ML20215C110
| ML20215C110 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/31/1986 |
| From: | Creamer K, Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8610100094 | |
| Download: ML20215C110 (16) | |
Text
.
1 TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC JULY 1, 1986 - JULY 30, 1986
(
I DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l
l Submitted by:
Plant Managef GilU gSIGiu[
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/(h 8610100094 860731 PDR ADOCK 05000259 1
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CONTENTS i
Operations Susunary.
1 Refueling Information...........................
3 Significant Operational Events......................
i.
Average Daily Unit Power Level....
6 Operating Data Reports............
9 Unit Shutdowns and Power Reductions......
. 12 l
l l
J 0033B
-... = - - -. - - -...
O 1
Operations Summary JULY 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.
U. nit 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 l
j 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 J
o 2
v Operations Sunsaary (Continued)
JULY 1986 Fatigue Usage Evaluation The cumulative usage factors far 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 9.81E+05 gallons of waste liquids were discharged containing approximately 5.39E-02 curies of activities 0033B
________=______________-_________________-____-_-__=O
O 3
v i
Refueling Information JULY 1986 j
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 pr.ocess computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG-0737), RPS modifications (IE Notice 78-45) H 0 8 ample 22 j
line modification (LER 81-050), radiation monitors modification (LER 80033),
l 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.
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 1,355 locations.
Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage 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 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 (10 CFR 50.49), torus modifications (NUREG-0661), containment modification (NUREG-0737), electrical changes (Appendiz R 10 CFR 50) (partial), NSIV modifications, modification of masonry walls (IEB-80-11), addition of feedwater nozzle temperature monitoring (NUkEG-0619), evaluation of the vent drain and test connections, VDTC, (LER-82020), valve modification (Appendix J) (partial), D/G speed sensor 00338
- _ ~ - - - -,, - - - - - - "~ ~
m
4 Refueling Information JULY 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 wera 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 available capacity of the spent fuel pool is 1164 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 of Narch 1987. 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 (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-ll), 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 78-45),
H0 sample line modification (LER 31-050), 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 change out, and plant design upgrade to seismic qualification.
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.
0033B
._=
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5 s
Significant Operational Events JULY 1986 Unit 1 07/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues.
07/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns-and end of cycle 6 refueling and modifications continues.
Unit 2 07/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
07/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
Unit 3 07/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
07/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
i l
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l 0033B 1--
- ~
--r
~
6 AVERAGE DAILY UNIT POhkR LEVEL 1
i 50-259 DOCKET NO.
UNIT One DATE 8/1/86 COMPLETED BY K. L. Creamer TELEPHONE 205/729-2960 i
MONTH July DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (M he-Net s quw,N,g3
-6 g7
-7
-6
-6
~-
y
,g 1
3
-7 to
-9
-6
~7 4
20 5
-6 2
-5
-6 22
-10 6
7
-7 33
_g
-5 1
24
-8
-8 9
25
-7
-8
-8 to
,26 11
-8 27
-7 12
-8
-8 23 T
13
-8 29
-7 14
-6
-9 30
-6
-8 15 3g I c,
- 8._.
IN1 TR11CTlONS On theJormat. list the cerg: Jaih us..t pour leselin MWe Net for exh day in the seporting month. Compute to the r.estest whole nwpwatt.
(9/77i
7 AVESAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 T'wo UNIT DATg 8/1/86 COMPLETED BY K. L. Creamer TELEPHONE 205/729-2960 MONTH July DAY AVERAGE DAILY POWER LEVEL IIAY AVERACE DAILY POWER LEVEL t%IWe.NtiI
- yweg,,3
-6
-5
.,7
-3
-1 g3 3
-5 g,
-6 4
-4 20
-4
-4 5
21
-3 6
-4 22
-3
~9
-4 7
n
-4 3
3
,4 9
-5 25
-4
~4 l
10 26
-4
-5 11 37
_4 12
~4 28
-3 13
~
-3 29
-5
~4 34 30 15
._- 3
_4
-5 l e, i
l IN5 IRtIP.ONS On it.ijoamat hs the.nerup dali uint piew6: lesel in MWe Net for each day iii Ihe reporting m.mth. Compute tu the r.enesi whole nwgawatt.
e (9/771
e 8
AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT T' ree h
6/1/86 DATE COMPLETED BY K. L. Creamer TELEPHONE ?nuv?o_?un MONTH July PAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL t.%IWc Neti (MWe Net)
~
I
.17
-5
-5
'I s
-5 s
3
-k_
19
-6
-5
-5
'O 4
5
-5
-5
-5
-5 22 7
-5 23
-5
-5
-5 g
24
-6
-5 9
25 to
-5 26
-5 II
-5 27
-5 I:
-5 28
-4 13
_-5
-4 3,
I 7
30
-4 15
-4 33
-8 le
.5,
IN5 tRt:CT10NS On th.< format,hst the very: dails usat pimt leselin MWe Net foi cach day in the reporting m mth. Coinpute to the r.earr>i whn!c megawatt.
e (9/771
9 s
OPERATING DATA REPORT 50-259 DOCKET NO.
DATE 8/1/86 COMPl.ETED BY K.
L. creamer TELEPHONE 9M /770-2955 OPERATING STATUS Nota Bron s Ferry One
- 1. Unit Name:
July 1986
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt): 1291 1152
- 4. Nameplate Rating (Gross MWe):
1065
- 5. Design Electrical Rating INet 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 Last Report, Give Reasons:
N/A
- 9. Power Level To which Restricted,lf Any/A(Net MWe):
N/A N
)
- 10. Reasons For Restrictions,If Any:
1his Month Yr. to.Date Cumulative 744 5,087 105,247 i1. Hours in Reporting Period 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 Resene Shutdown flours 0
0 168,066,787
- 16. Gross Thermal Energy Generated (MWH) 0 0
55,398,130
- 17. Gross Electrical Energy Generated (MWH)
-5,300
~-21,872 53,731,021
- 18. Net Electrical Energy Generated (MWH) 0 0
55.4
- 19. Unit Senice Factor
- 20. Unit Availability Factor 0
0 55.4
- 21. Unit Capacity Factor (Using MDC Net) 0 0
47.9 0
0 47.9
- 22. Unit Capacity Factor IUsing DER Net)
- 23. Unit Forced Outage Rate 10 0 100 32.7
- 24. Shutdowns Scheduled Oser Nc.st 6 Months (Type.Date,and Duration of Eachl:
l
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
March 1989
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY CO\\l\\lERCI A L OPER ATION N/77) r
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i 10 OPERATI G DATA REPORT
~
DOCKET NO.
50-260 DATE --8/1/86 COMPLETED BY E-T.- creamer TELEPHONE 205/729-2955 OPERATING STATUS Notes
- 1. Unit Name:
n e m_m. Ferry Two July 1986
- 2. Reporting Period:
- 3. Licensed ThermalPower(MW ):
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 Thecugh 7) Since Last Report.Give Reasons:
N/A N/A-
- 9. Power Level To Which Restricted,if Any/A -(Net MWe):
N
- 10. Reasons For Restrictions,if Any:
This Month Yr to-Date Cumulative 744 5,087 100,134
- 11. Hours in Reporting Period 0
0 55,860.03
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0
0 14,200.44 0
0 54,338.36
- 14. Hours Generator On.Line
- 15. Unit Resene Shutdown flours O
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
153.245.167 i
- 17. Gross Electrical Energy Generated (MWH) 0 0
50,771,798 l
- 18. Net Electrical Energy Generated (MWH)
-3,048
_-32,766 49,228,541
(
- 19. Unit Service Factor 0
0 54.3 0
0 54.3 l
- 20. Unit Asailability Factor l
- 21. Unit Capacity Factor (Using MDC Net).
0 0
46.2 U
U 46.2
- 22. Unit Capacity Factor (Using DER Net) 100 100 30.8
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
r December-1986
- 25. If Shut Down At End Of Report Perir. Estimated Date of Startup:
2 ti. Units in Test Status iPrior to Commercial Operation):
Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
9 11 6
OPERATING DATA REPORT DOCKET NO. 50-296 DATE R 11 /R A COMPLETED BY K'. L. Creamer TELEPHONE 705/729-2960 OPERATING STATUS Browns Ferry Three Notes
- 1. Unit Name:
- 2. Reporting Period:
Juiv 19fie 3293
- 3. Licensed Thermal Power (MWt):
1152
- 4. Nameplata 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):
M. 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 l'O. Reasons For Restrictions.If Any:
N/A This Month Yr.-to-Date Cumulative 744 5,087 82,559
- 11. Hours In Reporting Period 0
0 45.360.08
- 12. Number Of Houn Reactor Was Critical 0
0 5,149.55
- 13. Reactor Resene Shutdown Hours
- 14. Hours Generator On.Line 0
0 44.194.76
- 15. Unit Resene Shutdown flours 0
0 0
0 0
131,868,267
- 16. Gross Thermal Energy Generated (MWH) 0 0
43,473,760 I
- 17. Gross Electrical Energy Generated (MWH)
-3,846
-23,610 42,110,163 id. Net Electrical Energy Generated (MWH) 0 0
53.5
- 19. Unit Senice Factor 0
0 53.5
- 20. Unit Availability Factor 0
0 47.9
- 21. Unit Capacity Factor IUsing MDC Net) 0 0
47.9
- 22. Unit Capacity FactorIUsing DER Net) 100 100 32.9
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over 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. Units in Test Status IPrior to Commercial Operation):
Forecast Achieved INITIA L CRITICALITY INITI A L ELECTRICITY CO\\l%1ERCl A L OPER ATION N/77) m.
l 50-259 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UN8T NAME One DATE R-1-R6 COMPLETED BY
--K.
L. Creamer REPORT MONTH July TELEPHONE 205/729-2960 w.
E E
,5 g "h
4Yh Licensee jg Cause & Corrective No.
Date g
3g i;
js&
Event g?
g3 Action to 5
jgg Report a mV U
Prevent Recurrence H
g 6
315 7-1-86 F
744 F
4 Administrative hold to resolve various TVA and NRC concerns.
(Cont)
U a
I 2
3 4
i 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 Scrsm.
Entry Sheets for Licensee C Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161) l E-Operator Training & License Examination F Administrative 5
Exhibit I - Same Source G-Operational Error (Explain) 19/77)
Il-Oiher (Explain) 4 h
50-260 DOCKET NG.
UNIT SilUTIK)WNS AND POWER REDUCTIONS UNIT NAME NO DATE 8/1/86 REPORT MONTH July COMPLETED BY Y-L
va - e TELEPHONE 205/799-?qAn t
,33
'h Yh Licensee
,E*
Cause E., Co.rective ll Nii.
Date g
3g jg5 Event g?
g3 Action to j=
jisg Reporia mU O
Prevent Recurrence H
4 g
6 l
305 7-1-86 F
744 F
'4 Administrative hold to resolve (Cont) various TVA and NRC concerns.
4 U
I
'l
'l I
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-Regula ory Restriction 4-01her (Explain) 0161)
E-Operator Training & License Exa:nination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source (9/77)
Il-Other (Explain)
a 50-296 DOCKET NO.
UNIT SHUTDOWNS AND POWER REDLP310NS UNITNAME.Three i
DATE 8/1/86 lf COMPLETED BY r_ t r r.,_,
i REPORT MONTH Julv TEl.EPHONE 2_05/792-2960 i
i t
j!
.3 g 3
.h Licensee gg h%l Action to Cause & Corrective No!
Date k
3g ij
,;g g E Event g?
yO Prevent Recurrence
$5 5
g gi g Repor a vs U H
6 i
4 157 7-1-86 F
744 F
- 4 Adsninistrative hold to resolve various TVA and NRC concerns.
jI g
4 ll 5
t, i
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructions I
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 (NURI'.G.
D-Regulatory Restriction 4-Cther (Explain) 0161)
E-Operator Training & l.icense Examination
,;l F Administrative 5
l G. Operational Error (Explain)
Exhibii 1 - Same Source
]
(9/77)
Il-Other (Explain) 1 o..