ML20214L662
| ML20214L662 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1986 |
| From: | Ratliff S TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20214L646 | List: |
| References | |
| NUDOCS 8609100318 | |
| Download: ML20214L662 (16) | |
Text
_ _ _ _ _ _ _ _ _ _, _ _ _ _ _ _ _ _ _ _ _ _
TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT i
MONTHLY OPERATING REPORT TO NRC
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JUNE 1, 1986 - JUNE 31, 1986 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33. DPR-52, AND DPR-68 Submitted by:
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Plant ManVser' O
8609100318 860806 PDR ADOCK 05000259 R
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CONTENTS i
Operations Summary....
1 Refueling Information.
3 Significant Operational Events........
5 Average Daily Unit Power Level...
6 Operating Data Reports....
9 Unit Shutdowns and Power Reductions...................
12 Addenda - Revision to June 1985 through March 1986 and May 1986 Reports..
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Operations Summary JUNE 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 three reportable occurrences and no revisions to previous occurrences reported to NRC during the month.
Unit 1 Theunitremainedonadministrativehold'theenbiremonth. The unit is also
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undergoing its end-of-cycle 6 refueling.
Unit 2
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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.
This was prepared principally by T. R. Smith.
0033B
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2 Operations Sununary (Continued)
JUNE 1986 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629 0.14326 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
a Common System Approximately 9.48E+05 gallons of waste liquids were discharged containing approximately 6.16E-02 curies of activities t
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9 0033B
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3 Refuelina Information JUNE 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 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 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),
j EECW carbon to stainless pipe change out, and all NRC commitment items except
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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 118 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 of the fuel pool is 1,521 locations.
Unit 2 I
Unit 2 was shut down on September 15, 1984, for its fifth refueling outage l
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 l
c fifth refueling involves loading 8x8R (retrofit) fuel asseniblies into the core.
l 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 j
changes (Appendix R 10 CFR 50) (partial) NSIV modifications, modification of masonry walls (IEB-80-11), addition of feedwater nozzle temperature monitoring l
(NUREG-0619), evaluation of the vent drain and test connections, VDTC, (LER-82020), valve modification (Appendix J) (partial), D/G speed sensor 00338
4 Refuelina Information JUNE 1986 Unit 2 (Continued) installation (LER-81-004), HPCI and RCIC testable check valve change out, i
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 304 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 1165 locations. All HDRs have been installed in the pool with the exception of two.
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 schedu, led restart date of Narch 1987. The sixth refueling outage has been scheduled for September 21, 1
1988, and involves loading 8x8R (retrofit) assemblies into the core and AIWS 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), NSIV modifica-i 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 (IEB 79-02/14), postaccident evaluation (NUREG-0737), addition of 1
redundant drywell control air supply, RPS modification (IE Notice 78-45),
i H0 8 ample 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 l
change out, and plant design upgrade to seismic qualification.
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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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00338
-F 5
Significant Operational Events JUNE 1986 Unit 1 06/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues.
06/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues.
Unit 2 06/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
06/30/86 2400 Unit remains on administrative hold to resolve various ~
TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
Unit 3 06/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
06/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
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6 AVER AGE DAILY UNIT l'OWER LEVEL DOCKET NO.
50-259 UNIT One
- 86 DATE COMPLETED BY Scott Ratliff TELEPHONE 205/729-2019 MONut June DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL iMWr Neti IMWe Net) -
-3 g7
-6 2
-l
,3 7
3
_2 g,
_7 4
-2 g--
6
-1 5
21
-8 6
-2 22
-8 7
-3 73
- _ 9 8
6 24 6
9
~6 25
~7 6
6 10 26 II
-7 27
-5 l'
8 28
-7 8
13 6
-0 14
-6 15
-6 3l 16
'6 INSTRUCTIONS On this formar.hst the asera.:e daih un.: p.mst leselin \\lWe Net foi cath day in the separtmg m.mth. Compute to tr.e nearest whole mcgswatt.
(9/77)
1 AVER AGE II4ILY U. NIT POWER LEVEL 7
'n 50-260s DOCKET NO.
UNIT Two DATE 1 COMPLETED BY Scott Ratliff TELEPHONE 205/729-2019 atONTd June DAY AVERAGE DAILY POWER LEVEL DAY AVEH ACE DAILY POWER LEVEL iMWe Net)
(MWe Net) 1
- 10 17
-5 2
-8 18
-5
-0
'5 3
19
-9 s
4
-2 24 - - --n._ -
7 5
3,
-5
-9 6
22
-5 s,
-9
-5 23
-7 24
-9 9
~5 25
-5
-5 to 26
-4 Ii 5
27
-4 12
-6 23
-4 13 5
129 4
14
-5 30 4
15
-5' i e,
-5 INSTRUCT 10NS On !!.,* Jormat. list the asera.;e dash us..t p.mcr lesel in \\1Wc. Net for c.nh day tu llic returitug month. Compute t the nearSt whole mepwait, e
s (9/77) e
-M
e
- o A\\ ER 4GE IEt!LY UNil POhER LEVEL
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DOCKET NO.
Three uggy DATE '7-1-86 Sc tt Rat M COMPLETED BY TELEPif0NE 205/729-2019 Af0NTsi June t
DAY AVERAGE DA:LY POWER LEVEL DAY AVER AGE D AILY POWF.R LEVEL (M hc hell g y w e Negg 6
1
,7 5
2
-5 18
-s
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3 4
39 3
4
-4 27 " ~~
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-4 5
4 21 5
6
-4 22 5
m.
7
-4 23
-5 3
- 5 24
-5 9
9 25
-5
-5 10 3
-5
-5
-5 i
37 12
-S l
23
-5
-5 13
-5 14
-5 30
-5 15
-5 3g
-4 l e, I-INS TRUCTIONS On th.' format,hs the ecrage Juh utot powcr feielin MWe. Net for c.n.h day in the reporiang month. Compute to the r. rarest whole nwg4 wait.
(9/77)
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9 OPERATING DATA REPORT DOCKET NO.
50-259 DATE 7-1-86 COMPLETED BY S. Ratliff TELEPHONE 205/729-2019 OPERATING STATUS Notn Br wns Fe m One
- 1. Unit Name:
June 1986
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
3293 1152
- 4. Nameplate Rating (Gross MWe):
1065
- 5. Design Electrical Rating (Net MWe):
1098 4
- 6. Maximum Dependable Capacity (Gross MWe):
1065
- 7. Maximum Dependable Capacity (Net MWe).
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Laa Report.Give Reasons:
N/A
- 9. Power LevelTo Which Restricted.If Any(Net M e):
N/A
- 10. Reasons For Restrictions.lf Any:
This Month Yr..to-Date Cumulative
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- 11. Hours in Reporting Period 720 4.343 104J503.
0-0 59.521.38 -
- 12. Number Of Hours Reactor Was Critical 0
0 6,997.44
- 13. Reactor Reserve Shutdown Hours 0
0 58,267.26
- 14. Hours Generator On.Line 0
0 0
- 15. Unit Reserve Shutdown Hours 0
0 168,066,787
- 16. Gross Thermal Ener 3 Generated (MWH) 0 0
55,393,130
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH)
-4,116
-16,572 53,740,437 0
0 55.8
- 19. Unit Senice Factor 0
0 55.8
- 20. Unit Asailability Factor 0
0 48.3
- 21. Unit Capacity Factor (Using MDC Net) 0 P@
31.2 48.3
- 22. Unit Capacity Factor (Using DER Net) 100
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date','and Duration of Each t:
- 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 Achieved INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCI A L OPER ATION (9/77)
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10 OPERATING DATA REPORT DOCKET NO.
50-260 DATE 7-1-86 COMPLETED BY S-uneliff TELEPHONE 205/729-2019 OPERATING STATUS
- 1. Unit Name:
Mrn - Farry Tun June 1986
- 2. Reporting Period:
3293
- 3. Licensed Thennal Power (MWt):
1152
- 4. Nameplate Rating (Gross MWe):
1065
- 5. Design Electrical Rating (Net MWe):
1098.4
- 6. Matimum Dependable Capacity (Gross MWe):
- 7. Masimum Dependable Capacity (Net MWe):
106s
- 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:
N/A This Month Yr..to.Date Cumulative
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l1. Ilours In Reporting Period 720 4.343 99,390
- 12. Number Of Hours Reactor Was Critica!
0 0
55,860.03 0
0 14,200,44
- 13. Reactor Reserve Shutdown flours
- 14. Hours Generator On.Line 0
0 54.338.36
- 15. Unit Reserve Shutdown llours 0
0 0
0 0
153,245,167
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gron Electrical Energy Generated (MWil) 0 0
50,771,798
- 18. Net Electrical Energy Generated (MWH)
-4,057
-29,718 49,235,646 0
0 54.7
- 19. Unit Sersice Factor
- 20. Unit Asailability Factor 0
0 54.7 0
0 46.5
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 0 0
46.5 100 100 30.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date."and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
December 1986 2ti. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INillA L CRITICALITY INITIA L ELECTRICITY COM\\lERCIAL OPER ATION (9/77) w a
e.
11 1
OPERATING DATA REPORT DOCKET NO.
50-296 DATE 7-1-R6 COMPLETED BY e n oe u rg TELEPHONE ?ns/77o-9955 OPERATING STATUS Browns Ferry Three Notes
- 1. Unit Name:
3"-
19R6
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
3293 1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
1052 1098.4
- 6. Masimum Dependable Capacity (Gross MWe):_
1065
- 7. Maximum Dependable Capacity (Net MWe):
- 5. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
N/A N/A_
- 9. Power Lesel To which Restricted lf Any(Netge):
- 10. Re.rons For Restrictions,if Any:
This Month Yr. to.Date Cumulative 720 4,343 81.815
- 11. Ilours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 0
0 45,360.08
- 13. Reactor Reserve Shutdown llours 0
0 5,149.55
- 14. Ilours Generator On.Line 0
0 44,194.76 0
0 0
- 15. Unit Re>ene Shutdown llours
- 16. Crow Thennal Energy Generated (MWH) 0 0
131,868,267 0
0 43,473,760 17 Gros, Electrical Energy Generated (MWH)
- 15. Net Electrical Energy Generated (MWH) 3,452
-19,764 42,114,009 0
0 54.0
- 19. Unit Senice Factor
- 0 54.0 0
- 20. Unit Asailability Factor 0
0 48.3
- 21. Unit Capacity Factor IUsing MDC Net!
- 22. Unit Capacity FactorIUsing DER Net) 0 0.
48.3 e
100 100 32.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Each):
March 1987
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Unin in Test Status tPrior to Commercial Operationi:
Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY C0\\lM ERCIA L OPER ATION (9/77)
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- i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-259 UNIT NAME One DATE 7-1-R6 June COMPLETED BY h ar e Raetiff REPORT MONTH TELEPHONE 205/729-295j__
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3 Yk Licensee 5%
Cause & Corrective N.
Date
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,g g y Event u?
o-Action to
$E j;5g Report 2r iE0 Prevent Recurrence 6
315 6-1-86 F
720 F
4 Administrative hold to resolve (Cont) various TVA and NRC concerns.
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2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain)
I-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 & Ucense Examination F-Administrative 5
G-Opeiational Error (Explain)
Exhibit I - Same Source (9/77) llother(Explain)
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i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-260 UNIT NAME Two DATE 7 1-RA REPORT MONTH. Tune COMPLETED BY h e e-Rnr11Ff TELEPHONE 9ns/790_90ss I
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E E
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jY3 Licensee
,Eg ge.
Cause & Corrective N...
Date i
3g 55 2s&
Event g7 o8 Action to f:
5 j;gg Report n mO H
j' Prevent Recurrence 1
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Administrative hold to resolve 305 6-1-86 F
720 F
4 f'
(Cont) various TVA and NRC concerns.
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6 1
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equiprnent 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 1 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit 1 - Same Source (9/77)
IIOther (Explain) 1
50-296 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
m ee UNIT NAME DATE 7-1-86 REPORT MONTH June COMPLETED BY hnt e une14ff TELEPHONE 205/729-2955 "i
.hYk h",,
.! E Licensee En Cause & Corrective E
No.
Date 5-3g 5
,3 g y Event 55
$?
Action to
$E E
j@g Report =
<N 0
}U Prevent Recurrence 6
157 6-1-86 F
720 F
4 Administrative hold to resolve various TVA and NRC concerns.
c-I.
1 I
2 3
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 Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Admipistrative 5
G Operational Error (Explain)
Exhibit I-Same Source 19/77) llother(Explain) j' t
-