ML20206S333
| ML20206S333 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/31/1987 |
| From: | Crawford J, Creamer K, Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8704220376 | |
| Download: ML20206S333 (19) | |
Text
. - -
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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC MARCH 1, 1987 - MARCH 31, 1987 l
DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 T
l Submitted by:
Plant Manager i
l 0487k 0704220376 870331 l
pDR ADOCK 0500 9
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CONTENTS Operations Sumunary....
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 February 1987 Report.
. 15 i
I 1
1 s
Operations Summary NARCH 1987 i
l 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 five reportable occurrences and no 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 The unit remained on administrative hold the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.
1
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0 Operations Susunary (Continued)
MARCH 1987 Fatiaue Usame 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.
Common System Approximately 2.26E-02 gallons of waste liquids were discharged containing approximately 1.05E&O6 curies of activity.
t 2
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Refuelinu Information MARCH 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 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), NSIV modifications, modification of masonry walls (IE8 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 (IES 79-02/14), postaccident evaluation (NUREG 0737) RPS modifications (II Notice 78-45), H 0 sample line modification (LER 81050), radiation monitors modification (LER 80033), RECW carbon to stainless pipe change out, and all NRC cosuiltment 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, 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 i
j fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 2 items are CRD SDIV piping modification (IES 80-17),
environmental qualification of electrical equipment (10CFR50.49), torus i
modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial), NSIV modifications, modification of 4
i masonry walls (IE8 80-11), addition of feedwater nossle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections, VDTC, i'
(LER 82020), valve modification (Appendix J) (partial), D/G speed sensor i
3
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Refuelina Information MARCH 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 IECW 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 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 placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be deterinined. The sixth refueling outage has been scheduled for September 21, i
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 masonry walls (IRB 80-11), evaluation of the vent drain i
and test connections, VDTC, (LER 82020), valve modifications (Appendix J), HpCI concerns, replacement of plant process computer, seismic qualifications of piping (IE8 79-02/14), postaccident evaluation (NUREG 0737), addition of j
redundant drywell control air supply RPS modification (IE Notice 78-45),
I H0 sample line modification (LER 81050), radiation monitor modification (LER 80033), replacement of jet pump holddown beam assemblies (I88 80-07),
change out of switches in S8CT (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 164 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 l
installed in the pool with the exception of six.
I i
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4 i
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Sinnificant Operational svents MARCH 1987 Unit 1 03/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
03/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit 2 03/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and and of cycle 5 refueling and modifications continues.
03/31/87 2400 Unit remains on administrative hold to resolve various j
TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
Unit 3 03/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
03/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
l i
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l l
UNIT SHUTIMMUNS AND POWER REDUCTIONS DOCKET NO.
50-259 UNIT NAME naa DATE 4/1/87 conyLETED gy K.
L. Creamer REPORT MONTH March TELEPHONE 205/729-2960 n.
E c
3?
3 j Y3 Licensee h
h Cause & Correctise No.
Ihte h
3g s
255 Event g?
9-3 Action to.
f:
E j gi g Report =
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Present Recurrente H
6 315 3-1-87 F
744 F
4 Administrative hold to resolve (Cont.)
various TVA and NRC concerns.
e I
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructisms S: Scheduled A-Equipment Failure (Explaml 1-Manual for Preparati<m of Data B-Maintenance of Test 2-Manual Scram.
Entr> Sheets for IArmee C-Refueling 3-Automatic Scram.
Esent Report tLERlFdeINUREG-D-Regulatory Restriction 4Oher iEuplaint 0168i F@rator Training & Ikense Faamination F-Administrative 5
G-Operational Envor IE mplaini Estubit I-Same S.aurce l'8/77)
IlOher IExplain t L
a UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-260 UNIT NAME Two DATE 4/1/87 Y
REPORT MONTH March b5h2 E
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=
5?
E fEX Licensee
[v, g*7 Cause & Corrective N..
Date g
3g g
jgg Event s?
Action to
$5 5
j5g Report
}'
Prevent Recurr'ence 6
305 3-1-87 F
744 F
4 Administrative hold to resolve (Cont. )
various TVA and NRC concerns, s
I 2
3 4
F: Forced Reason:
Method:
Exhibit G Instructions 5: Scheduled A-Equipment Failure (Explain)
I-Manual for Preparation of Data B-Maintenanceof Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (l_E RI File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrati.e 5
G-Operational Error iExplain t Exhibit I - Same Source 19/77) flother (ExplainI
u t: NIT SifUTDOWNS AND POWER REDUCTIONS DO(.KET NO.
50-296 UNIT NAME Three DATE a/1/A7 CNW.D n r.
T..
cr
..r REPORT MONTH Karch TT.LEMtONE 205/729-2960 E
1E 1g 3
j [3 Licensee h
h Cauw & Corrective N.
Date t
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Event
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Atti m to.
f:
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Present Recurrente 7
o 6
157 3-1-87 F
744 F
4 Administrative hold to resolve (Cont.)
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various TVA and NRC concerns.
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3 4
F Forced Re: son:
Method:
Exhibit G-Instsuctions 5 Scheduled A Equipment Failure (Explain) l-Manual for PreparJilon of DJta B Maintenance of Test 2-Manual Scram.
Ent:) Sheets for facensee C-Refuelmg 3 Automatic Scram-Esent Repori (1.E RI File int:RI G-D-Regulatory Restriction 44ther (Explaml 0161)
E-Operator Trainmg & I; cense Esamination F Administrati.e 5
G-Operational Ferot (Explain t Eshibit I - Same Source 19/77)
IIOther (L splain t
N-L j
OPERATING DATA REPORT DOCKET NO.
50-259 DATE 4/1/87 l
COMPLETED BY J. D. Crawford TELEPHONE, orn1790-7507 OPERATING STATUS
{
- l. Unit Name.
Browns Ferry Unit One Notes
- 2. Reporting Period Harch 1987 i
- 3. Licensed Thermal Power (MWt):
3293
- 4. Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Rating (Net MWe): 1065
]
- 6. Maximum Dependable Capacity (Gross MWe):
inoa.A
- 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
- 9. Power Level To Which Restricted. If Any (Net MWe):
N/A
- 10. Reasons For Restrictions,if Any:
N/A 1
This Month Yr to.Date Cumulative i
I1. Hours In Reporting Period 744 2160 111,080 l
- 12. Number Of Hours Reactor Was Critical 0
0 -
- -59r521.38
- 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
i
- 16. Gross Thermal Energy Generated (MWH) 0 0
168,066,787
- 17. Gross Electrical Energy Generated (MWH) 0_
0 55,398,130 i
i
- 18. Net Electrical Energy Generated (MWH)
-2543
-6789 53,713,846 l
- 19. Unit Service Factor 52.4 0
0 f
- 20. Unit Availability Factor 0
0 52.4 4
i
- 21. Unit Capacity Factor (Using MDC Net) 0 0
45.4
- 22. Unit Capacity Factor (Using DER Net) 0 0
45.4
- 23. Unit Forced Outage Rate 100 100 36.9
]
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
i i
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: To be determined
- 26. Units in Test Status (Prior io Commercial Operation):
Forecast Achieved I
INITIAL CRITICALITY INITIAL ELECTRICITY f
COMMERCIAL OPER ATION 1
19/77) l 9
l AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT n~
DATE 4/1/87 COMPLETED BY J. D. Crawford TELEPHONE 205/729-2507 l
MONTH March DAY AVFRAGE D4ILY POWER LEVEL 114Y AVER AGE D4ILY POWER LEVEL IMWe Neti IMWe-Net) 1
-3 37
-4 2
-3 g3
-4 3
-3 39
-4 4
-4 20
-4 5
-3 21
-4 6
-3 22
-4 7
-3 23
-4 8
~3 24
-4 9
-3 25
~4
-3 to 26
-4 II
-1 27
-3 12
-4 28
-4 I3
-4 29
-4 14
~4 30
-2 15
-3 3g
-2 16
-4 INS mUCT10NS On th.eformat.hst the average dails unit p..ws leselisi \\lwe. Net fut each day in the r6portmg m.enth Co the redrest whole tregswatI.
01/7 7 )
10
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l OPERATING DATA REPORT
^
DOCKET NO.
50-260 DATE A/t/R7 COMPLETED BY T-D-Crawford TELEPHONE
?ns/7?o-2507 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Two Notes
- 2. Reporting Period.
March 1987
- 3. Licensed Thermal Power (MWt):
3293
- 4. Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Rating (Net MWe):
1065
- 6. Maximum Dependable Capacity (Gross MWe):
InoA.a
- 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
- 9. Power Level To Which Restricted.If Any (Net MWe):
N/A
- 10. Reasons For Restrictions.lf Any:
N/A This Month Yr to.Date Cumulative II. Hours in Reporting Period 744 2160 105.967 f
- 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
- 17. Gross Electrical Energy Generated (MWH) 0 0
50,771.798
- 18. Net Electrical Energy Generated (MWH)
-3203
-6099 49.212,204 1
- 19. Unit Service Factor 0
o qt.?
- 20. Unit Availability Factor 0
0 51.2
- 21. Unit Capacity Factor (Using MDC Nrt) 0 0
'43.9
- 22. Unit Capacity Factor (Using DER Net) 0 0
43.9
- 23. Unit Forced Outage Rate 100 100 35.5
- 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:
To be determined.
- 26. Units in Test Status iPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTftl CITY COMMERCIAL OPER ATION (9/77) 11
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I.
AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT Two DATE Al'/a7 COMPLETED BY J. D. Crawford TELEPHONE 205/729-2507 MONT11 March DAY AVERAGE DAILY POWER LEVEL IMY AVER AGE DAILY POWER LEVEL IMWr Neti IMWe Net)
-2 37
-6
-3
-7
,3 3
-?
19
-6 4
-3 20
-6
~
5 21
-6
-3
-6 g
7
-2 23
-6 g
-3 24
-6 9
-3 25
-7
~3 10 26
-6 ll
-3
-6 27 12
~3 28
-6 13
-3 29
-6 14
~2 30
-3
~
is 31 16 INSTRUCT 10NS On th.* format.hst the average dail) usat imws:levelin MWe Net fut cash day in ihr kporting in.enth. Co the reatest whole twgawatt.
(9/77) 12 h
fi t.
l p,
AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 UNIT Three DATE ' 4/l/87 COMPLETED gy i n. crawford TELEPHONE 205/729-2507 MONT11 Mareh DAY AVERAGE D i
()WER LEVEL l)4Y AVER ACE D AILY POWER LEVEL (MWe Net) 1
-3
-3 37 2
-3 gy
-3 3
-3 3
-3
-3 4
20
-3
-3 21
-3
-3 6
22 7
-2 73 3
8
-3
-3 24
-3 9
25
-2<w= === - - *
-3
-3 10 26 II
-3 n
-2
-3 28
-7 13
-3
-6 29 14
-3
-3 30 15
-3
-3 3:
16
-3 INSTRUCTIONS
8 d d' '""' l'"*68 Id'VI18' MWe Nel fut cash day in the tsporams month. Comnute tu the reare i whiil
.g3 ais e
(9/771 13
.a
s-a OPERATING DATA REPORT DOCKET NO.
50-296 DATE t./t /a7 _
COMPLETED BY r n Cr.awford TELEPHONE 2ns/729-2507 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Unit Three Notes
- 2. Reporting Period:
Mareh 1987
- 3. Licensed Thermal Power (MWt):
3293
- 4. Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Rating (Net MWe): 1065
- 6. Masimum 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 J.ast Report. Give Reasons:
n/A
- 9. Power Level To Which Restricted,if Any (Net MWe):
N/A
- 10. Reasons For Restrictions.lf Any:
N/A This Month Yr..to Date Cumulative
- 11. Hours in Reporting Period 744 2,160 88.392 f
- 12. Number Of Hours Reactor Was Critical 0
0
--45,4M.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)
A6
-8417 42.083.711
- 19. Unit Service Factor 0
0 49.9
- 20. Unit Availability Factor 0
0 49.9
- 21. Unit Capacity Factor (Using MDC Net) 0 0
44,7
- 22. Unit Capacity Factor (Using DER Net) 0 0
44.7
- 23. Unit Forced Outage Rate 100 100 38.3
- 24. Shutdowns Scheduled Over Nest 6 Months (Type.Date,and Duration of Eacht:
- 25. If Shut ihmn At End of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior io Commercial Operationi:
Forecast Achieved INiilA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION (4/77) 14
DOCKET NO.
50-760 UNIT SHUIDOWMS AND POWER REN UNIT NAME Tiso DATE 3/1/87 TM [os'h2EE&n REroRT MONTu v.hm=~
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jh-7 Licensee
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Cause & Corrective Ihte i
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2sE Ewns g?
!Li Action to.
j
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M E
j5g Report 2 mV Prevent Recurrence d
305
- 2-1-87 F
672 F
4 Administrative hold to resolve (Cont.)
various TVA and_NRC concerns.
I cl I
1 2
3 4
F: Forced Reason:
Metland:
Exlubit G-Instructiims 5-Scheduled A-Eqmpment Fadure(Esplain)
I-Manual for Preparati.m of Data B-Maintenance of Test 2-Manual Scram.
Entr) Sheets for tremee C-Refuehng 3-Automatic Scram.
Event Report iLERI File (N1: REG-D-Regulatory Restriction 44)tleer (Emptain1 01611 E4)perator Trainmg & tiense Examination F-Adnunistrative 5
G4)perational Error iExplaial Estubit I - Same Simsce r8/77)
III):her iExplaint
- Revision e
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UNIT SHUTUOWNS AND POWER REDUCHONS DOCKET NO.
5n-706 i
UfGT NAME Thr**
l DATE
't /1 / 87 l
conyLETED BY E.
L. cr.- r REPORT MONTH r k ~. '"
TELEPHONE 70s/77e-?oAn l
l
=
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E c
3?
3 j Y~
Lscensee
,E*
{*?
L Cause A Corrective l
h Ibse g
3g 4
2gy Event 37 o-Action an.
f:
E 5 ;F, =s Report mO Present Recurrence e
v l
6 l
l l
l 157
- 2-1-87 F
- 672 F
4 Administrative hold to resolve various TVA and NRC concerns.
)
e I
2 3
4 F: Forad Reason:
Method:
Exhibit C-Instructions S Scheduled A-Equipment Fadure(Emplain) 1-Manual for Preparatism of Data B-Maintenance or Test 2-Manual Scram.
Entr> Sheets for tiensee C-Refuelmg 3-Automatic Scram.
Event Report (LE RI Fde (NUREG-D-Regulatory Restriction 40ther (Etriam) 0161)
EOperator Trainmga Licenw Eununation F-Adnunestratix 5
G-Operational E: ur (Esplam)
Eshibit I - Same Source raf77)
Ilother ([splam)
- Revision E
i I
TENNEOCEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post office Box 2000 Decatur, Alabmaa 35602 APR I 41987 I
l 1
U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Office of Nuclear Reactor Regulation i
Washington, D.C.
20555 c
l Attention Office of Management Information and Program Control In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 l
50-296 BROWN 8 FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - MARCH 1987 Enclosed is the March 1987 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY L
Robert L.
is Plant Manager i
Enclosure cci Mr. G. E. Gears Mr. G. G. Zech, Director Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Conunission 7920 Norfolk Avenue 101 Marietta St., NW, Suite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector I
Region II Browns Ferry Nuclear Plant Attn Dr. J. Nelson Grace, P.O. Box 311 l
Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, suite 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power i
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 k
An Equal Opportunity Employer
- - - - - - - -