ML20207C710

Monthly Operating Repts for Apr 1986

ML20207C710
Person / Time
Site:	Browns Ferry
Issue date:	04/30/1986
From:	Robert Lewis, Tanya Smith, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
0006B, 0058B, 58B, 6B, NUDOCS 8607210422
Download: ML20207C710 (76)

Text

-

TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY. NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC APRIL 1, 1986 - APRIL 30, 1986 DOCKET NUMBERS 50-259, 50-260 AND 50-296 LICENSE NUMBERS DEP.-33, DPR-52, AND DPR-68 Submitted by:

Plant Mana6er' 8607210422 860430 DR ADOCK 05000259 PDR I

CONTENTS Operations Sununary.

i Refueling Information..

3 Significant Operational Events....

5

~

Average Daily Unit Power Level....

8 C.arating Data Reports.

11 Unit Shutdowns and Power Reductions..

14 e

e 0

0058B

1 Operations Summary APRIL 1986 The following saunary describes the significant operation activities during the reporting period. In support of this sununary, a chronological log of significant events is included in this report.

There was one reportable occurrence and no revisions to previous occurrences reported to NRC during the month of April.

Unit 1 The unit remained on administrative hold the entire month. The unit is also undergoing its end-of-cycle 6 refueling.

Unit 2 The unit remained on administrative hold the entire month. The unit is also undergoing its end-of-cycle 5 refueling.

Unit 3

~

The unit remained in administrative hold the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.

l 4

1 This was prepared principally by T. R. Smith.

00583

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

2 Operations Summary (Continued)

APRIL 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.

1 Common System Approximately 9.69E+05 gallons of waste liquids were discharged containing approximately 3.62E-02 curies of activities l

0 0058B

- ~ ~ ~

3 Refueling Information APRIL 1986 Unit 1 Unit I was placed on administrative hold in March 1985.to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date of March 1989. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 1

~l 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 the vent drain and test

'l connections, VDTC, (LER-82020), valve modification (Appendix J), HPCI concerns, modification of PCIS logic (LER 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 sample 22 line modification (LER 81-050), radiation monitors modification (LER 80033),

EECW carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which is scheduled for next outage.

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 on September 15, 1984, for its.fifth refueling outage with a scheduled restart date of December 1986. On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns. The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.

)

The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB-80-17), -

environmental qualification of electrical equipment (10 CFR 50.49), torus modifications (NUREG-0661), containment modification (NUREG-0737), electrical 3

l changes (Appendix R 10 CFR 50) (partial), NSIV modifications, modification of

}

masonry walls (IEB-80-11), addition of feedwater nozzle temperature monitoring (NUREG-0619), evaluation of the vent drain and test connections, VDTC, a

l (LER-82020), valve modification (Appendix J) (partial), D/G speed sensor l

l 0058B l

=-

4 Refueling Information APRIL 1986 Unit 2 (Continued) installation (LER-81-004), HPCI and 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, 35'2 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel st'orage 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 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date of March 1987. The sixth refueling outage has been scheduled for September 21, 1988, and involves lo& ding 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-startup unit 3 items are environrental qualifica-tion of electrical equipment (10 CFR 50.49), containment modifications (NUREG-0737), electrical changes (Appendix R 10 CFR 50) (all), NSIV modifica-tions, modification of masonry walls (IE8-80-11), evaluation of the vent drain and test connections, VDTC, (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, RPS modification (IE Notice 78-45),

H0 sample line modification (LER 81-050), radiation monitor modification 22 (LER 80033), replacement of jet pump holddown beam assemblier (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.

00588

5 l

Significant Operational Events APRIL 1986 Unit 1 04/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues 04/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues t

l 0058B e-.w..e,me,

.= -

6 Significant Operational Events APRIL 1986 Unit 2 l

04/01/86 0001 Unit remains on administrative hold to rerolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues i

04/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modificatione continues 1

e t

i e

00588

7 Significant Operational Events APRIL 1986 Unit 3 04/01/86 0001 Unit began environmental qualification and mooification outage to comply with NRC requirements.

04/30/86 2400 Environmental qualification and modifications outage to comply.with NRC requirements continue,s.

'I

.i i

00588 t

-...-.-w..

e AVER ACE $)AILY UNIT POWER LEVEL 50-259 DOCKET NO.

UNIT __.

DATE -

5-1-86 COMPLETED 3Y T.

Thom TELEPHONE 205/729-2501 it0NTd Anr41

~

DAY AVERAGE DAILY POWER LEVEL DW AVER ACE D AILY POWER LEVEL 151% c-NetI (S!We N:t) -

3

-2 g7 2

-2 g3

-2

-2

-2

}

3 3,

4

-2

-2

,o 5

-2

-1 y,

o

-2 22

-3

-2 33

-3

-2

-2 3

24

-2

-2 9

25

-2

-2

.J 26 11

-2

-2 37

-2 23

~

13

-2

-2 29 l4

-2

-2 30 15

-2 3,

p,

-2 INSTRt CTIONS Un theformat. list the asera:;e duh u:,. p...ssi lege!!n uwe. Net for rath day in Ilie sq.osting month. Cornpute to

!!:e f.?Jff',8 whole gneputt, e

19/77) 5%b

~.

9 AVER \\GE DAILY UNIT POWER LEVEL DOCKETNO. _50-260 L?ilT

-WO DATE '5-1-86 COMPLETED BY T.

Them TELEPHONE 205/729-2509'

..:GNnt Anril CAY AVERAGE D Ally power LEVEL i2A IM N Neti A\\,Ett AGE D AILY POWER LEVJ' L

-8 IMWe,%:).

_7 2

-8 i3

-7

~

3

-7_

_7

-8 a

-7 o

S

-8

~

_y e

~7 22

-8

-7 i

23

-8

'l

-6. -

_8

~

-5 25 10

-8 26

_-8_

l1

-7

-7

~

-8

~7

-8 23

^r--

g3 29

_y

!4

- - - 3a

-8

.i

-7 is

-8

-=.

1.'.S IR t:Cno.N:s On tLej.nmu.In et.e 45..,2 :e Jaih io,i p,. ace taet in uwe Net for rach da) in ihe seputi:nE inonti th: re4 ras who e n.eg.twaii,

e. L.,tnpu te t <.: -

8 (9/77)

m 10 AVER \\GE DAILY UNIT POhER LEVEL DOCKET NO. _50-296 i

UNIT Three l

DATE 5-1-P6 1

i C0MPLETED Sy T. Thom l

TELEPHONE 205/729-2509 l

l l

MONng April CAY AVERAGE DAILY POWER LEVEL rM.

AVEll AGE DAILY POWER Lty t IMwe. Net 3 j

1

-7 BfWe Net) 17

-5 '

2

-8

-5 13 3

-5

-4 go 4

-5

-4 20

-5

-i

-4 23

-4 5

-4 24

-4

-5 9

-5 25

-5

-5 10

,.6 11

-4

-5 27

-5

-4 23 13

-5 g

-5 29

-5 14

-5 30 li

-5 31 Ic

-5 i

INSTRL'CTIONS h[*l.

""" P""*' lori in \\lWe.Nel fut cah day in the seporen,g ni,.nti.. Comput: tu tl ? r J: >I f

11 4

OPERATING DATA REPORT DOCKET NO. 50-259 DATE 5-1-86 COMPLETED BY T. Smith TELEPHONE 9ns /99a=7955 OPERATING STATUS

1. Unit Name:

Browns Ferry One Not*5

2. Reporting Period:

April 1986

3. Licensed Thermal Power (M%t):

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 J

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 Any Net MWe):

N/A

10. Reasons For Restrictions,1f Any:

A 1

This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 719 2,878 103,039

12. Number Of Hours Reactor Was Critical 0

0 59,521.38

13. Reactor Reserve Shutdown Hours 0

0 6,997.44 14.14urs Generator On.Line 0

0 58,267.26

15. Unit Reserve Shutdown flours 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 Electrical Energy Generated (MWH)

-1.559

-11.176 53,745,833

19. Unit Service Factor 0

0 56 5

20. Unit Availability Factor 0

0 56 5 0

0

21. Unit Capacity Factor (Using MDC Net) 49.o

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

49.0

23. Unit Forced Outage Rate 100 100 30.9

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

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

March 1989

26. Units in Test Status iPrior to Commercial Operation);

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION N/77) u____._._____r.-an_em-m.__,-

mA

12 OPERATING DATA REPORT 50-260 DOCKET NO.

DATE 3/1/66 COMPLETED BY T. Smith TELEPHONE 205/729-2955 OPERATING STATUS Notes

1. Unit Name:

Browns Ferry Two

2. Reporting Period:

April 1986 3293

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

1098.4

6. Maximum Dependable Capacity (Gross MWe):

1065

7. Maximum Dependable Capacity (Net MWe).

s

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

?

N/A t

i N/A

9. Power Level To Which Restricted.If Any (Net MWe):

j

10. Reasons For Restrictions,If Any:

N/A j

This Month Yr..to Date Cumulative

11. Hours in Reporting Period 719 2.879 97.926

12. Number Of Hours 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 Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

153,245,167 0

0 50,771,798

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

-5,447

-19,710 49,245,654

19. Unit Service Factor 0

0 55 5

20. Unit Availability Factor 0

0 55.5 0

0 47 2

21. Unit Capacity Factor (Using MDC Net)

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

47,2

23. Unit Forced Outage Rate 100 100 18.79

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

25. If Shut Down At End Of Report Period. Estimated Date of Startup: - - -December 1986

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)

13 o

OPERATING DATA REPORT DOCKET NO. 50-296 DATE 5-1-M COMPLETED BY T-c-4eh TELEPHONE 20s/729-2955 OPERATING STATUS

1. Unit Name:

B ren.m a Ferry Three

. otes

2. Reporting Period:

April 1986

~

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

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 (Net MWe):

N/A

9. Power Level To Which Restricted,If Any/A

10. Reasons For Restrictions. If Any:

N This Month Yr..to.Date Cumulatise

11. Hours in Reporting Period 719

_2,879 80,351

12. Number Of Hours Reactor Was Critical 0

0 45,306.08

13. Reactor Reserve Shutdown Hours 0

0 5,149.55

14. Hours Generator On.Line 0

0 44,194.76

15. Unit Reserve Shutdown Hours 0

0

.0

16. Gross Thermal Energy Generated (MWH) 0 0

131,868,267

17. Gross Electrical Energy Generated (MWH) 0 0

43,473,760

18. Net Electrical Energy Generated (MWH)

-3,244

-12,798 42,120,975

19. Unit Service Factor 0

0

>>.0

20. Unit Availability Facto, 0

0

55. 0 0

0 49, 2

21. Unit Capacity Factor (Using MDC Net)

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

_49._2

23. Unit Forced Outage Rate 100 100 30.6

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:

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 Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77)

.I i

50-259 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

~

UNIT NAME One DATE 5-1-86 COMPLETED BY T. Thom REPORT MONUI April TELEPHONE 205/729-2509 llII e.

ht,

.! E Y

Licensee E

Cause & Corrective t,

l No.

DJie i

5?

.2 s &

Event

7 a.8 Action to l

$5 E

j;%g Report =

<d O Prevent Recurrence 6

i' 315 4-1-86 F

719 F

2 Administrative hold to resolve (Cont.:

various TVA and NRC concerns.

+

q

~

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain)

I Manual for Preparation of Data B-M4intenance of Test 2 Manual Scram.

Entry Sheets for Licensee C.Rcfueling 3-Auf omatic Scram.

Even: Repori It.I'RI File (Nt1RI G-D-Regulatory Restriction 4-Other (Explain )

0161)

E-Operator Training a bcense Examination F Administrative 5

CrO vrational brcs (Explain) f stubii I - Same Source l

08/77)

II 0:her (Fxplain) 9 9

b lt UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT N/ ME Two DATE 5-1-R6 COMPLETED BY T. Thom REPORT MON 111 Apri1 TELEPilONE 705/779-?SO4 e

e.

E E

i

}E

'h

$ $3 Licensee

,En,

$*?

Cause & Correceive L

No.

Ible i

3@

j js5 Even 3y g

Action to f

E jgg Report =

id V g'

Prevent Recurrence H

6

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305 4-1-86 F

719 F

4 Administrative hold to resolve various (Cont. )

TVA and NRC concerns.

i$

i i

I 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Prepar.ition of Data H Maintenance of Test 2 Manual Seram.

Entr> Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report 11 ER) File G NURI:G.

D Regulatory Restriction 4-Other ( Esplain) 01611 E-Operator Training & Litense Examination i

F-AJnunistrati.e 5

G-Operational Luor (l'.splaia)

Eshibit i. Same Siiurce tis /77)

Il Other (I:splain) l t

t j

UNIT SilU1 DOWNS AND FOWER REtJUC110NS DOCKET NO. 50-296

, UNITNAME Three DATE 5-1-R6 COMPLETED BY T.

Thnm IIEh)RT MONTil Ap.-11 TELEHtONE 205/729-2509 1

j3

'h E

Licensee

,E t, ho Cause & Corrective.

l No.

Date R

5?

4 255 Esent

?

El Action to j5 5

j 5, g Report *

<E L

['

Prevent Recurrence i

6 t

i 157 4-1-86 F

719 F

Administrative hold to resolve

+

(Cont.)

various'TVA and NRC concerns.

.I t

s p

cn t

L I

2 3

4 F: Forced Reason:

Method:

lixhibit G - Inst ructions S Scheduleil A Equipment Failure (I splain)

!-Manual for Preparati. n or Data R. Maintenance of Test 2-Manual 5erani.

I'nas) 5heets f or 1.kernce 0-Rehielir:g 1 Autinnatic Scram.

1:veni Repin 4 I l'lO l'ite a NIiltl&

l D-Reculatory llestrictii n l-Othes likplaisi) 0161i l~-Operator llJining sk Ilien'.e i UmiHJIhtHe F-Administrati e 5

G-Operati.m.11.rios tI splat.il lTinbit I - Same Somce 19!771 11 Other fliplaml l

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l 9

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's 4

R40 8 6 0 512 969 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT APRIL 1986 Submitted By:

Plant Manager

c b

MONTHLY OPERATING REPORT DISTRIBUTION LISTS MONTH BEING DISTRIB' TED:

APRIL J

TVA Report (39 copies)

Get RIMS number stamped on ORIGINAL before zeroring Addressee (1 copy unless indicated otherwise)

Betsy Elfo~;d-Lee, Rad Health,'LP SS SIE-C C.C. Mason, MR 6N 45B-C H.S. Kidd, Nuclese Safety Review Staff, E 38 29 C-K B.J. Spence, Supv., Records / Manual Control Unit, LP 4S 1250-C John Adams Performance & Analysis Section, LP 4N 53A-C G.W. Killian, Quality Audit Branch, LP 4N 53A-C

~

Director, Div of Engrg Projects Nuclear, W11A8 C-K J.H. Miller, Chief, Mechanical Branch, LP SS 150D-C E.A. Belvin, Chief, Radiological Health Staff, LP SS 62E-C R.J. Johnson, Chief, Nuclear Training Branch, POTC W.E. Andrews, Manager, Operations Quality Assurance Branch, LP 4N SOA-C Chief, Nuclear Engineering Branch. W10C128 C-K F.A. Szczepanski, Chief. Nuclear Safety Staff, BR IN 76B-C J.R. Ratliff, Chief, Nuclear Fuel Branch, BR 6N 32A-C Plant Operations Section, 140 CST 2-C Don Evitts, Operations Analysis Section, 1200 CUBB-C J.A. Mcdonald, Chief, Quality Improvement Staff, 345 SPB-K M.E. Rivers, Director, Environmental Quality (2 ea) 201 SPB-K RIMS, MR 4N 72A-C J.E. Jones, General Electric Company Suite 105, P. O. Box 105064, Atlanta, GA 30348 Steve Sawochka, Nuclear Water & Waste Technology 7015 Realm Drive, San Jose, CA 95119 Dr. Johan Blok, Radiological & Chemical Technology, Inc.

1604 Kerley Drive, San Jose, CA 95112 Engineering Section Files Janice Retherford, Planning & Scheduling W.C. Bibb, Site Director E.P. Schlinger, Engineering & Modification, Design Bldg.

J.H. Rinne, Design Bldg S. H. Rudge, Assistant to the Site Director Admin Bldg.

DRB JRC DSH JDS TRS JDW BEW (2 ea)

Plant Manager Routing Phil Ray, GE PWS (2 copies-1 working, 1 extra)

s

~

TABLE OF CONTENTS PART I Operations Summary Plant Operations.

1 Refueling Information..

6 Change in Procedures.

9 Change in Facility Detign.

9 Surveillance Testing.

14 Containment Leak Rate Tests..

15 Changes, Tests, and Experiments Requiring Authorization from the NRC Pursuant to 10.CFR 50.59 (a) 15 Changes in Plant Organization..

16 Changes, Tests, and Experiments Not Requiring Authorization from the NRC Pursuant to 10 CFR 50.59 (a) 16 Primary Coolant Chemistry.

17 Source Tests.

18 Environmental Technical Specification Requirements.

18 Calculation of Usage Factor..

18 Accidents..

20 Significant Operational Events.

21 Plant Instruction Revisions.

24 Reportable Occurrences.

25 Primary Coolant Chemistry..

28 Liquid Radwaste Monthly Operating Report.

30 Reactor Power Percent.

31 0006B

.. ~ -... = -

e TABLE OF CONTENTS (Continued)

Nuclear Plant Operating Statistics.

34 Unit Outage and Availability.

.'. S Electrical Maintenance Sununary.

38 Mechanical Maintenance Summary.

40 Radioactive Liquid Effluents.....

42 Airborne Releases.

46 Solid Radioactive Waste.

48 Resin Usage Report.

51 Fuel Cladding Integrity Parameters.

52 Waste Treatment System Volume Throughputs.

53 0

t l

l 0006B

....z- =----.

i 1

1 OPERATIONS

SUMMARY

APRIL 1986 Unit 1 The unit remained in administrative hold the entire month. The unit is also undergoing its end-of-cycle 6 refueling.

Unit 2 The unit remained in administrative hold the entire month. The unit l's also undergoing its end-of-cycle 5 refueling.

Unit 3 The unit remained in administrative hold the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.

4 0006B

2 OPERATIONS

SUMMARY

(Continued)

APRIL 1986 Reliability and Availability The accumulated average daily gross (AADG) capacity factors, based upon midnight MWH meter readings for each unit are tabulated below for each month during the last calendar year. The second column compares this year's performance with last year's. -

_ Unit No. 1 Unit No. 2 Unit No. 3 1985 1986 1985 1986 1985 1986 l

January 64.2 0.0 0.0 0.0 94.8 0.0

• (31)

February 79.0 0.0 0.0 0.0 87.0 0.0 l

• (28)

March 69.7 0.0 0.0 0.0 66.4 0.0

• (31)

April 52.1 0.0 0.0 0.0 49.5 0.0

• (30)

Nay 42.1 0.0 39.2

• (31)

June 34.2 0.0 32.6

• (30)

July 29.1 0.0 27.7

• (30)

August 25.2 0.0 24.0

• (31)

September 22.4 0.0 21.3

• (2.5)

October 20.0 0.0 19.0 November 18.1 0.0 17.2 i

Decemberl 16.5 0.0 15.7

• Refuel Outage (Days) 1 Yearly Average The predicted AADG will not be addressed until power generation is commenced.

0006B i

e RELIABILITY AND AVAILABILITY i

CAPACITY FACTOR LOSSES t

APRIL 1986 UNIT 1 UNIT 2 UNIT 3 1985 MO '86

_1985 MO '86 1985 MO '86 l

CAPACITY FACTOR 16.5%

0.0 0.0 1 0.0 15.7%

0.0 i

i LOSSES WERE CAUSED BY:

4 1.

Refueling 67.3 i

2.

PCIOMR 0.3 0.2 3.

Performance degradation l

4.

Turbine control valve tests and sis 0.2 i

5.

TIP system operation 6.

Reactor feedpump problems / maintenance 0.2 7.

Automatic Scram 1.2 8.

Control rod pattern adjustment 9.

Feedwater heater problems / maintenance

10. Maximum flow (rod limit) 0.2

11. Computer out-of-service - hardware

12. End-of-cycle coastdown 0.6

13. Rod sequence control system problems / maintenance

14. Control rod problems / maintenance 0.1

15. Scram timing

16. Recirculation M/G set brush replacement

17. Condensate domineralizer problems / maintenance

18. Main steam valve problems / maintenance

19. Recirculation N/G / problems / maintenance 0.5

20. Recirculation pump / motor / problems / maintenance 0.5

21. Startup testing

22. River temperature limits i

23. Rod sequence exchange

24. Core limits (high axial peaking)

25. Feedwater valve problems / maintenance i

e

RELIABILITY AND AVAILABILITY CAPACITY FACTOR LOSSES APRIL 1986 UNIT 1 UNIT 2 UNIT 3 1985 NO '86 1985 NO '86 1985 NO '86 CAPACITY FACTOR 16.5%

0.0 0.0 0.0 15.7%

0.0 LOSSES WERE CAUSED BY:

v

26. Administrative Limitations 81.1 100 32.7 100 80.0 100

27. RWCU line repair 1.0

28. Control air leak in drywell

{

29. Main steam low-pressure quarter isolation

30. Condensate pump problems / maintenance

31. Deinerting and maintenance in drywell

32. HPCI valve problems / maintenance l

33. Main turbine / repair 1.6 i

34. Bus duct / repair p

35. RHR valve problems / maintenance (service water) 0.3

36. Lack of demand

37. Main turbine high vibration

38. Main condenser cleaning i

39. Offgas problems

]

40. Xenon transient i

41. Immovable control rod (10-39)

I

42. RHR heater repair

43. (CNFLPD) thermal limits

44. Main transformer repair

45. Main turbine repair

46. Drain header pipe repair

47. Derated to prevent overlap of U2 and U3 refuel 1

outages and ADS /HPCI cable separation design j

48. Derated to prevent outage overlap 1

l i

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RELIABILITY AND AVAILABILITY j

CAPACITY FACTOR LOSSES APRIL 1986 UNIT 1 UNIT 2 UNIT 3 1985 MO '86 1985 MO '86 1985 MO '86 CAPACITY FACTOR 16.5%

0.0 0.0 0.0 15.7%

0.0 LOSSES WERE CAUSED BY:

p

49. Environmental concerns

50. Steam Relief valve repair 0.5

51. Tip system problems / maintenance 0.3 l

52. Modifications, including environmental requirements to meet NURG 0588 h

53. IRM "D" purge repair 0.4

54. Level instrumentation problems / maintenance 2.6

55. Environmental concerns outage

+

56. Environmental qualification outage, NRC requirement, un 9

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6 OPERATIONS

SUMMARY

(Continued)

APRIL 1986 Refueling Information Unit 1 Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date of March 1989. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies'into the core. The prior-to-startup Jnit 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), MSIV modifications, modifica-tion of masonry walls (IEB-80-11), evaluation of the vent drain and test connections, VDTC, (LER-82020), valve modificatio,n (Appendix J), HPCI concerns, modification of PCIS logic (LER 259-85009), replacement of plant process computers, seismic qualifications of piping (IES 79-02/14), postaccident evaluation (NUREG-0737), RPS modifications (IE Notice 78-45), H 0 sample 22

~

line modification (LER 81-050), radiation monitors modification (LER 80033).

EECW carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which is seneduled for next outage.

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.

0006B

]

-. _ _. _ _ ~__

-. ~ -

7 OPERATIONS

SUMMARY

(Continued)

APRIL 1986 Refueling Information Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date of December 1986. On September 3, 1985, the unit

~~

was placed on administrative hold to res'oIve TVA and NRC safety concerns.

The fif th refueling involves loadin's 8x8R (retrofit) fuel assemblies into the core.

The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB-80-17),

environmental qualification of electrical equipment (10 CFR 50.49), torus modifications (NUREG-0661), containment modification (NUREG-0737), electrical changes (Appendix R 10 CFR 50) (partial), MSIV modifications, modification of masonry walls (IEB-80-11), addition of feedwater nozzle temperature monitoring (NUREG-0619), evaluation of the vent drain and test connections, VDTC, (LER-82020), valve modification (Appendix J) (partial), D/G speed sensor installation (LER-81-004) HPCI and 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.

00068

e 8

OPERATIONS

SUMMARY

(Continued)

APRIL 1986 Refueling Information Unit 3 Unit'3 was shut down on March 9, 1905, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date of March 1987.- The-~si~xth~ 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 the vent drain and test connections, VDTC,(LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (II:B 79-02/14), postaccident evaluation (NUREG-0737), addition of redundant drywell control air supply, RPS modification (IE Notice 78-45),

H0 sample line modification (LER 81-050), radiation monitor modification 22 (LER 80033), replacement of jet pump holddown beam 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 I

fuel storage pool. The present available capacity of the fuel pool is 914 locations.

00068

I 9

1 OPERATIONS

SUMMARY

(Continued)

I APRIL 1986 i

4 i

Chante in Procedure i

There were 193 revisions to plant instructions during the month; 190 1

instructions were changed primarily for correction, and the remaining 3 i

revisions related to safe operation of the plant.

l Chante in Facility Desian i

1 Packame Number Description i

Safety-Related Modifications ECN P3138 RHR System -

Replaced the Ri!R pump's 2A and 2C cooler fan Unit 2 -

motors.

Work Plan 2214-84 l

The ECN was not completed on this work plan.

l Work plan 2001-85 will change out the motors on pumps 2B and 2D.

Work plan 2030-86 will i

perform the postmodification test and complete the ECN for unit 2.

1

[

ECN P0753 HPCI/ ADS Installed cable separation tags to separate 1

Cable Separation -

the HPCI inboard isolation valve cables Unit 2 (ESS Div. I) from the ACS cables (ESS Div. I).

Work Plan 2162-85 No wire lifts or terminations'were made on l

this work plan.

i The ECN was not completed. Installation work plans and postmodification testing to be implemented during unit 2, cycle 5 outage.

q ECN P0646 Standby Diesel Installed isolation valve on each air Generator System -

supply line to air starting motors on diesel Units 1 and 2 generators A, B, C, and D for units 1 and 2.

i Work Plan 10387 The valves are locked open manual valves and I

did not degrade the seismic qualifications of the system. The function of the system was not changed; the margin of safety was not j

reduced. The ECN was completed for units 1 and 2.

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. ~.... _ _.. _ _ _ _.

__~

i 3

10 i

OPERATIONS SUNNARY (Continued) j APRIL 1986 i

Channe in Facility Desian

& ckste Number Description I

Safety-Related Modifications ECN P0381 Standby Replaced GENAC transmitter, LT-63-1 with Liquid Control -

Rosemount transmitter.

Unit 2 Work Plan 2032-85 A very small portion of the work covered.by this ECN was completed. The ECN replaces J

other transmitters on various systems.

ECN P0126 Reactor Protection Installed panels 9-81 and 9-82 for the reactor Emergency Core Cooling protection and emergency core cooling analog i

Systems - Unit 2 trip unit system.

Work Plan 2162-84 l

A very small portion of the work covered by l

the ECN was implemented by this work plan.

ECN P3134 Containment Replaced the mounting brackets for 2-FN-84-19B Atmospheric Dilution and 208.

(CAD) System - Unit 2 l

Work Plan 2004-84 Implementation of the modification assured seismic q'Jalification of FN-84-198 and 208.

The probability of occurrence or the consequences of an accident or malfunction of j

equipment important to safety previously l

evaluated was not increased.

ECW P0707 Reactor Replaced the 24V DC power supplies PK-99-A1, 4

Protection System -

PK-99-A1A, PK-99-A2, PK-99-A2A, PK-99-81, f

Unit 2 PK-99-81A, PX-99-B2, and PK-99-82A in the RPS Work Plan 2034-84 panels 9-83, 9-84, 9-85, and 9-86.

4 l

4 Replacement of the power supplies was to make i

a system improvement that would decrease j

maintenance or service problems. The j

modification provided an improvement of the

,j power supplies; therefore, the probability of i

occurrence or the consequences of an accident or malfunction of equipment important to i

safety was not increased. The ECN was j

completed for unit 2.

1 1

00065 4

_.e..,m,~.%....m...._,_.,.._.,____..____.__,,

11 OPERATIONS

SUMMARY

(Continued)

APRIL 1986 Change in Facility Design Package Number Description Safety-Related Modifications ECN P0354 Radiation Installed embedded conduits and ground cables Monitoring System -

for the off-gas stack monitor building Unit 2 locat1d northeast of the off-gas stack.

Work Plan 2067-85 A very small portion of the work covered by the ECN was completed.

ECN P0254 Area Radiation Pulled cables Cl385 through C1388. The cables Monitoring System -

were not terminated. No other work covered Unit 3 by the ECN or work plan was implemented.

Work Plan 7968 The work plan was revised to delete remaining work. A new work plan will be written to implement the ECN.

ECNs P0361, L2079 Removed zener diodes from valves FSV-76-49 CAM System - Unit 1 through FSV 76-68.

Installed seal-tight Work Plan 10348 connectors on FSV-76-53 through FSV-76-58 and FSV-76-63 through FSV-76-68.

A very small portion of the work covered by the ECNs was completed.

ECN P0275 Unit Station Installed relays, controls, and wiring for Service Transformer -

USST 18.

Unit 1 Work Plan 10087 A very small portion of the work covered by the ECN was implemented on this work plan.

ECN PS304 Diesel Generator Installed new seismically qualified hold-down Battery Racks - Units 1 and 2 studs for the diesel generator battery racks Work Plan 1224-85 for units 1 and 2.

i The modification allows the battery racks to i

be seismically qualified. No safety-related function or equipment was adversely affected. The ECN was* completed for units 1 and 2.

1 0006B

j i

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12 OPERATIONS SUNNARY (Continued)

APRIL 1986 i

Change in Facility Design Package Number Description Safety-Related Modifications ECN P0324 Radiation Provided conduits, grounds, junction boxes, Monitoring System -

tees, and cables for instrumentation for the Unit I containment monitoring system in unit 1.

Work Plan 10346 A very small portion of the work covered by l

the ECN was implemented on this work plan.

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i-

)

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13 1

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OPERATIONS SUNNARY (Continued) i i

APRIL 1986 l

l Channo in Facility Deslan i

Package Numbcr Description 1

t l

Non-Safety-Related Nodifications l

}

l I

ECN P5083 Associated Replaced existing XI-57-46 with 0-5NA asumeter

}

Electrical Equipment -

and wired in series with SI-47-16.

XI-57-46 t

Unit 3 indicates the turbine speed.

It was wired in

)

Work Plan 3011-84 parallel and did not function correctly.

This modification will allow II-57-46 to J

function properly.

)

The ECN was totally completed as it only l

covered unit 3.

i j

ECN PS234 Security System -

Removed existing field fabricated lock 1,2,3, and Comunon shields and installed tamper proof shields l

Work Plan 0055-85 (lockguards) over exposed door locking j

mechanisms on doors 223, 241, 254, 298, 471, I

472, 484, 485, 500, 510, 513, 538, 540, 630, j

634, 642, 648, 654, 657, 702, 721, and 827.

The doors will now provide the intended level of intrusion security. The ECN was totally completed.

i DCR 1318 Condensate Installed grating to allow access to #4 and #5 System - Unit 1 low pressure heaters. Also, extended the Work Plan 6350 grading to the condenser vacuum breakers.

The DCR was completed for unit 1.

ECN L1799 Control and Changed the power feeds for the unit 1 standby

{

I Service Air System -

and the unit's 2 and 3 dryers to panel 25-118.

}

l Units 1, 2, and 3 Changed the logic (electrically) for the

)

Work Plan 5569 FCV-32-90 on all dryer stations.

I i

Incorporated some wire and equipment i

modifications in the junction boxes locally i

mounted per the ECN.

I The ECN was totally completed.

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0006a 1

,____-_-..2 r --

_~_

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

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

14 l

1 OPERATIONS

SUMMARY

(Continued) i APRIL 1986 i

i Surveillance Testing i

i Unit 1 A total of 223 surveillance tests were completed on unit 1 per 83 different test instructions.

Unit 2 i

A total of 155 surveillance tests were completed on unit 2 per 45 i

different test instructions.

j Unit 3 i

A total of 281 surveillance tests were completed on unit 3 per 101 1

different test instructions.

i Prepared principally by P. K. Blakely.

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0006B

15 l

j OPERATIONS

SUMMARY

(Continued) i APRIL 1986 I

I Containment Leak Rate Test Primary containment penetration leak-rate tests were performed during the month. The results are within technical specification limits. The results are listed in the following table, j

Leakage (sefm)

Type Test Unit 1 Unit 2 Unit 3 Type A Integrated Containment No Test No Test No Test (1 per day)

Type B Personnel Air Lock No Test No Test No Test i

Equipment Hatches No Test No Test No Test l

Torus Hatches No Test.

No Test No Test Other Penetrations No Test No Test No Test Type C (Isolation Valves)

No Test No Test No Test Type B & Type C Totals No Test No Test No Test Changes. Test, and Experiments Requiring Authorization From the NCR Pursuant to 10 CFR 50.59(a)

There were three revisions for unit 1 technical specifications. These I

revisions included the following pages of Appendix A:

EPL 1 through EPL 22, 37/38, 39/40, 59/60, 51/52, 75/76, 256/257, 284/285, 314/315, and 324/325.

There was one revision for unit 2 technical specifications. This revision i

includes the following pages of Appendix A:

EPL-1 through EPL-22, 51/52, 75/76, and 285/286.

1 There was one revision for unit 3 technical specifications. This includes l

Appendix A: EPL-1 through EPL-24, 52/53, 78/79, 306/307 Prepared principally by T.R. Smith.

00068

16 OPERATIONS

SUMMARY

(Continued)

APRIL 1986 l

l Changes in Plant Organization There were no changes in the plant staff for those positions designated as key supervisory positions in the technical specifications reported for the month of April.

Changes. Tests, and Esperiments not Requiring Authorization from NRC Pursuant to 10 CFR 50.59(a)

ST 8605:

Demonstration of Radwaste Box Compactor Operability Purpose of the test was to demonstrate operability of Phelps Engineering radwaste bor compactor.

00068

17 OPERATIONS

SUMMARY

(Continued) 1 APRIL 1986 l

Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained within technical i

specification and fuel warranty limits during April. Chloride concentration

~

and pH of the reactor coolant remained within technical specification and fuel warranty limits during April. This calendar year, the technical specification and fuel warranty limits have not been exceeded.

Unit 2 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during April.

Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during Apell. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.

Unit 3 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during April.

Chloride concentration of the reactor coolant remained within technical specification and fuel j

warranty limits during April. This calendar year, the technical specification i

and fuel warranty limits have not been exceeded.

I 1

l 00068 i

- _. _ _ -. _., _ - _ _ _.- - _ _. _ _,,-.. __._._. _ _ _.. _.._._,. ~ _ _.,..__ _ _ _ _ ___ -. __ _ _ _ _. _ _ __,__ _,

18 l

OPERATIONS SUNMARY (Continued) l APRIL 1986 Source Test None.

Environmental Technical Specification Requirements There were no releases from the sedimentetion pond during the month. We are monitoring a small leak passing out around the effluent pipe into the biothermal stream. The pH of this discharge as well as the pH of the stream is being monitored. The stream pH has been consistently above 7.5 with no consequent problems. Final plans are being made for the repair of the dike.

The ambient river temperature (upstream) averaged 64.0'F with a maximum of 68.1*F occurring April 30.

A slightly higher maximum of 71.4*F was recorded downstream on Apell 27.

The maximum delta temperature was 3.3*F, occurring on April 28, while the monthly average delta temperature was 0.9'F.

No chlorination was done during the month.

Since the temperature has been above 60*F, surveillance of the river for larval clams (pediveligers) have been made. No larvae in the water column were observed.

The sewage lagoon appears to be recovering from the problems previously observed. We had one excursion of the total suspended particulates due to algae, but all BOD values were well within limits with the maximum being i

S 37.

The average flow (5,166 gallons per day) of the lagoon is depressed because of the dry conditions. The maximum flow of 8,712 gallons per day was observed on four days (April 1, 4, 8, and 21).

The pH of the lagoon is l

presently at near neutral levels (approximately 7.5).

Calculation of Usage Factor The cumulative usage factors for the reactor vessel are as follows:

T Usaae Factor Location 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 l

Closure stucs 0.24204 0.17629 0.14326 j

00068

19 OPERATIONS SUNNARY (Continued)

APRIL 1986 Common 5

The radwaste system performed as designed. Approximately 9.69E+05 gallons of waste liquid were discharged containing approximately 3.62E-02 curies of

}

activity, i

There were no trash shipments and only one condensate / waste resin shipment.

i The condensate / waste resin container shipped on March 27, 1986, was randomly selected by Chem-Nuclear (CNSI) for puncture and water content determination. Burial site criteria allows a maximum of one-percent fees standing water, by volume, for any High Integrity Container (HIC). This would equate to a maximum of 12.25 gallons for this particular HIC and the CNSI test produced 21 gallons. As a consequence, Browns Ferry was fined $1000 by the State of South Carolina and refused permission to dispose of spent resins at the Barnwell, South Carolina, disposal site until approved corrective actions j

have been implemented.

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=

20 ACCIDENTS APRIL 1986 There were two loss-of-time accidents during the month of April.

0 0

00068

21 SIGNIFICANT OPERATIONAL EVENTS APRIL 1986 Unit 1 04/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues I

04/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues l

00068

22 Significant Operational Events APRIL 1986 Unit 2 04/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues 04/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues I

i 6

0006B

23 1

SIGNIFICANT OPERATIONAL EVENTS APRIL 1986 Unit 3 i

l 04/01/86 0001 Unit began environmental qualification and modification outage to comply with NRC requirements.

1 04/30/86 2400 Environmental qualification and modifications outage i

to comply with NRC requirements continues.

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24 PLANT INSTRUCTION REVISIONS APRIL 1986 Category Instruction

Reason for Request

Change in BF SI-4.3.B.2 Control Surveillance Instruction Response to Rod Drive Housing Support Review Project NCO 86-0125-003 LER, IE (86-1026-003). The conduct of i

Bulletin, NRC the review itself implements Inspection the noted commitments.

i Report, OPQA Audit, etc.

BF EMI-105 Not'or' Operated References'and Implements Valve Analysis Test System recommendation in response to t

IE Notice 85-020, that spring pack relaxation does not occur. Moves data cover sheet to page 1.

Implements the recommendations of the 2-FCV-69-12 Critique

1. 86-0013.

Expands and clarifies precautions. Adds step to verify stem rotation does not occur.

Rearranges steps so that the proper interlock jumpers, lifts, or boots are verified prior to making any test connections.

Adds second person verification that support rod nuts are tight.

Improves test data. Adds an optional k-factor calculation formula.

BF CI 400 Sampling Corrects, clarlfles, and adds l

Procedures Section's CI procedures 46.5.4a LER 260-85004.

00068 i

25 REPORTABLE OCCURRENCES APRIL 1986 Occurrence BFR0 Date Description Unit 1 259/86011 03/25/86 Emergency Equipment Cooling Water (EECW) pumps A3, B3, B1, and Cl started unexpectedly.

Investigation of the event revealed the following: The raw cooling water supply piping to the control air compressors was being isolated-for-pipe-change-out-maintenance.

Low pressure switches in the supply piping.were, however, overlooked duri.ng the preparation of the hold order boundaries. The hold order required hand control valve 24-562 be closed which isolated the air compressors and low pressure switches from the raw cooling water supply. This caused a trip of the low pressure switches which in turn started the four EECW pumps. The EECW system is designed to provide emergency cooling water to the air compressors on loss of normal raw cooling water pressure. The hand control valve was reopened thus resetting the pressure switch and the EECW pumps were secured.

o I.

1 0006B

_ _~

.-.. __=

I 26 REPORTABLE OCCURRENCES APRIL 1986 Occurrence BFR0 Date Description I

Unit 2 i

There were no items reportable this month.

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27 i

REPORTABLE OCCURRENCES APRIL 1986 1

Occurrence BFR0 Date Description Unit 3 i

There were no items reportable this month.

i s

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4 0006B

28 PRIMARY COOLANT CHEMISTRY APRIL 1986 Parameter Unit 1 Unit 2 Unit 3 1.

Gross Radioactivity a.

Crud (filter) (uci/ml)

High Low NOT REQUIRED DURING SHUTDOWN Average b.

Filtrate (uC1/ml)

High Low NOT REQUIRED DURING SHUTDOWN Average 2.

Suspended Solids (l)

(Fe, ppb)

High N/A N/A 100 Low N/A N/A

< 10 Average N/A N/A 15 3.

Tritium (uci/ml)

High 3.17E-04 4.14E-04 2.27E-04 Low 2.92E-04 3.76E-04 1.88E-04 Average 3.06E-04 3.99E-04 2.11E-04 4.

Iodine-131 (uci/ml)

High

<MDA

<MDA

<MDA Low

<MDA

<MDA

<MDA Average

<MDA

<MDA

<MDA 5.

Iodine-131: Iodine-133 Ratio High Low NOT REQUIRED DURING SHUTDOWN Average (1)Not required when there is no fuel in vessel 0006B n.

29 PRIMARY COOLANT CHEMISTRY (Continued)

APRIL 1986 Parameter Unit 1 Unit 2 Unit 3 6.

Chloride (ppb)

High

<10

<10

<10 Low

<10

<10

<10 Average

<10

<10

<10 7.

DH 250C High

'6.2

'6.2 6.1 Low 5.8 5.7 5.7 Average 6.0 6.0 6.0 0

8.

Conductivity (umho/cm 25 C)

High 0.79 1.4 (1) 1.2 Low 0.54 0.76(1) 0.53 Average 0.64 0.92(1) 0.79 (1) Dip cell conductivity.

d f

0006B

W LIQUID 3BADWASTE MONTHLY OPERATING REPORT APRIL 1986 3ATA PLOTTED FOR THE PREVIOUS 12 MONTHS 50 -

- 2 RATEfG,M) 40 _

HI 30.80 LOW 18.49 AVG 23.38 30.

i TOTAL RELEASE foil

~

HI 0.11 LOW 0.02 AVG 0.05 10 _

O FLOWRATE j

0 U

C

~

9 0 g RELEASE (CI)

MAY JUN TUL AUG SEP GCT NOV DEC JAN FEB FAR APR THROUGHPUT WASTE 8

GALLONS X 10 HI 0.43E+07 7

LOW 0.15E+07 AVG 0.29E+07

~

FLOOR DRAIN HI 0.21E+07 exuss LOW 0.78E+08 AVG 0.14E+07 4 _

LAUNDRY 3 - ll I l I HI 0.12E+08 LOW 0.78E+05 2 -

AVG 0.93E+05 l~

b h MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR COST OF OPERATION o,E irro 7foo unm THOUSA S OF DOLLARS WASTE 85 _

HI O.33E+05 LOW 0.88E+04

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AVG 0.20E+05 50 -

FLOOR DRAIN 45 -

HI 0.35E+05 40 -

LOW 0.48E+04 35 -

AVG 0.18E+05 30 _

25 _

LAUNDRY HI 0.89E+03 20 _

15,

LOW 0.00E+00 AVG 0.50E+03 10 MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR WASTE COLLECTOR SYSTEM LAUNORY SYSTEM FLOOR DRAIN SYSTEM

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Unit-2 Reactor Power Percent I

I lil! Ill l

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III :

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ll lil ull Il li i

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In lll lll lI nn n 91; i u n In un i i

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~

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Tv4 ne2A loNp+su NUCLEAR PLANT OPERATING STATISTICS Browns Ferry Nuclelf Plant Period Hours Month 19 item No.

Unit No.

Unit-1 Unit-2 Unit-3 Plant 1

Averace Hourly Gross Load, kW 0

0 0

0 2

Maximum Hour Net Generation, MWh 0

0 0

0

_ 3 Core Thermal Energy Gen. GWD (t)2 0

0 0

0 4

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

5 Gross Electrical Gen., MWh 0

0 0

0 6

Station Use, MWh 1559 5447 3244 10250 j

E 7

Net Electrical Gen., MWh

-1559

-5447

-3244

-10250 8

Station Use, Percent 0

0 0

0 1

9 Accum. Core Avg. Exposure, MWD / Ton 0

0 0

0 10 CTEG This Month.10 BTU 0

0 0

0 6

11 SGTEG This Month,106 BTU 12 13 Hours Reactor Was Critical 0

0 0

0 14 Unit Use, Hours. Min.

0 0

0 0

15 Capacity Factor, Percent 0

0 0

0 3

16 Turbine Avail. Factor, Percent 0

0 100.0 33.3 17 Generator Avail. Factor. Percent 0

0 100.0 33.3 e

18 Turbooen. Avail. Factor. Percent O

O 100.0 33.3 19 Reactor Avail. Factor. Percent O

O 100.0 33.3 2

20 Unit Avail. Factor. Percent O

O O

O 21 Turbine Startuos 0

0 0

0 22 Reactor Cold Startuos 0

0 0

0 23 24 Gross Heat Rate, Btu /kWh 0

0 0

0 y

25 Net Heat Rate, Btu /kWh 0

0 0

0 3

26 C

27 y

28 Throttle Pressure, psig 0

0 0

0 1

29 Throttle Temperature, *F 0

0 0

0

.a 30 Exhaust Pressure, inHg Abs.

0 0

0 0

c E

31 intake Water Temp., F 0

0 0

0 32 33 Main Feedwater, M lb/hr 0

0 0

0 34 35 36 37 Full Power Capacity, EFPD (3)

(4)

(4)

(4) l' 38 Accum. Cycle Full Power Days, EFPD (3)

(4)

(4)

(4) s 39 Oil Fired for Generation, Gallons 1336 5

40 Oil Heatino Value. Btu / Gal.

139,500 41 DiawJ Generation. MWh 54.6 47 Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date M_Wh Date Factor, %

3 43 U

U U

c Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.

5 2(t) indicates Thermal Energy.

j (3)

Inf ormation furnished by Reactor Analysis broup - ulattanooga (4) Administrative hold n

Data Submitted Date Revised Plarit Supbrintendent

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38 ELECTRICAL TECHNICAL SECTION MONTHLY REPORT - APRIL 1986 Unit Common Major Non-Routine Activities -

Overtime of 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> was worked on SCR BFN EEB8536 obtaining motor overload relay information.

Unit two and all common boards are complete, including submission of drawing discrepancies and corrective maintenance requests; unit three boards are now being worked.

Completed unit two HFA relay coil changeout.

Work continues on QMDS valves.

Remodeling began April 30 on part of the old concrete test lab to convert it into a circuit breaker maintenance facility.

This facility will allow us to begin the long overdue circuit breaker overhaul program.

Schedule maintenance forms BF 111 were submitted to place all 4-kV, 480V, and 250V switchgear under the preventive maintenance program.

Significant effort was made to resolve open DRs and CARS.

Since March the backlog has been reduced from approximately two dozen to approximately six.

Major rework of the unit two outage schedule for this section was accomplished and submitted to Planning. The schedule will now be a much more meaningful document.

Don Reynolds was reassigned to the Communications & Security Maintenance Section.

One college recruit, Joseph Maxwell, accepted an offer of employment and is to report June 9, 1986.

Bill King attended a PCB Seminar in Atlanta on April 3, 1986.

Donnie Smith went to Splicing and Termination School.

Steven Thomas attended Systems Training.

ASSIGNMENTS:

Backlog 434 New Assignments 47 Completed Assignments 119 Overtime 15.5%

39 2

ELECTRICAL TECHNICAL SECTION MONTHLY REPGRT - APRIL 1986 MR TRACKING PROGRAM UNITS 0, 1, 2. AND 3 STATUS CODES DESCRIPTION A

MRs in status.'A' have been scoped and are available for work, Planning complete. These MRs are/or should be on the daily schedule.

295 E

MRs in status 'E' are on hold for equipment outage.

O F

MRs in status

'F' are for Fuse Program activities.

The word " FUSE" shall also be added in remarks to identify MR3 for the Fuse Program after the MRs are placed in

'X' and 'C' status.

O H

MRs in status 'H' are on hold for reasons other than established codes, such as Engg or Specialist review. The remarks field should 81 indicate the MR disposition.

M MRs in status 'N' are waiting on materials. MRs in this status should reference the contract number, contract item number, and contract performance date.

59 P

MRs in

'P' status are MRs in Planning which are available for the General Foreman to select for work. NOTE: N0 MRs in this status I

should be selected for work if the scope of work is not completely l

clear; these MRs should be moved to the 'S' status and the job scoped by the responsible Maintenance Scoper.

584 l

S MRs in this status are being scoped by the Maintenance Scoper'. The Scoper shall completely scope the job, prepare planning checklist and return to Planner for disposition, 95 1

T MRs in this status are work complete but waiting on postmaintenance testing.

5 0

MRs requiring unit short outage or refueling outage.

30 Total Backlog 1284 Total MRs Received 510 Total MRs Completed 516 9

l

40 MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)

April, 1986 COMMON No major non-routine activities.

The following instructions were approved or revised:

1.

MMI Reactor Core Isolation Cooling (RCIC) System Maintenance, Units 1,2,3 2.

MMI High Pressure Coolant Injection (HPCI) System Maintenance, Units 1,2,3 3.

MMI 23A - High Pressure Coolant Injection (HPCI) Booster Pump, Units 1,2,3 4.

MMI Changing and/or verification of Pressure in the EHC System Accumulators 5.

MMI 49 - Residual Heat Removal (RHR) Heat Exchanger Maintenonce 6.

MMI Preventative and Corrective Maintenance of Limitorque Operators 7.

MMI Opening and Closing of Primary Containment Hatches 8.

MMI-102 - Rigging Equipment Program 9.

MMI-129 - Opening and Closing of Drywell Personnel Airlock Doors 10.

MMI-141 - Lubrication of Equipment 11.

MMI-157 - Inspection, Lubrication and Replacement of LPCI MG-Set Couplings and Bearings, Units 1,2,3 12.

MMI 159 - Sampling Inspection Program for Verifying Correct Installation of Concrete Expansion Shell Anchors 13.

MMI-160 - Secondary Containment Damper Preventative Maintenance 14.

SI 4.6.11.1 - Visual Examination of Hydraulic and Mechanical Snubbers 15.

SMMI 3.0 (Unit 1) - Dye Penetrant Inspection of Instrument and Sampling Lines and the Vent, Drains, and Packing Leak-off Lines on the First Isolation Valves - Unit 1 16.

SMMI 3.0 (Unit 2) - Dye Penetrant Inspection of Iastrument and Sampling Lines and the Vent, Drains, and Packing Leak-off Lines on Major Isolation Valves in the Drywell - Unit 2 17.

SI 1 -

Main Steam Relief Valves 18.

MMG 035-1301 - Stator Cooling System Maintenance

41 MECHANICAL TECHNICAL SECTION MONTHLY REPORT - CONTINUED April 1986 19.

MMG 1601 - Inspection and Cleaning of Sumps and Drains '

20.

MMG 2401 - Breathing Air System Instructions for Operation and Maintenance 21.

MAI Protective Coating Application by Approved Vendor for Steel and Concrete in the Drywells In addition to the previously mentioned activities, the section was involved in the following.

1.

Closed the following Discrepancy Reports (DRs) and Corrective Action Reports (CARS):

a.

DR 85-599 - Stack gas sample pumps 81 and B2 were rebuilt without CSSC parts.

b.

DR 86-145 - Out-of-tolerance investigation report on pressure gage E83450, delinquent.

Report was not received by Mechanical Maintenance until after due date.

c.

DR 86-194 - MR 629049, CSSC MR worked without QA review.

d.

DR 85-500 - PT examination of the weld build-up area of the 64 series ventilation valve disc's, revealed several flaw indications in the base metal.

Indications were removed, without proper documentation, e.

CAR 85-064 -Stainless steel flanges bolted with carbon steel.

2.

Mechanical Technical Section, Unit 0, devoted 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> to training during April 1986.

3.

Maintenance Requests to craft:

MRs received - 509 MRs completed - 437 O

_ _ = - - - -

42 DROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES 2 MAY 1986 1:27:16 PM RADI0 ACTIVE LIQUID EFFLUENTS 1.

GROSS RADIOACTIVITY UNITS (1) a)

total RELEASE CURIES 3.62E-02 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI.'ML 2.24E-09 c)

MAXIMUM CONCLNTRATION RELEASED UCI/ML 5.58E-09 d)

PRECENT OF APPLICABLE L-IMIT (20 CI/ QUARTER) 1.G1E-01 2.

TRITIUM a)

TOTAL RELEASE CURIES 8.91E-01 b)

AVERAGE DILUTED CD MENTRATION RELEASED UCI/ML 5.5LE-08 c)

PRECENT OF APPLICAB..E LIMIT (3E-03 UCI/ML) 1.84E-03 (2) 3.

DISSOLVED NOBLE GASES a)

TOTAL RELEASE CURIES 1.71E-03 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.06E-10 s

c)

PRECENT OF APPLICABLE LIMIT (6E-06 UCI/ML)

< 1.77E-03 4.

GROSS ALPHA RADI0 ACTIVITY l

a)

TOTAL RELEASE CURIES 2.50E-05 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.55E-12 5.

VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 3.67E 06 6.

VOLUME OF DILUTION WATER LITERS 1.62E 10 (1)

DASED ON PRE-RELEASE ANALYSES WHICH ARE NOT DECAY CORRECTED (2)

INCLUDES Xe-133, Xe-135, AND OTHERS

43 j

BROUNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES ISOTOPES RELEASED UNITS CI CR-51 3;41E-05 11N-54 1.42E-04 CO-58

5.55E-04 FE-59

8.91E-04 CO-60 2781E-03 ZN-65 1.10E-02 NB-95

< 5.32E-04 ZR-95 9.38E-04 MGTC-99M

< 4.18E-04 I-131

< 6.33E-04 XE-133

< 1.24E-03 CS-134 6.84E-03 XE-135

< 4.77E-04 CS-137 1.53E-02 BA-140

< 2.33E-03 LA-140

< 1.42E-04 CE-141

< 7.02E-04 SR-89

< 1.08E-04 SR-90

< 7.70E-05 4

44

)

BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS j

LIGUID RELEASES j

OTHERS UNIT 3 CI i

AG-110M 1.21E-04 i

1 l

t t

i I

i 3

t i

i t

I i

I e

._ -. =,= =

=.= =

==

.=

45 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES 2 MAY 1786 1:27:16 PM LAUNDRY DRAIN VOLUME RELEASED:

91465.8 GALLONS FLOOR DRAIN VOLUME RELEASED:

763962.9 GALLONS WASTE SAMPLE TANK VOLUME RELEASED:

113245.0 GALLONS DISTILLATE TANN VOLUME RELEASED:

0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLUME RELEASED:

0.0 GALLONS TOTAL VOLUME RELEASED TO THE RIVER:

968673.7 GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR MONTH:

5.58E-09 UCI/ML A/D LONGEST RELEASE TIME FOR MONTH *-

360- MINUTE $

SHORTEST RELEASE TIME FOR MONTH:

210 MINUTES TOTAL TIME OF RELEASES FOR MONTH:

10668 MINUTES AVERAGE TIME FOR BATCH RELEASES:

305 MINUTES COMPOSITE INFORMATION:

COMPOSITE CI AFTER DILUTION UCI/ML RELEASED UCI/ML SR-89

< 2.95E-08

< 1.08E-04

< 6.70E-12 SR-90

< 2.10E-08

< 7.70E-05

< 4.77E-12 H-3 2.43E-04 8.91E-01

. 5.51E-08 GROSS ALPHA 6.83E-09 2.50E-05 1.55E-12 s

NUMBER OF BATCHES RELEASED:

35 NUMBER OF ADMINISTRATIVE LIMIT VIOLATIONS:

0 NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS:

0 1

46 AIRBORNE RELEASES APRIL 1986 Summation of All Releases Unit This Month 1.

Fission and Activation Gases a.

Total Release Ci

<1.62E+02 b.

Average Release Rate for Period uCi/see

<6.70E+01 c.

Percent of T.S. Limit (0.05 C1/sec) 0.00E-01 2.

Iodines a.

Total Iodine-131 Ci

<3.49E-05 b.

Average Release Rate for' Period uC1/sec

<1.44E-05 c.

Percent of T.S. Limit (0.4 uC1/sec) 0.00E-01 3.

Particulates a.

Particulates with half-lifes

> or = 8 days Ci 5.48E-05 b.

Average Release Rate for Period uC1/see 2.26E-05 c.

Percent of T.S. Limit (0.4 uC1/sec) 5.66E-03 d.

Gross Alpha Radioactivity Ci

<1.36E-09 4.

Tritium a.

Total Release Ci 4.73E-01 b.

Average Release Rate for Period uCi/sec 1.96E-01 c.

Percent of T.S. Limit 3.37E-01 d.

Ground Level Release Ci 4.73E-01 e.

Elevated Release Ci

<1.02E-03 (1) Reporting Period - 28 days.

l 0006B

47 AIRBORNE RELEASES (Continued) l APRIL 1986 Elevated Releases 1.

Fission Gases Unit This Month Kr-85m Ci

<2.45E-01 Kr-85 Ci

<9.21E+01 Kr-87 Ci

<6.14E-01 Kr-88 Ci

<9.73E-01 Xe-133 Ci

<6.93E-01 Xe-135m Ci

<9.57E-01 Xe-135 Ci

<2.61E-01 Xe-138 Ci

<9.17E-01 Others (Specify)

N/A Total for Period Ci

<9.68E+01 2.

Iodines I-131 Ci

<2.52E-06 I

I-133 Ci

<9.67E-06 I-135 Ci

<4.04E-04 Total for Period Ci

<4.16E-04 3.

Particulates Sr-89 Ci

<1.99E-07 Sr-90 Ci

'<7.73E-08 Cs-134 Ci

<4.95E-06 Cs-137 Ci

<5.78E-06 Ba-140 Ci

<1.69E-05 La-140 Ci

<1.11E-05 Others (Specify)

N/A Total for Period Ci

<3.91E-05 4.

Tritium Ci

<1.02E-03 0006B 1

48 SOLID RADIOACTIVE WASTE APRIL 1986 Condensate / Waste Rosin Shipments 1 Approximate Volume of Resin / Sludge Shipped 4.08 Cu.N.

(144 Cu.Ft.)

Total Curies Shipped 18.3078 Principal Isotopes Zn65, Cal 37,Cs134,Co60,Fe55 Date Shipped Disposal Facility 03/31/86 Barnwell, SC Reactor Water Cleanup Rosin Shipments 1 There were no cleanup resin / sludge shipments.

Drunused Shipments 1 There were no drum shipments.

Boxed Shipments 1 There were no box shipments.

(1) All shipments by Sole-use truck.

1 1

b I

00068

49 SOLID RADIOACTIVE WASTE (Continued)

APRIL 1986 Summary Shipped to Stored Approximate Proposed for Barnwell Onsite Cost May 3

3 Ft (2) 1035 Ft3 1050 Ft (2)

Compacted Drums 0 3

Ft (2) 0 Ft3 0

3 Ft (2)

Compacted Boxes 0 3

Ft (2) 560 Ft3 0

3 Ft (2)

Drums 0

3 3

Ft (2) 4768 Ft3 4768 Ft (2)

Boxes 0

3 Ft (1) 1501 Ft3 18,746.40 0

3 Ft (2)

CWPS Resin 144 Ft (1) 672 Ft3 0

Ft3(2) 3 RWCU Resin 0

~

Ft (2) 8536 Ft3

$18,746.40(3) ' 5818 Ft (2) 3 3

Totals 170 3

Total volume of waste shipped during the month:

170 Ft (2)

Available 1986 burial space remaining at Barnwell:

73490 Ft3 (1) Actual resin volume.

(2) Container burial volume.

(3) Cost included are for containers, transportation, and disposal.

Prepared principally by R. D. Nosley.

6 i

I 0006B l

... ~.

.- ~. -..

8

~

50 CUBIC FOOTAGE OF RADWASTE GENERATED 15000-14500-14000-13500-13000-12500-i 12000-11500-11000-10500-I 10000-l 9500-9000-8500-8000-7500- +

7000- ------- ---------------1986 MONTHLY ALLOTMENT------------------------

6500-f 6000-5500-

+

5000-4500-

+

4000-

+

+

3500-

+

+

+

+

3000-

+

2500-l 2000-1500-

+

}

1000-500-0-

i M

J J

A S

O N

D J

F M

A A

U U

U E

C 0

E A

E A

P Y

N L

G P

T U

C N

B R

R l

'85

'85

'85

'85

'85

'85

'85

'85

'86

'86

'86

'86 i

i

.I i

f

f 9

51 RESIN USAGE REPORT l

APRIL 1986 RESIN CONSUMED (CU.FT.)

% of Total Bead POWDEX ECODEX ECOSORB EPIFLOC Total Radwaste Floor Drain Filter 42 0

160 0

0 56 216 Waste Domineralizer 5

26 0

0 0

0 26 Waste Filter 29 92 0

0 60 152 Fuel Pool Demins 6

0 32 0

0 0

32 Reactor Water Cleanup Unit 1 1

0 6

0 0

0 6

Unit 2 0

0 0

0 0

0 0

Unit 3 5

0 28 0

0 0

28 Cond. Demins Unit 1 4

0 20 0

0 0

20 Unit 2 4

0 20 0

0 0

20 Unit 3 4

0 20 0

0 0

20 Totals 100 26 378 0

0 116 520 Prepared principally by S. B. Jordan.

e 0006B

\\

e 52 FUEL CLADDING INTEGRITY PARAMETERS APRIL 1986 Unit 1 Reactor Water Iodinos (uCi/sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uci/sec)

Date Flow MWt Xe-138 Kr-87 Kr-88' Kr-85m Xe-135 Xe-133 Unit in Outage Unit 2 Reactor Water Iodines (uCi/sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Finston Geses at Discharge of SJAE (uci/sec)

Date Flow NWt Xe-138 Kr-87 Kr-88 Kr-85m Ke-135 Xo-133 Unit in Outage Unit 3 Reactor Water Iodines (uCi/sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uC /sec)

Date Flow NWt Ye-138 Kr-87 Kr-88 Kr-85m Xe-135 Xo-133 Unit in Outage i

0006B

e I l WASTE TitEAT!!ENT SYSTE!! V01.ll!1I'. TiliW!'CitPUTS( X }

April MontS TO CN.!AT.----

2.59E04 DWN H.S lam

2. mM p 3E04 pd

""d)

COLLECTOR

).

DitAIN SAMPLE l>

gpd..

TANK

.TER TANK

[ 7.77E05 gal]

[7.64005 gal]

[9. 69E05 gal) 216(0) 3 R

c.'

[7.77E05 gall 0

37 IJsUNDRY 3,05E03 end o 4.33E02 97' DRAIN gpd TANK

[9.15E04 ga(

{0 j

[ 1.30E04 gall

\\i 0

cpd u

-4*90E04 m"' d>

'^

DISTILLAT2 0

1.47E06 gal V

[

0 galj~~)

l

)

IAI-3.77E03 cpd l

l l

!1.13E05 gall i ~~

~~l WASTE I

i ggg7g ca::. 3;,7 7 COLLECTOR UASTE WASTE SM'PLE 4.93E04 gpd, 4,172Q4,._",pd g c-jpg TAI;K FILTLR y

DEMI:!ERALIZEE b

i

~

TANK

~ gy'

[1.48E06 gal)

{1.37E06 gal) 152 (3) f t3 26 ft

.j j

l 1

i

[1.48E06 gall

, 4/28/86 (1) Represents 30 days, gpd cverage gallers per dry

=

(2) Values accurate to two (2) significant figures

[

total gallens

=

(3) 160 Ft of powdered resins, 56 Ft of resin and fiber mixture, o Ft3 of Ecosorb.

(4) 92 Ft of powdered resins, 60 Ft of resin and fiber mixture.

0-Ft of Ecosorb.

A,.

TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 JUN 0 41986 Nuclear Regulatory Conunission Office of Management Information and Program Control Washington, D.C.

20555 Gentlemen:

Enclosed is the April 1986 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY

/

[RobertL. Lewis o

Plant Manager Enclosure e t. : 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 i

and Enforcement Nuclear Regulatory Commission l

Washington, D.C.

20555 (10 copies)

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

P. O. Box 10412 Palo Alto, California 94304 i

I 9 k An Equal Opportunity Employer