ML20234B050
| ML20234B050 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/31/1987 |
| From: | Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709180246 | |
| Download: ML20234B050 (17) | |
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TENNESSEE VALLEY AUTHORITY
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0FF)CE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT
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,i MONTHLY OPERATING REPORT TO NRC l
AUGUST 1, 1987 - AUGUST 31, 1987 h
1 DOCKET NUMBERS 50-259, 50-260 AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l
1 I-Submitted by:
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P1' ant Manager j
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0709100246 07 h9
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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 Y
l
., 3
<4 Operations Sumary AUGUST 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 six reportable' occurrence and no revisions to previous occurrences reported to NRC during the month.
Unit 1 k
The unit remained on administrative hold the entire month. The unit is also
~~
undergoin6 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 J
The unit remained on administrative hold the entire month.
The unit 19 also l
l undergoing environmental qualifications to comply with NRC requirements.
i 1
W j P o.
h Operations Summary (Continued)
AUGUST 1987 l
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Fatigue Usame Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usame Factor Unit 1 Unit 2 Unit 3 i
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.
f Common System Approximately 9.78E+0S gallons of waste liquids were discharged.containing I
approximately 2.64E-02 curies of activity.
1 s
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1 2
Refueling Information AUGUST 1987 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 to ba 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 modification.s (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), postaccident evaluation (NUREG 0737), RPS modifications (IE Notice 78-45) H 0 sample 22 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 etcrage pool presently contairs 284 new assemblies, 764 EOC-6, 252 E00-5, 260 EOC-4, 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 assemblics into the core.
The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB 87-17),
environmental qualification of electrical equipment (10CFR50.49), to rus modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial), MSIV modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUHEG 0619), evaluation of the vent drain and test conr.ections, VDTC, (LER 82020), valve modification (Appendix J) (partial), D/G speed sensor f
I 3
I
R_ofueliuR Information AUGUST 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 pro 6eam review, and EEC4 carbon to stainless pipe change out.
There are 0 assemblier in the reactor vessel.
At month end there were 304 new assemblies, /64 EOC-5, 248 EOC-4, 352 EOC-3,156 EOC -2, and 132 EOC-1 assemblies in the spent fuel storage tool. The present available capacity of the spent fuel pool is 148L 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 scheduled restart date to be dete rmined.
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 (NUREC 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-tions, modification of caconry 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 1
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 81050), radiation monitor modification (LER 60033), replacement of jet pump holddown beam assemblies (IEB 80-07),
chango out of switches in SBCT (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 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 585 locations. All high density racks (HDR) have been I
installed in the pool with the exception of six.
1 4
4 Significant Operational Events AUCUST 1987 Unit 1 08/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
08/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refuejing and modifications continues.
Unit 2 08/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refuejing and
~
modifications continues.
08/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
Unit 3 08/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
08/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
5
W..
I 1
l OPERATING DATA REPORT DOCKET NO.
50-259 l
DATE 9-1-87 COMPLETED BY J. D. Crawford TELEPHONE (2)5 729-2507 1
OPERATING STATUS j
- 1. Unit Name:
Browns Ferry Unit One Noti s
{
- 2. Reporting Period: August 1987-
- 3. Licensed Thennal 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 Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A j
l
- 9. Power Level To Which Restricted,1f Any (Net MWe):
N/A
'f 10.. Reasons For Restrictions.lf Any:
N/A
]
This Month Yr..to.Date Cu'mulative I
744 5831 114,751
!!. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 0
0 59.521.38
- 13. Reactor Reserse Shutdown Hours 0
0 6,997.44
- 14. Hours Generator on.Line 0
0 58,267.26 i
- 15. Unit Reserve Shutdown Hours
'O O
O
- 16. Gross Thermal Energy Generated (MWil) 0 0
168,066,787 t
- 17. Gross Electrical Energy Generated (MWH) 0 0
55y98,130
- 18. Net Electrical Energy Generated (MWH)
-818
-11344 53,709,291
- 19. Unit Service Factor 0
0 50.77
- 20. Unit Availability Factor 0
0 50.77
- 21. Unit Capacity Factor (Using MDC Net) 0 0
44.o
- 22. Unit C.pacity Factor (U>ing DER Net!
0 0
44.0
- 23. Unit forced Outage Rate 100 100 39.32
- 24. Shutdowns Scheduled Oser Next 6 Months (Type, Date,and Duration of Eaeh):
- 25. IIShut Down At End Of Report Period. Estimated Date of Startup:
To be determined
- 26. Units in Test Status tPrior to Connnercial Operation):
Forecast Achiesed INITI \\ L CRITICALITY INill A L ELECTRICITY
'f CO\\l%1LRCI \\L OPl R.\\ llON 6
N/77 )
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OPERATING CATA REPORT I
DOCKET NO.
50-260 DATE 9-1-87 COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507-l OPERATING STATUS b l'8
- 1. Unit Name:
Browns Ferry Unit Two
- 2. Reporting Period:
August 1987 3293
- 3. Licensed Thermal Power (MW:):
1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
{
1065
- 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:
l N/A i
- 9. Power LevelTo Which Restricted.lf Any(Net MWe):
N/A F '
- 10. Reasons For Restrictions,If Any:
N/A'
~
P This Month Yr..to Date Cumulative I1. Ilours in Reporting Period 744 5831 109,638
-j 12.' Number Of Hours Reactor Was Critical 0
0 ss.A60.01
- 13. Reactor Reserve Shutdown Hours 0
0 14.200.44 i '
- 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
Isq.74s.167
- 17. Gross Electrical Energy Generated (MWH) 0 0
50.771.798
- 18. Net Electrical Energy Generated (MWH)
-4710
-19455 49.198.848
- 19. Unit Service Factor 0
0 49.96
- 20. Unit Availability Factor 0
0 49.56
- 21. Unit Capacity Factor (U3ing MDC Net) 0 0
42.13 22, Unit Capacity Factor (Using DER Net) 0 0
42,13 100 100 38.3
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration cf Each):
1.
'5. If Shut Down At End Of Report Period. Estimated Date of Startup:
To be determined j
j
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INillA L CRITICALITY INITIA L ELECTRICI rY C0\\tMERCl \\L OPI'R \\ IloN t
7
("U 7 )
i.
OPERATING DATA REPORT DOCKET NO.
50-296 DATE 9-1-87 5
. COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507-OPERATING STATUS bOI'5 I
- 1. Unit Name:
Browns Ferry Unit Three
- 2. Reporting Period: August 1987 3293
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
1152 l
S. Design Electrical Rating (Net MWe):
1065 1098.4
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
10M 8.~ If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report, Give Reasons:
l N/A
- 9. Power Lesel To hhich Restricted,if Any (Net MWe):
N/A
- 10. Reasons For Restrictions. lf Any:
N/A i
1 i
This Month Yr..to.Date Cumulative
- 11. Ilours in Reporting Period 744 5831 92063
- 12. Number Of flours Reactor Was Critieal 0
0 45,306.08 j
- 13. Reactor Resene Shutdown llours 0
0 5.149.55
- 14. Ilours Generator On.Line 0
0 44,194.76
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Cross Thermal Energy Generated (MWil) n n
131.868.267 j
- 17. Gross Electrical Energy Generated (MWil) 0
- 18. Net Electrical Energy Generated (MWil)
-4955 _, _,,
0 43,473.760
-34057 42,058,071
- i
- 19. Unit Service Factor 0
0 48.0
- 20. Unit Availability Faetor o
n 48.0 I
- 21. Unit Capacity Factor (Using MDC Net) 0 0
42.9 l
- 22. Unit Capacity FactorIUsing DER Net) 0 0
42.9 l
- 23. Unit Forced Outage Hate 100 100 41.34
- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date,and Duration of Each):
1
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
Tn ho aneneminna
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA L CRillCA LITY INITIA L ELECIRlCITY COMMERCIAL OPI R A IlON I
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3 8
F)/77 )
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AVERAGE DAILY UNIT POWER LEVEL 1
DOCKET NO.
50-259 WIT
.One.
DATE 9-1-87 l
COMPLETED BY J. D. Crawford TELEPHONE
-(205) 729-2507~
MONTH August 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL -
IMWe Net) iMWe Net) -
1
-1 17
-1
-I
-1 3
18 q
-I
-I 3
19 4
-l 20
-l 5
-1 2l
-1
-I
-1 6
n s
i 7
-1
-l 23 j
g
-1
-l 24 9
-1 25
-l j
10
-1 26 l1
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-l 37 j
-2
-1 l
,3 13
-1
-1 29 l
-1
-I 14 30 i
IS
-1
-1 3r i t, -
-1 INSTRUCTIONS l
On this fortnat.hst the nerage daily unit power levelin MWe. Net for each day in the reportuip inonth. Coinpute to the nearest whole megawait.
I 19177) 9
=_u__=___.
n.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 1
i Two UNIT
'DATE 9-1-87 COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 MONTH August DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Nett g ywe. Net )
1
-4
-10 37
~
_3
-3
-8 g3 3
-3
-7
- 9 4
-3 20
-7 5
-3
-7 yg
-4
-7 6
n s
-6
-6 7
23
-7
-6 3
24 9
-7 23
-6 10
-6 26
- 7' Ii
-7
-6 37
-8
-7 I2 73 13
-7
~7 29 1
14
-7
-7 I
30 l3
-8
-7 3;
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-9 INSTRUCTIONS On this forinat. list the average daily unit power level in MWe. Net for each day in the reponing uninth. Coinpute to I
the nearest whole megawatt.
(0177) 10 i
r AVERAGE DAILY UNIT POWER LEVEL a
l I
DOCKET NO.
50-296 i
UNIT Three 9-1 DATE l'
COMPLETED BY J. D. Crawford 1
l l
TELEPHONE (20s) 729-2507 l
MONTH Aunust 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) 1
-7 17
-5 l
I 18
-9
' l
.2
-7 i
3
-7 19
-6 4
-7
-6 20 5
-7
-6 6
-8 22
-6 s
7
-7 23
-7 8
~7
-7 24
-7
-6 9
25 10
--6
-6 26 it
-6
-7 3,
12
~7
-6 i
28 13
~7
-6 39 14
-6 30
-6 15
-6
-6 l
3;
-11 i3 INSTRUCTIONS On this format. list the average daily unit power levelist MWe Net for each day in the reportmg enonth. Compute to i
the nearest whole megawatt.
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TENNESSEE VALLEY AUTHORITY I
Browns Ferry Nuclear Plant Post Office Box 2000 l
Decatur, Alabama 35602 SEP 111987 U.S. Nuclear Regulatory Commission ATTN: Document Centrol Desk Office of Huclear Reactor Regulation Washington, D.C.
20555 Attention: Office of Management Information and Program Control i
In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260
)
50-296 BROWNS FERRY NUCLEAF PLANT (BFN) - MONTHLY OPERATING REPORT - AUGUST 1987 Enclosed is the August 1,.1987 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY
., b' f
J. G. Walker Plant Manager Enclosure cc: Mr. C. E.. Gears Mr. G. G. Zech, Director 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 Regiona1' Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 INPQ Records Center Institute of Nuclear Power Mr. Ted Marston, Director Operations Electric Power Research Institute Suite 1500 l
P. O. Box 10412 1100 Circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389
\\\\
An Equal Opportunity Employer