 8, 1985.
2. Temporary instrument lines were installed and vessel drain in preparation for nozzle replacements was in progress on April 30.

D. Major Valves Valve 23-580 was disassembled, cleaned, and reassembled in preparation for Residual Heat Removal Service Water (RHSW) 10-year hydro.

E. Balance-of-Plant

1. Repair work in "C" condenser was completed on April 8 with the exception of one 8" elbow, which will require a modification.
2. "2B" RHR heat exchanger work was completed on April 16.

26 ,

u OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT April 1985 MAJOR WORK COMPLETED (Continued)

F. Modifications

1. ECN P0392 (SCRAM Discharge Header Modifications) - removed old scram discharge instrument volumes on April 2.
2. ECN P0555 (Torus Sandblast, Paint and Heat Cure) - sandblasting, painting of 12 bays, and heat cure of 11 r 16 bays were completed as of April 30. ..
3. ECNs/ Work Plans reported field complete as of April 30, 1985.

ECN Work Plan Description a

P0083 2219-84 Replace RHR Pump Seal Heat Exchanger "B" and "D" P0093 6847-84 -

Remove and Modify Torus ECCS Strainer Baskets P0126 2163-84 Set Panels 25-5&6 C/D P0126 2167-84 Install conduit in ceiling of Elev. 565' P0126 2152-84 Core Drills ,

P0126 2165-84 Conduit in Turbine Building P0157 2018-84 Cap & Remove 1" EECW Piping in Core Spray Room P0192 2005-84 Relocate RHRSW Vent Valves P0334 -

Changeout Refuel Platform Air. Compressor P0361 2063-84 T.A.P. : RHR LP.2 P0361 2062-84 T.A.P. : RHR LP.1 P0361 2056-84 T.A.P, : C.S. LP.2 P0361 2074-84 T.A.P. : C.S. LP.2 P0361 2080-84 T.A.P. : HPCI P0361 2064-84 T.A.P. : RHR LP.2

t

- 27 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT April 1985 MAJOR WORK COMPLETED (Continued)

F.- Modifications (Continued)

ECN Work Plan Description P0392 2199-84 Remove Existing SDIV Instrumentation P0533 2175-84 Torus Temperature Monitor Conduit Installation-on Elev. 519' Pedestal P0555 2130-84 Remove Torus Baffle Supports

~

P0585 - Replace Diesel G'enerator Speed Sensing Switches P0597 2159-84 Increase Range of Reactor Feed Pump Flow Instrumentation P0612/13 2238-84 Weld and Machine MSIV Poppets P0646 10387 Add / Replace Diesel Air Start Valves P0672 2191-84 Remove PS-3-57 A-D & Associated Wiring P0688 2116-84 Modify FCV 76-xx/84-xx To Make Flange Testable P0690 2116-84 Modify FCV 76-xx/84-xx To Make Flange Testable P0695 2116-84 Modify FCV 76-xx/84-xx To Make Flange Testable P0697 2113-84 -Drill Ventilation Penetrations P0697 2102-84 Drill HVAC (Control Bay) Platform Holes P0720 2060-85 Prefabricate Jet Pump Instrument Piping P0738, etc Various Physical Security Plan Modifications P3085 2066-84 Replace PS-73-1A/B P3134 2004-84 Modifh Mounting Bracket FM-84-19B/-20B P3138 2001-85 Replace B&D RHR Pump Room Cooler

28

/

OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT April 1985 CRITICAL PATH A. Work Plan Approvals; Modifications Group April 1 May 1 Change Total Workplans 280 269 -11 Approved Workplans 61 100 +39 Outstanding Workplans 219 169 -50 Workplans in Approval Cycle 69 -- 78 N/A B. ECN P0126; Replace Transmitters with Analog / Trip System Conduit Installation' Location 'N~pril 1 May 1 Auxiliary Instrument Room 20% 60%

Elev. 565' 75% 99%

Turbine Building 90% 99%

Spreader Room 10% 905 Elev. 593' -

20%

C. ECN P0361; Torus Attached Piping Hanger Modifications Hangers Installed: April 1 - 83 May 1 - 161 Hanger Status by System: April 1 May 1 HPCI 17% 41%

RCIC 41% ~ 44%

RHR I 43% 66%

RHR II 625 - 64%

CS I 4% 79%

CS II 27% 49%

Drywell Torus Purge 36% 59%

RETURN TO SERVICE DATE: May 1: Se tember 20, 1985 April 1: September 21, 1985

m:{c

/ '

NoNa N rh N oheNr nk P. O. Box 2000 Decatur, Alabama 35602 MAY 101985 Nuclear Regulatory Commission

~ 0ffice of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the April 1985 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3

-Very truly yours,

& TENNESSEE VALLEY AUTHORITY t

4 G. T.; Jones Plant Manager i..

, Enclosures cc: Director, Region II INPO Records Center

. Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway

,: Atlanta, GA 30303 (1' copy) Atlanta, GA 30389 Director, Office of Inspection and Enforcement

' Nuclear Regulatory Commissiar Washington, D. C. 20555 If a;' - )

Mr. A. Rubio,' Director Electric Power Research Institute

.P. O. Box 10412 Palo Alto, CA 94304

' {\

An Equal Opportunity Employer

Retrieved from "https://kanterella.com/w/index.php?title=ML20129G323&oldid=2917435"