ML20212L047

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Monthly Operating Repts for Oct 1986
ML20212L047
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/31/1986
From: Creamer K, Robert Lewis
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8701290296
Download: ML20212L047 (17)


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

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CONTENTS Operations Summary...

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

3 Significant Operational Rvents......................

5 Average Daily Unit Power Level...................... 6 Operating Data Reports..........................

9 Unit Shutdowns and Power Reductions...................

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Operations Summary OCTOBER 1986 The following summary describes the significant operation activities during the reporting period. In support of this summary, a chronological los of significant events is included in this report.

There were seven reportable occurrences and no revisions to previous occurrences reported to NEC during the month.

Unit 1 The unit remained on administrative hold the entire month. The unit is also 1

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

This was prepared principally by T. R. Smith.

0027B

2 Operations Susmaarr (Continued)

OCTOBER 1986 Fatigue Usaae Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usaae 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 0.24204 0.17629 0.14326 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.b(3) reporting requirements.-

Coaumon System Approximately 13.93E+05 gallons of waste liquids were discharged containing approximately 2.64E-02 curies of activity.

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Refueling Information s,

OCTOBER 1986 Unit 1 e'

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 restset date to be determined. The sixth refueling will involve loadirs 8x8R.(retrofit) fuel assemblies into the core. The prior-to-startup unit 1 itosas 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 O sonry walls (IEB-80-11), evaluation of the vent drain and test connections, VDTC, (LER-82020), valve modification (Appendix J), HPCI concerns, modification of PCIS logic (LER 259-85009), replacement of plant process 1

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. '

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  • There are.0 assemblies in the reactor vessel. The spent fuel storage pool presently contaids 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available capacity I

of the fuel pool'.is 1355 locations.

Unit 2

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

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with a echeduled r'estart date to be determined. On September 3, 1985, the unit was placed ori' 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 (I88-80-17),

environmental qualification of electrical equipment (10 CFR 50.49), torus modifications (NUREG-0661), containment modification (NUREG-0737), electrical changes (Appendix R 10 CFR Sd) (partial), NSIV modifications, modification of masonry walls (IEB-80-11), addition of foedwater 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 00278 e-

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4 Refueling Information OCTOBER 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 303 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 swallable capacity of the spent fuel pool is 1164 locations. All HDRs have been installed in the pool with the exception of two.

s 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 to be determined. 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-

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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 (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 (IES 79-02/14), postaccident evaluation (NUREG-0737), addition of l

redundant drywell control air supply, RPS modification (IE Notice 78-45),

H0 sample line modification (LER 81-050), radiatiEn 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.

4 There are 764 assemb' lies presently in the reactor vessel. There are l

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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Significant Operational Events OCTOBER 1986 Unit 1 10/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.

10/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.

fait 2 10/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.

10/31/86 2400 Unit remains-on administrative hold-to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.

Unit 3 10/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and envircamental qualifications and modifications continues.

10/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT be DATE "11-1-86 COMPLETED BY

_K.

L. Creamer TELEPHONE (205) 729-2960 MONTH October DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL tMWr Neti (Mwe Net) 1

-3 17

-3 2

-2_

18

-3 ' '

3

-2 gg

-3

-1 4

20

-3 5

-1 21

-2 6

-1 22

-3 7

-2 23

-2

-4 3

24 9

-3 25

-2

-3 10 26

-1 ll

-3 27

-2 12

-3

-2 23 W

13

-3 29

-3 4

-3

-3 3g 15

-3

-3 3,

16

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l 1.*ii TR t!CT10NS On th.<jormat, hst the averge daih umt p mtr fewlin MWe. Net for each day in the reporting month.Cornpute to l

ihe r.e4 rest whole nwgawatt, l

(9/77 )

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 b

UNIT DATE 11-1-86 COMPLETED BY K. L. Creamer TELEPHONE (205) 729-2960 l

October MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL iMWr Net)

(MWe Net) 1

-5

-4 g7 2

-5 gg

-5 * ^

3

-6 gg

_4

-5 4

20

-4 5

-5

~ 21

-5 6

-4 22

-5 7

-5 23

-3 3

-5 24

-3

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9

-5 25

-3

-5 10 26

-4 11

-5 27

-4 I:

-5 23

-3 W

13

~4 29

-4 34

-5 30

-5 15 31 3

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INS TRt!CT10NS Onth. Jorn:st,hst the awrg: dails urut p.m lewiin MWe Net for each dayin the reporting month. Cornpute to the r.esrnt whole megswatto (9/77i i

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8 AVE 2 ACE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 11 NIT _ hree DATE 11-1-86 COMPLETED BY t"-

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TELEPHONE (205) 729-2960 MONTH October DAY AVERAGE D I P WER LEVEL Dry AVER ACE DAILY POWER LEVEL (MWe Net) 1

-4 37

-5 2

-4._

13

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3

-4 gg

_4 4

-4 20

-4 5

-4 21

-4

-5

-5 6

.22 7

-4

_4 23

-5 s

-4 34 9

-5 25

-4 10

-4 26

-4 13

-5 4

37 12

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-5 14

-4 30

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IN5 ! RUCTIONS 8

H-e hbi or enh day in the reporting month. Compute eo

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OPERATING DATA REPORT DOCKET NO.

50-259 DATE 11-1-86 COMPLETED BY K. L. Creamer TELEPHONE

(?nn 7?o-2960 OPERATING STATUS

1. Unit Name:

Bmns Fem One Notn October 1986

2. Reporting Period:

3293

3. Licensed Thermal Power (MWt):

1152.

4. Nameplate Rating (Gross MWe):
5. Design Electrical Rating (Net MWe):

1065

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. lf Any (Net MWe):

N/A

10. Reasons For Restrictions. lf Any:

N/A This Montb Yr. to-Date

, Cumulative i

745 7,296 107,456

11. Hours in Reporting Period 0

0 59.521.38

12. Number Of Hours Reactor Was Critical 0

0 6,997.44

13. Reactor Re erve Shutdown Hours
14. Hours Generator On-Line 0

0 58.267.26

15. Unit Reserve 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 Electrical EnerEy Generated (MWH)

-1.897

-31.807 53.725.202

19. Unit Service Factor 0

0 54.2

20. Unit Availability Factor 0

0 54.2 0

0 47.0

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

47.0

22. Unit Capacity Factor (Using DER Net) 100 100 34.3
23. Unit Forced Outage Rate i

t

24. Shu: downs Scheduled Over Next 6 Months (T)pe. Date,and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup:

To be determined.

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

Forecast Achieved INITIA L CRI flCA LITY INITIAL ELECTRICITY CO\\l%IERCIAL OPER ATION (9/77)

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50-260 DATE 11-1-86 COMPLETED 11Y E.

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(' reamer TELEPHONE (2ns) 729-2960 OPERATING STATUS m us Fe m h o Notes

1. Unit Name:
2. Reporting Period: October 1986 3293
3. Licensed Thermal Power (MWt p:

1152.

4. Nameplate Rating (Gross MWe)\\

1065 S. Dessen Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

1098.4 1

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 Any (Net MWe):

N/A

10. Reasons For Restrictions,If Any:

M /A This Month Yr..to Date Cumulative i1. Hours In Reporting Period 745 7,296 102,343 0

0.

55,860.03

12. Number Of Hours Reactor Was Critical
13. Reactor Reserve Shutdown Hours 0

0 14,200.44

14. Hours Generator On-Line 0

0 54,338.36

15. Unit Reserve Shutdown flours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

153,245,167

17. Gross Electrical Energy Generated (MWH) 0 0

50,771,798

18. Net Electrical Energy Generated (MWH)

-3,260

-42,956 49,222,408-

19. Unit Senice Factor 0

0 53.1 0

0 53.1

20. Unit Asailability Factor
21. Unit Capacity Factor (Using MDC Net 1 0

0 45.2

22. Unit Capacity FactorIUsing DER Net) 0 0

45.2

23. Unit Forced Outage Rate 100 100 32.7
24. Thutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup:

To be determined.

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

Forecast Achiesed INITIA L CRITICA LiTY INITI A L ELECTRICITY CO\\l%IERCIA L OPER A TION i

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11-OPERATING DATA REPORT 50-296 DOCKET NO.

DATE 11-1-86 COMPLETED BY K. L.

Creamer TELEPHONE (?nsi 7?S-2960 OPERATING STATUS I. Unit Name: _ Rr=,w worry Three Notes

2. Reporting Period:

October 1986

3. Licensed Thermal Power (MWt):

3293 1152

4. Nameplate Rating (Gross MWe):

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 Rati::gs (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.If Any: N/A This Month Yr.-to.Date Cumulative II. Hours in Reporting Period 745 7,296 84,768
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 Em rgy Generated (MWH) 0 0

131,868,267

17. Gross Electrical Energy Generated (MWH) 0 0

43.473.760

18. Net Electrical Energy Generated (MWH)

-3.246

-33.036 12,100,737

19. Unit Service Factor 0

0 52.1 0

0 52.1

20. Unit Availability Factor U

U "O*O

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

46.6

23. Unit Forced Outage Rate 100 100 35.1 s
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:

To be determined.

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26. Units in Test Status (Prior to Commercial 0perationi:

Forecast Achiesed i

INI TIA L CRITICALITY l

INITIAL ELECTRICITY C0\\l%f ERC) \\ L OPFR ATION (9/77)

l UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-259 UNIT NAME One DATE 11-1-86

  • October COMPLETED BY r.

T.. r'ran-o r REPORT MONTH TELEPHONE (205) 729-2960 n.

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Cause & Corrective

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No.

Date r;

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Action to

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Prevent Recurrence 6

315 10-1-86 F

745 F

4 Administrative ho? d t o resolve (Cont) various TVA and NRC concerns, t

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F: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-j D Regulatory Restriction 4-Other (Explain) 0161) 3 E-Operator Training & License Examination F-Administrati.e 5

t G-Operational Error (Explain)

Exhibit I - Same Souree

('s/77)

II4hher (Explain) i s.

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.s-UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260

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UNIT NAME Two DATE 11 1 u October COMPLETED gy K.

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Creamer REPORT MONTH TELEPHONE (2051 729-2960 w.

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Cause & Corrective g*L No.

Date g-3g 5

.E 5 E Event 3,7

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Eg' Prevent Recurr'ence

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6 305 10-1-86 F

745 F

4 Administrative hold to resolve (Cont) various TVA and NRC concerns.

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F: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A Equipment Failure (Explain) 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 Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 Same Source 19/77) 11-01her (Explain)

4 50-296 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Three DATE 11-1-86 COMPLETED BY r-t-

ce,=mor REPORT MONTH n,eahor TELEPHONE (205) 729-7960 "i

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hIk Licensee

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Cause & Corrective No; Date

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Event

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Action to

$E jgg Report a 50 jU Prevent Recurr'ence 6

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157 10-1-86 F

745 F

4 Administrative hold to resolve (Cdnt) various TVA and NRC concerns.

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4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

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

Event ReporI(LERI FileINUREG-D-Regulatory Restriction 44 her (Explain) 01611 E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 - Same Source (9/77)

. II-Other (Explain) e

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o TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 NOV 181986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, D.C.

20555 Gentlemen:

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

Very truly yours, TENNESSEE VALLEY AUTHORITY u

obert L. Lewis Plant Manager Enclosure cc: Director, Region II INPO Records Center Nuclear Regulatory Cosaission 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 Cosuaission Washington, D.C.

20555 (10 copies)

Mr. A. Rubio, Director l

Electric Power Research Institute l

P. O. Box 10412

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Palo Alto, California 94304 I

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An Equal Opportunity Employer

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