ML20199D766

Monthly Operating Repts for Mar 1986

ML20199D766
Person / Time
Site:	Browns Ferry
Issue date:	03/31/1986
From:	Robert Lewis, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
0058B, 58B, NUDOCS 8606230055
Download: ML20199D766 (23)

Text

_.

TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT NONTHLY OPER TING REPORT TO NRC MARCH 1, 1986 - MARCH 31, 1986 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:

Plant Manager ha 1 EON Ifg 8

=_. :

CONTENTS Operations Summary.

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

3 Significant Operational Events.

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

8 Operating Data Reports.

. 11 Unit Shutdowns and Power Reductions.

. 14 Plant Naintenance.

. 17 Addenda - Revision to February reports.................

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Operations Summary MARCH 1986 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 NRC during the month of March.

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

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 for the unit's environmental qualifications outage to comply with NRC requirements.

This was prepared principally by B. L. Porter.

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2 Operations Summary (Continued)

MARCH 1986 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unit 3 l

Shell at water line 0.00620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629 0.14326 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.

Common System Approximately 8.94E+05 gallons of waste liquids were discharged containing l

approximately 1.82E-02 curies of activities l

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3 Refuelina Information NARCH 1986 Unit 1 Unit I was in shutdown for its sixth refueling on June 1, 1985, with a scheduled restart date of March 1989. This refueling outage will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 1 items are environmental qualification of electrical equipment (10 CFR 50.49), torus modification (NUREG-0661), containment modifications (NUREG-0737),

electrical changes (Appendix R 10 CFR 50) (all). NSIV modifications, modifica-tion of masonry walls (IEB-80-11), evaluation of vent drains (LER-82020), valve modification (Appendiz J), HPCI concerns, modification of PCIS logic (LER i

259-85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG-0737), RPS modifications (IE Notice 78-45), H 0 8 ample line modification (LER 81-050), radiation 22 monitors modification (LER 80033) EECW carbon to stairless pipe change out, and all NRC cosunitment items except Anticipated Transients Without Scram (ATWS) modifications which is scheduled for next outage. The unit was shut down on March 19, 1985, and remained in cold shutdown until June 1, 1985, because of unfinished modifications to meet environmental concerns.

There are 0 assemblies in the reactor vessel. The spent fuel storage pool presently contains 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available capacity of the fuel pool is 1,639 locations.

Unit 2 Unit 2 was shut down for its fifth refueling outage on September 15, 1984, t

with a scheduled restart date of October 8, 1986. This refueling outage will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-i startup unit 2 items are CRD SDIY piping modification (IEB-80-17), environmental qualification of electrical equipment (10 CFR 50.49), torus modifications (NUR2G-0661), containment modification (NUREG-0737), electrical changes' j

(Appendix R 10 CFR 50) (partial), NSIV modifications, modification of masonry walls (IEB-80-11), addition of feedwater nozzle temperature monitoring i

(NUREG-0619), evaluation of vent drains (LER-82020), valve modification (Appendix J) (partial), D/G speed sensor installation (LER-81-004) HPCI and 0058B F

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4 Refueling Information i

NARCH 1986 Unit 2 (Continued)

RCIC testable check valve change out, modification of PCIS logic (LER 259-85009), HPCI concerns, seismic program review, and EECW carbon to stainless pipe change out.

There are 0 assemblies in the reactor vessel. At month end there were 305 new assemblies, 764 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 162 locations. All old racks have been removed from the pool and new HDRs are being installed.

Unit 3 Unit 3 started its environmental qualification outage to comply with NRC requirements December 1, 1985, with a scheduled restart date of March 1987. The unit was shut down on March 9, 1985, and remained in cold shutdown until December 1, 1985, on administrative hold to resolve various TVA and NRC concerns. The sixth refueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-startup unit 3 items are environmental qualifica-

)

tion of electrical equipment (10 CFR 50.49), containment modifications (NUREG-0737), electrical changes (Appendix R 10 CFR 50) (all) MSIV modifica-tions, modification of masonry walls (IEB-80-11), evaluation of vent drains (LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG-0737), addition of redundant drywell control air supply, evaluation of vent drains (LER 82020), RPS modification (IE Notice 78-45),

H0 8 ample line modification (LER 81-050), radiation monitor modification 22 (LER 80033), replacement of jet pump holddown been assemblies (IEB-80-07),

change out of switches in SBGT (LER-83-018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.

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

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5 SIGNIFICANT OPERATIONAL EVENTS MARCH 1986 Unit 1 03/01/86 0001 End of cycle 6 refuel and modifications outage continues i

03/31/86 2400 End of cycle 6 refuel and modifications outage continues 0006B

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6 SIGNIFICANT OPERATIONAL EVENTS MARCH 1986 Unit 2 03/01/86 0001 End of cycle 5 refuel and modifications outage continues 03/J'/16 2400 End of cycle 5 refuel and modifications outage continues O

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7 SIGNIFICANT OPERATIONAL EVENTS MARCH 1986 Unit 3 03/01/86 0001 Unit began environmental qualification and modification outage to comply with NRC requirements.

03/31/86 2400 Environmental qualification and modifications outage to comply with NRC requirements continues.

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT One DATE 4/1/86 COMPLETED BY

_T.

Thom TELEPHONE 205/729-2501 MONTH hrch DAY AVER AGE DAILY POWER LEVEL D4Y IMhe-Neil AVER AGE D AILY POWER LEVEL

~

g yw,3,,3 1

57

-2 2

-2 18

-2 3

-2 3,

-2 4

-2 20

-2 5

-2 2g

-2 6

-2 22

~2 7

-2 23

-2 3

-2 24 9

~2

-2

-2

~2 25 10 26

-2 11

-2 27

-2 I2 13

-2 2g 3,

-2 14

-2 30

-2

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15

-2 3,

16

-2 s

INSTRUCTIONS j

On thaJormat.hst the averJde daily ut.it pi wcr lewiin MWe Net for each day in the the ne4 rest whole megswati, m.mth. Compute to i

e (9/77)

- - - _ - = _ _.

9 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT h DATE 'A/1/R6 COMPLETED BY T. Thoin TELEPHONE 205/729-2509 MONTH March DAY AVERAGE DAILY POWER LEVEL DAY iMhe Net)

AVER AGE D4tLY POWER LEVEL Q MWe Net)

I

-8 37

-8 2

-8

_7 3

-8 19

-8 4

-8

-8 5

-7 21

-8

-8 6

22

-8 "O

7

-y y

s

-8 24

-7

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25

-8

-8 10 26

-8 II 12

-8

-8 27 23

-8 13

-8 0

29

-8 14

-8 30

-7 is

-8 31 16

-8

-7 INS TRUCTIONS On If..< format,hst the averee daily urnt Powcr leselin MWe. Net fut each day in th the neuest whole nwgawati,

. ompute to i

(9/77I i

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-s m =

m m m-W w__

,..w

10

.WER AGE DAILY UNIT POWER LEVEL DOCXET NO. 50-296 UNIT Three DATE 'a /1/R6 COMPLETED BY

_T.

Thom TELEPHONE 205/729-2509 Af0NTil March DAY

.tVER AGE D. ALLY P()WER LEVEL DAY AVER ACE D41LY POWER LEVEL iMWe Net)

-4 7

-5 2

-3 18

-4 3

-4 4

-4

_4

o

-4 5

-4 21

-4 6

-a yy

_4

-5 23

-5 8

y

-4 9

-4 25

-5

-5 10 11

-0

-4 26 27

-4 l

32

-5 13

-5

-5 28 14

~4

-4 29 30

-4 15

-5 l6

~5

-5 3:

INS TRtJCTIONS the nearest whole nwgawaii.On thaforrnat,hst the neraje daily unit po.wr levelin MW l

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11 OPERATING DATA REPORT DOCKET NO. 50-259 DATE. 4-1-86 COMPLETED BY T.

Thnm TELEPHONE 205/729-2509 OPERATING STATUS t

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1. Unit Name: Browns Ferry One N'

March 1986

2. Reporting Period:

i

3. Licensed Thermal Power (MWt): 3293 i

1152

4. Nameplate Rating (Gross MWe):

1065 i

5. Design Electrical Rating (Net MWel:

6. Maximum Dependable Capacity (Gross MWe):

1098.4 1065

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Fower Level To Which Restricted,if Any (Net MWe):

N/A

10. Reawns For Restrictions,If Any: N/A 4

I This Month Yr.-to Date Cumulative 744 2,160 102,320 i1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 0

0 59,521.38

13. Reactor Reserve Shutdown Hours 0

0 6,997.44

14. Hours Generator On-Line 0

0 58,267.26

15. Unit Resene Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

168,066,787 17 Gross Electrical Energy Generated (MWH) 0 0

55,398,130

18. Net Electrial Energy Generated (MWH)

-1,545

-9,617 53,747,392

19. Unit Senice Factor.

0 0

56.9

20. Unit Asailability Factor 0

0 56.9 0

0 49.3

21. Unit Capacity Factor (Using MDC Net)

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

49.3

23. Unit Forced Outage Rate 0

0 23.6

24. Shutdowns Scheduled Over Next 6 Months (Type Date,and Duration of Each):

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

9/14/86

26. Units In Test Status IPrior to Commercial Operatio.0:

Forecast Achieved INITIAL CRITICALITY INITIA L ELECTRICITY CONIMERCIAL OPER ATION N/77) 1

12 OPERATLNG DATA REPORT i

DOCKET NO. 50-260 DATE a/1/R6 COMPLETED BY T.

Thom TELEPHONE 205/729-2509 OPERATING STATUS

1. Unit Name:

Bren.m e Ferry Tv.rn March 1986

2. Reporting Period:

1

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):

1152 1065

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

1098.4 1065

7. Maximum Dependable Capacity (Net MWe):

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,If Anv Net MWe):

N/A

10. Reasons For' Restrictions.If Any:

NA I

I This Month Yr.-to.Date Cumulative i

744 2160 97,207 i1. Hours In Reporting Penod

12. Number Of Hours Reactor Was Critical 0

0 55,860.03

13. Reactor Reserve Shutdown Hours 0

0 14,200.44 i

14 Hours Generator On-Line 0

0 54,338.36 I

l

15. Unit Reserve Shutdown Hours 0

0 0

16. Gmss Thermal Energy Generated (MWH) 0 0

153,245,167

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17. Gross Electrical Energy Generated (MWH) 0 0

50,771,798

18. Net Electrical Energy Generated (MWH)

-5,677

-14.263 49,251,101 r

19. Unit Sersice Factor 0

0 55.9

(

0 0

55.9

{

20. Unit Availability Factor

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

47.6 0

0 47.6

22. Unit Capacity Factor (Using DER Net) f

23. Unit Forced Outage Rate 0

0 23.0

24. Shutdowns Scheduled Over Ne<t 6 Months (Type Date,and Duration of Each1:

25. If Shur Down At End Of Repcrt Period, Estimated Date of Startup:

Fall, 1986 j

26. Units in Test Status IPrior to Commercial Operation):

Forecast Achieved INITIA L CRITICALITY f

I INITI A L ELECTRICITY COMMERCIAL OPERATION (9/77) t

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i OPERATING DATA REPORT i

DOCKET NO.

50-296 DATE 4/1/86 COMPLETED BY L T.h.am.

1 TELEPHONE 205/729-2509 OPERATING STATUS i

Notes i

1. Unit Name:

Browns Ferry Three March 1986

2. Reporting Period:

3293

3. Licensed Thermal Power (MWt):

1152 I

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): - 1065 1098.4

6. Maximum Dependable Capacity (Gross MWe):

1065

7. Maximum Dependable Capacity (Net MWe):

j

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

N/A

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9. Power LeselTo which Restricted.lf Any t MWe):

N/A

10. Reawns For Restrictions. If Any:

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f This Month Yr.-to.Date Cumulative 744 2160 79,632 j

i1. Hours in Reporting Period l

12. Number Of Hours Reactor Was Critical 1

0 45,306.08

13. Reactor Reserve ShuMown Hours 0

0 5.149.55

14. Hours Generator On.Line 0

0 44,194.76

15. Unit Reserve Shutdown flours 0

0 0

[

16. Gross Thermal Energy Generated (MWH) 0 0

131.868.267 l

0 0

43,473,760 l

17. Gross Electrical Energy Generated (MWH) j

18. Net Electrical Energy Generated (MWH)

-3,267

-9,554 42,124,219 l

19. Unit Service Factor 0

0 55.5 i

20. Unit Availability Factor 0

0 55.5 i

0 0

49.7

21. Unit Capacity Fact <.r (Using MDC Net) 0 0

49.7 l

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

26.4

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type.Date,and Duration of Each):

i l

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

March 1987

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved l

r INITIA L CRITICALITY INITIAL ELFCTRICITY i

COMMERCIAL OPERATION l

r (9/77)

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I UNIT SilUTDOWNS AND POWER MEDUCTIONS DOCKET NO. 50-259 UNIT NAME Brownn Ferry O te t

DATE 4/1/86 REPORT MONTif March COMPLETED BY T-Thn=

TELEPHONE 205/729-2509 n.

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3 j $5 Licensee jg Cause & Corrective g

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Date g

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E3 Action to

$5 E

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Report a wU 5'

Prevent Recurrence o

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i 315 3/1/86 S

744 C

2 End of cycle 6 refuel outage continues.

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'l' I: Forced Reason:

Method:

Exlubit G - Inst ructions l

2 3

4 S: Scheduled A. Equipment Failure (Explain) 1 -Man ual for Preparation of Data l

B. Maintenance ci Test 2-Man ual Scram.

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

Event Report (l.I'RI File iNURI G.

g D Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & thense Examination F Administrative 5

G-Operational i tror 11 = plain)

E xlubii I - Same Source

(' A/77 )

Il-Ot her ( Explain i f

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I UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAME Rr ni.m q Ferry Two DATE 4/1/R6 COMPLETED BY T-Thn=

REPORT MONTH March TELEPHONE 205/729-2509 1'

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Cause & Corredive k-N' '.

DJte j ,{ ] y [ygng g; y j'E Action to $3 5 j5g Report a n0 Prevent Recurrence 6 l !t l 305 3/1/86 S 744 C 4 EOC-5 refuel outage. [: j (Controlled shutdown 9/15/84) l l-i t7, t l i l i 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data i B-Maintenance of Test 2-Manual Scram. Entry Sheets fo 1.icensee C Refueling 3 Automatic Scram. Esent Repoit II.1:R) File INtIRI Cr D-Regulatory Restriction 4-Other ( Explain) 0161) E-Operator Training & thense Examination F Administrative 5 G-Operational Error (Explain) Eshibit I - Same S unce 19/77) Il Other IExplain) f

.I l i DOCKET NO. 50-296 UNIT SHUTDOWNS AND POWER REDUCTIONS UNITNAME Browns Ferry Three i DATE 4/1/86 REPORT MONTH March COMPLETED BY T. Thom TELEPHONE 205/729-2509 i _E E .$ g 3 j YE Licensee j-r, {% Cause & Corrective No. Date i 3g 4 ,a j 5 Event 3,? 9 'E Action to j's s jgg Report a mV H j' Preveni Recurrence j 6 ~ 157 3/1/86 S 744 H Environmental qualification outage to comply with NRC requirements. I I I I i i w i l t + 4 l i i i i 'i i 2 3 4 F: Forced Reason: Method. Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) l Manual for Preparation of Data B. Maintenance er Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Repori ILE R) File iNURI G-i D-Regulatory Restriction 4-Olher ( Explain) 016i) E-Operatur Training & l.icense l.xamination F-Administrative 5 i G-Operational Firor ( Explam) Estubit I - Same Source 19/77) li-Other (E xplain) i e i ( ' f e ~.

o t iic:.5 EtiOWilS FERitY NUCLEAR PLANT Uhl1 0 BF E-.UIL 30 9/ppendix B A 29/82 CSSC Ecuitment ELECTRICAL MAINTENANCE

SUMMARY

For the Month of March 1983 L Effect on Safe Action Taken t Nature of Operation Cause of Results of to Preclude Date System _ Component Maintenance of Reacto-Malfunction Malfunction Recurrence t986 s 2/23 Air Condi-A spreader rm Motor arcing None Starter windiag Lost exhaust in Replaced motor

tioning, exhaust fan A bad spreader room i

cooling & l heating. j FA-031-91 r 1 ! 2/27 Standby gas Blower B disch Alarm on B-SBGT None Buread out coil Alarm in U-l control Replaced coil as l treatment flow low Ann control room on alarm circuit instructed i FA-065-42 HS-65-40A i U f l t I 4 1 i 4 t-

P:ce.3 I BF EMSIL 30 BROWNS FERRY NUCLEAR PLANT UNIT A endix B CSSC Eouitxnent ELECTRICAL MAINTENANCE

SUMMARY

9 9/82 f For the Month of March 86 19 Effect on l Safe Action Taken Nature of Operation Cause of Results of to Preclude Date System Component Maintenance of Reacto Malfunction Malfunctine Facurrente I 1986 ' 3/2 RB heating Panel 9-42 Troubleshoot None N/A Refuel zone isolation MR 723601 - To IM - & ventila-aux instr rm No elec problem tion RLY-64 refuel zone 5 I i h.g f l I ~ l

a-Par.c 3 I i EROWNS FERRY NUCLEAR PLANT UNIT 3 LF EMS 1L 30 /ppendix B CSSC Eauinment ELECTRICAL HAlNTENANCE

SUMMARY

9/29/82 i i M TC 86 For the Month of 19 i Effect on Safe Action Taken i Nature of Operation Cause of Results of to Preclude i Date System Component Maintenance of Reacto Malfunction Malfuncrinn _E2Curtcuce {1986 . ; 3/1 Standby 3B diesel Adjusted lower None Unknown Diesel generator ' Adjusted lower MOP I diessl generator MOP limit speed - tolerance speed is limit step 3.15 u. i generator lower MOP out of tolerance 855-870 RPM; would on SI 4.9.A.l.d - go ( 880 RPM. Attachment C not used. ' j 3CEN 82-3B limit not e i l O i i i I t I l 1 1

.., e,,,.m..n. NUCLCAR PLANT 0; ERATING S rAPSrics e Browns Ferry Nuclear i.a"t

• Revision 20 reb ru ar y t(6,

62 Month .c. -., 7 5 l i j93,4 Unit No. Unh-1 Unit-2 Unit-3 Pin-t i I .c 0 0 0 0 e.s..:- 6,cu tv Gross t. oat kw 0 0 0 0 our Net Geraration. Mw% ? v.w m m w Ce ! TN rmal Energy Gen. GWD (t)2 0 0 0 0 p !!can Gen Teerrnal Energy Gen., GWO (t) s Grcss ricetricat Gen., MWh 0 0 0 0 ] e stauon Use, Mwh

• 3.501
• 4,302
• 3,05.1__

.*10.814. j 7 Net Clectreal Gen., MWh

• -3.501
• 4.302
• 21 : 05 L__..J :-la,854 -. -. _ _. _ -,'

i s:ne Use, Perrent 0 0 0 0 1 0 0 0 0 _j Accur,. Cera Avg. Exposure MWD / Ton CTEG Ttus f.ionth,10 GTU 0 0 0 0 l 0 6!1Tt i L_: i.. A_0_ T_L G T r is ?.*09t h, I C 5 . i I .3 H.;rs reactor Was Critical 0 0 0 0 I U.t Usc. Heurs. Min. O O O O f_______. j Qw *v F;ctor, Percent O O O O S -a o r3 f t. Facter. P,*rcent 0 0 _,1QO ___,l '3.. l I '7 l [;_an ;;6r A.a I. Faq1pr. Percent n _J ._109 1 1. 7. _ _ __ ~'

Lt.

._Mm. Av a>I. Factor. Percent O O 100 j].) n 0 10(L M l_____ i 2,_tg Ava A Facter. P,;rcent o .'! 2 ijytAa.I F*ctet Percent O O __Q __O ._.i i O O O O !. *; f r r tme St:rtuos ,2? ' f_ezier Cold St3rtuns n n 0 _6 1 N G< ss Heat Rate. Otu/kWh n O O l 0 r ' ct Hcat Rate Otu/kWn 0 0 0 0 l 2 26 l i ^7 ?3 ihrctt e Pretsure, psig 0 0 0 0 E Tr enttte Temocr3ture. *F n 0 0 0 T - _M_ f a

• 3u<t Pressure, InHg Abs.

0 0 0 0 ._i i f ji Nake Water Temp.. *F 0 0 0 0 _ _ Jl

?

a 33 f.*3in Icedwater, f.11b/hr O O O l O l

( _ '_,,[

i l l. _ _.. u i 3 )7 A.:I Pcwe-C.'pacity, EFPD (3) (4) (5) (O I t 33 Accum. Cvcle Full Power Day?, EFPD (1) (4) (5) (6) ___8 79 O I fired for Cencration. Gallons 1

• 3 '* 3 23 n t He.1 tin 1 Vate. Otu! Gal.

t__1MI 511_, -__ l 54.6 il rhe! GemratMn. MWh ~J j ..%. H:ur Net Gen. Max. Day Net Gen. Load i ".'n-Tirne Date f.twh Dato Factor. % j l 43 o n o _/ ,,,.l ~ . l.. crks-1 For.2FNP this value is MWD /STU and for SGNP and WGNP this value is MWD /?,1TU. __,, _ l -i ht) ircicates Therma! Energy. l i ' I~ ( it int'cr: ition furnished by Reactor.\\nalysis Group - Chattanoo:a j3,1 13r! cf cycle 6 Refuel Outnge 1 3._ n.' of Cycle 5 Ret' vel Distace -t t i il +ci r .m atal oniiiiication Catage l r,' ) / .O.- tie '! Date McVisCd LbY .;.,,(~p. 4 MN 4 etant.,upa entenJa.d -. C'., %5m :.. w_.. 6 Awa sgm y an...,,, pg fr, ..,, ;,, g,,.,, .-,- -< p -1 ~' e M 7,

v TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 APR t 31986 Decatur, Alabama 35602 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, D.C. 20555 Gentlemen: Enclosed is the March 1986 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2 and 3. Very truly yours. TENNESSEE VALLEY AUTHORITY Robert L. Lewis Plant Manager Enclosure ec: 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, Georgia 30303 (1 copy) Atlanta, Georgia 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D.C. 20555 (10 copies) Mr. A. Rubio, Director Electric Pokar Research Institute P. O. Box 10412 Palo Alto, California 94304 / I i 1 An Equal Opportunity Employer}}