ML20237A122
| ML20237A122 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/30/1987 |
| From: | Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8712140272 | |
| Download: ML20237A122 (17) | |
Text
. _ _ _ _ _ _ _ _ _ _. -
t TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT i
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MONTHLY OPERATING REPORT TO NRC November 1, 1987 - November 30, 1987
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DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
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Submitted by:
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lant Manager
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1 0487k 8712140272 871130 PDR ADOCK 05000259 g p y.
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CONTENTS Operations Summary.
1 Refueling Information.
3 Significant Operational Events 5
Operating Data Report.
6 Average Daily Unit Power Level.
9 Unit Shutdowns and Power Reductions.
. 12
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o l
Operations Summary I
November 1987 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 four reportable occurrences and two revisions to previous occurrences reported to NRC during the month.
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 3
I The unit remained on administrative hold the entire month. The unit is also l
i
'. 4 undergoing environmental qualifications to comply with NRC requirements.
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1
5 Operations Suttnary (Continued)
November 1987
)
Fatigue Usage Evaluation The cum 21stive 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 0.00431 i
Feedwater nozzle 0.29782 0.21519 0.16139 l
closure studs 0.24204 0.17629 0.14360 NOTE: This accumulated monthly information satisfies Technical l
Specification Section 6.6.A.i a(3) reporting requirements.
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Common System Approximately 8.24E+05 gallons of wasto liquids were discharged containing approximately 2.94E-02 curies of activity.
I 2
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.n Refueling Information November 1987 Unit'l 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 to be determined. 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
~
(10CFR50.49), torus modification (NUREG 0661), containment modifications (NUREG'0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifications, modification 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), postuccident evaluation (NUREG 0/37), RPS modifications (IE Notice 78-45), H O sample 2y line modification (LER 81050), 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 are scheduled for next outage.
'There are 0 assemblies in the reactor vessel. The spent fuel storage pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, l
232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available capacity of the fuel pool is 1355 locations.
Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined. 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 (10CFR50.49), torus modifications (NUREG 0661), containment modification (NUREG 0737), cicetrical changes (Appendix R 10CFR50) (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 modifical,lon (Appendix J) (partial), D/G apeed sensor 3
s Refueling Information November 1987 Unit 2 (Continued) installation (LER 81004), 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 assemblics in the reactor vessel.
At month end there were 304 new assemblies, 764 EOC-5, 24H 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 1481 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 pitcad 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-tion of electrical equipment (10CFR50.49), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-tions, modification of nasonry 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 redundant drywell control air supply, RPS modification (IE Notice 18-45),
HO sample line modification (LER 81050), radiation monitor modification 2
(LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07),
change out of switches in SBGT (LER 83018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.
There are 0 assemblies in the reactor vessel. There are 764 assemblies to finish cycle 6, 248 EOC -5, 280 E00-4,124 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 585 locations. all high density racks (HDR) have been installed in the pool with the exception of six.
4
Significant Operational Events November 1987 Unit 1
~11/01/87 0001 Unit remains on administrative hold to resolve various i
TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
11/30/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit 2 11/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
11/30/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
Unit 3 11/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
11/30/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
i
t OPERATING DATA REl0R1 DOCKET NO.
50-259 OATE 12-01-87 COMPLETED BY J. D. Crawford TELEPHONE (205) 779-2507 OPERATING STATUS l Notes l
1.
Unit Name Browns Ferry Unit One l
l 2.
Reporting Period: Novrwnber 1987 l
l j
3.
Licensed Thermal Power (MWt): _3293 l
l 4.
Nancplalo Rat ing (Gross MWe): _1152 l
l 5.
Destgr. Electrical Rating (Net MWe) 1065 l
l 6.
Maximum Dependable Capacity (Gross MWe) 1098.4 l
l 7.
Maximum Dependable Capacity (Net MWe) 1065 l
l 8.
If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Repcrt, Give Reasons:
NlA 9.
Power Level To Which Reslaicted, if Any (Not MWe):
NlA
- 10. Reasons for Restrictions, If Any:
NlA This Month Yr-to-Date Cumulative
- 11. Ilours in Reporting Period 720 8016 116,936
- 12. Number of Hours Reactor Was Critical 0
0 59.521.38
- 13. Reactor Reserve Shutdown Hours 0
0 6.997.44
- 14. Hours Generator On-Line 0
0 58.267.26
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
168.066.787
- 17. Gross El,ctrical Energy Generated (MWF0 0
0 55.398.130
- 18. Net Electrical Enercy Generated (MWH)
-702
-13.489 53.707.146
- 19. Unit Service Factor 0
0 49.83
- 20. Unit Availability Factor 0
0 49.83
- 21. Unit Capacity Factor (Using MDC Net) 0 0
43.13
- 22. Unit Capacity Factor (Using DER Net) 0 0
43.13
- 23. Unit Forced Oulage Rate 100 100 40.68
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Dale, and Duration of Fach):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL. CRITICALITY INillAL ELECTRICITY COMMERCIAL OPERAll0N (9l77) y YV j
6
1 OPERATING DATA REPORT i
DOCKET NO.
50-260 l
DATE 1241-87 CO WLETED BY J. D. Crawford TELEPHONE T205) 729-2507 OPERATING STATUS l Notes l
l.
Unit Name Browns Ferry Unit Two l
l 1
2.
Reporting Period November 1987 l
l 3.
Licensed Thennel Power (Mt): 3293 l
-l z
4.
Nameplate Rating (Gross, Me): 1152 l
l.
J 5.
Design Electrical Rating (Not MWe) 1065 l
6.
Maximum Dependable Capacity (Gross MWe) 1098.4 7.
Maximum Dependable Capacity (Net MWe) 1065 l
l 8.
If Changes Occur in Capacity Ratings (items Nun 6er 3 Through 7) Since Last Report, Give Reasons:
NlA 9.
Power Level To Which Restricted, if Any (Net MWe):
NlA
- 10. Reasons For Restrictions, if Any:
NlA This Month Yr-to-Date Cumulative ll. Hours in Reporting Period 720 8016 111.823
- 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 Thennal 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)
-3.156
-32.463 49.185.840
- 19. Unit Service Factor 0
0 48.59
- 20. Unit Availability Factor 0
0 48.59
- 21. Unit Capacity Factor (Using MOC Net) 0 0
41.30
- 22. Unit Capacity Factor (Using DER Net) 0 0
41.30
- 23. Unit Forced Outage Rate 100 100 39.76
- 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 dolermined
- 26. Units in Test Status (Prior to Conenercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COpt4ERCIAL OPERATION (9l77) 7
OPERATING DATA REI' ORT DOCKET NO.
50-2 %
DATE I?-04-87 COMPLETED BY J. D. Crawford~
TELEPHONE T705T 72F 7557 OPERATING STATUS l Notes l
1.
Unit Names Browns Ferry Unit Three l
l 2.
Reporting Period: November 1987 l
l 3.
Licensed Thermal Power (MWt): 3293 l
l 4.
Nameplate Rating (Gross MWe): 1852 l
l 5.
Design Electrical Rating (Net MWe) 1065 6.
Maximum Dependable Capacity (Gross MWe) 1098.4 7.
Maximum Dependable Capacity (Net MWe) 1065 l
l 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
NlA 1
9.
Powor Level To Which Restricted, if Any (Net MWe):
NlA l
- 10. Reasons For Restrictions, If Any:
HlA This Monto Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 8016 94.248
- 12. Number of Hours Reactor Was Critical 0
0 45 306.08 a
- 13. Rom; tor Reservo Shutdown llours 0
0 5.149.55 1
- 14. Ilours Generator On-Line 0
0 44.194.76
- 15. Unit Reserve Shutdown Hours 0
0 0
l
- 16. Gross Thermal Energy Generated (MWH) 0 0
131.868.267
- 17. Gross Electrical Energy Generated (MWH) 0 0
43.473.760,
- 18. Not Electrical Energy Gonorated (MWH)
-4.014 46.583 42.045.545
- 19. Unit Sorwice Factor 0
0 46.89
- 20. Unit Availability Factor 0
0 46.89
- 21. Unit Capacity Factor (Using MDC Net) 0 0
41.89
- 22. Unit Capacity Factor (Using DER Net) 0 0
41.89
- 23. Unit Forced Outage Rate 100 100 43.01
- 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 dolormined
- 26. Units in Test Status (Prior to Cunmucial 0poration):
Forocast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY Co mERCIAL OPERAll0N (9l77) 8
n-AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-759 Unit
~One DATE 12-01-87 l
COMPLETED BY J.D. Crawford TELEPHONE (2t5)729-2507 l
MONTH NOVEMBER 1987 DAY.
AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
-1 17
-1
(
'2
-1 18
-1
]
I j
s
- 3
-1 19
-1
.j 4
-1 20
-1 l
5
-1 21
-1 6
-1 22
-1 l
7
-l' 23
-l' 8
-1 24
-1 9
-1 25
-1 l
j 10
-1 26
-1 11
-1 27 12
-1 28
-1 13
-1 29
-1 i
14
-1 30
-1 i
15
-1 31 16
-1 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the. reporting month. Compute to the nearest whole megawatt.
1 (9/77)
I 9
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 Unit Two DATE 12-01-87 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH E0VEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)
(HWe-Net) 1
-5 17
-2
-7 18
-2 2
___1 3
- 7_
19
-3 4
-7 20
-4 5
-7 21
-4 6
-7 22
-3 7
-8 23
-3 8
-7 24
-3 9
-8 25
-3 10
-7 26
-3 4
11
-8 27
-3 12
-4 28
-3 13
-4 29
-3 14
-2 30
-3 15
-2 31 16
-2 INSTRUCTIONS On this format, list the average daily unit power level in HWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) 10
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 Unit Three DATE 12-01-87 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH NOVEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
-6 17
-5 l
2
-4 18
-6 l
3
-4 19
-6 l
4
-6 20
-6 5
-6 21
-6 6
-6 22
-5 l
7
-5 23
-6 8
-6 24
-6 9
-6 25
-6 10
-6 26
-6 4
11
-6 27
-6 12
-6 28
-6 13
-6 29
-6 14
-6 30
-6 15
-6 31 16
-5 INSTRUCTIONS On this format, list the average daily unit power level in MWo-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
(9/77) 11
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1 j-TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 DEC 101987 C
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention: Office of Management Information and Program Control In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - NOVEMBER 1987 Enclosed is the November 1987 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNES E VALLEY AUTHORITY i
/
G. Walker ant Manager Enclosure ec: Mr. G. E. Gears Mr. G. G. Zech, Director 1
Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 101 Marietta St., NW, Suite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector Region II Browns Ferry Nuclear Plant Attn:
Dr. J. Nelson Grace, P.O. Box 311 Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power Mr. Ted Marston, Director Operations Electric Power Research Institute Suite 1500 P. O. Box 10412 1100 circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389 f),
f,/
/
t I
An Equal Opportunity Employer l
.