ML20211P712
| ML20211P712 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/30/1986 |
| From: | Creamer K, Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8703020419 | |
| Download: ML20211P712 (17) | |
Text
-
___=.x+-=--
-,- =--- x:.
-n x:.
b TENNESSEE VALLEY AUTHORITY I
0FFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT NONTHLY OPERATING REPORT TO NRC NOVEMBER 1, 1986 - NOVEMBER 30, 19,86 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:
Plant"Nanagef
. L
/
8703020419 861130
['
PDR ADOCK 05000259
\\
R PDR
m.=
CONTENTS Operations Susunary.
1 Refueling Information...........
3 Significant Operational Events............
5 Average Daily Unit Power Le' vel......'.........
6 Operating Data Reports.........
9 Unit Shutdowns and Power Reductions...
12 O
O e
ape e up am -
4 00278
.a.-.---------
1 Operations Summary NOVEMBER 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 repdrt.
There were one reportable occurrence 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 mont;h. 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.. _ _.
This was prepared principally by T. R. Smith.
l l
00278
_______=c___
2 Operationi Susunary (Continued)
NOVEMBER 1986 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are sa 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.
Cosenon System Approximately 19.56E+05 gallons of waste liquids sore discharged containing approximately 2.72E-02 curies of activity.
0 0027B
.c x._.
3 Refuelina Information NOVEMBER 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 refualing 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 (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-ll), 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 modifica' tion (LER 80033),
EECW carbon to stainless pipe change out, and all NRC cossaitment items except Anticipated Transients Without Scram (ATWS) modifications which is scheduled for next outage.
There are 0 assemblies in the reactor vessel. The Jpent 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 i
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 lotding 8x8R (retrofit) fuel assemblies int.o the core.
The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB-80-17),
j environmental qualification of electrical equipment (10 CFR 50.49), torus modifications (NUREG-0661), containment modification (NUREG-0737), electrical changes (Appendix R 10 CFR 50) (partial), NSIV 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 modification (Appendix J) (partial). D/G speed sensor 1
00278
4 Refueling Information NOVENBER 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 RECW carbon to stainless pipe change out.
There are 0 assemblies in the reactor vessel. At month end there were 303 new assemblies, 764 IOC-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 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 l-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 (I85-80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modifications (Appendix J), HPCI l
concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG-0737), addition of l
redundant drywell control air supply, RPS modification (IE Notice 78-45),~~~"
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), EFCW 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.
l l
00278 i
_ ES f * *,** **_ -
eem"**La~*"--****'v
- m ?r w M** ** re re m so e meewr -
" * 'r**T i'*!
- 7 7
- T,***"T"* ***,,-
_~
5 Slanificant Operational Events
~
NOVENBER 1986 Unit 1 11/01/86 0001 Unit remains on adn'inistrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
11/30/86 2400 Unit remai-ns on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit 2 11/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
11/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cye,le 5 refueling and modifications continues.
Unit 3 11/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
11/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
0027B
s
.6 AVER AGE DAILY UNIT POWER LEVEL l
50-259 DOCKET NO.
I
. UNIT One i
12-1-86 DATE i
K. L. Cremer COMPLETED BY a
TELEPHONE 205/729-2960 i
f
"*O *#
MONT}i C
l DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL
{
(MWe Nef t tMWe Net)
{
l 17
-3
-3 2
-3
-3 18 3
-3 a
-4 t
-3
-3 4
20 l
-4
-3 5
21 6
-3 4
-3 7
23
-3
-3 8
24 9
-3 25
-3
-3 10 26
-4
~
-3 gy 12
-3 29
-3
~
-3 14 30
-3 15
-3 3t 16
-3 INSTRUCTIONS t
On thi=Jormai hs: the average dail> ura: piews: lovlin MWe Net fue each day in the reporting month. Compute to the nedre51 wht)Ie inegaWJls.
e (9/77) l
~;
^-
~
7 AVER ACE DAILY UNIT POWER LEVEL 50-260 DOCKET NO.
. UNIT Two DATE 1-86 COMPLETED BY K.
L. Nenmar TELEPHONE 205/729-2960 MONTH
~
DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE D AILY POWER LEVEL IMWe Neti (MWe Net)
-3
-3
,7 2
-3
-2
~
gg 3
-3
-3 19 4
-3
-3 20 5
-3.
23
-3 6.
-3
~3
~
22
-3 *
-3 7
73
-3 a
24
-3
-3 25
~
10
~
26
-2 l1 27
-3 t
{
12
-4 28
-3 I3
-2 t
29
-3 14
~3
}1 30
-3
-3 1
15 31 n
16
-3
{
t, h
{
INSTRUCTIONS On thaformat.hst the averade daily usili powcr leselin MWe Net fut each day in the reporting month. Compute to the nearest whole megawatt.
4 fr (9/77) i
?
o 8
AVER AGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.
UNIT Three
.)
, 1-86 i
K. L. Creamer COMPLETED BY 205/729-2960 TELEPHONE November DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL IMWe Neti (MWe Net)
-4
-5 g
37
-4
-4 y
gg
-5
(
3 gg
-5 4
-6 20
-4 t
5
-8 21
-4 6
-8 22
~4
-8 7
23
-4
-8
-4 g
24 9
-8 25
-4
-8 26
-4 10
-8 II 27
-5 g;
-8
-3 28 I3 29'
-4 I4
-8 30
-4 15 "9
31 16 INSTRI'C110NS On theformat,hst the average daily useit pour leselin MWe. Net for each day in the reportmg month. Compute to the nearest whole megawatt.
(9/771 l
a,
9 4
OPERATING DATA REPORT DOCKET NO. 50-259 DATE 12-1-86 COMPLETED BY K. L. Creamer TELEPHONE 205/729-2960 OPERATING STATUS
- 1. Unit Name: Brwns Fe m One Notes wember 1986
- 2. Reportmg Period:
3293
- 3. LicensedThermalPower(MWt):
- 4. Nameplate Rating (Gross MWe):
1152.
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 Last Report.Give Reasons:
N/A N/A
- 9. Power Level To Which Restricted If An[A(Net MWe):
N
- 10. Reasons For Restrictions,If Any:
This Month Yr..to.Date Cumulative 720 8,016' 108,176 t
i1. Hours in Reporting Period 0
0 59.521.38
- 12. Number Of Hours Reactor Was Critical
- 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 Electrical Energy Generated (MWH) 0 0
55,398,130-
- 18. Net Electrical Energy Generated (MWH)
-2,380
-34,187 53,722,82.2
- 19. Unit Service Factor 0
0 53.9
- 20. Unit Availability Factor 0
0 53.9
- 21. Unit Capacity Factor (Using MDC Net) 0 0
46.6
- 22. Unit Capacity Factor (Using DER Net) 0 0
46.6
- 23. Unit Forced Outage Rate 10 0 100 34.9 s
- 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 determined.
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)
x-
-_w----.
_ =_ _ _.-
=
10 s
OPERATING DATA REPORT
.j 50-260 DOCKET NO.
- DATE 1Z-1-30 COMPLETED BY K. L. Creamer TELEPHONE 2fM/729-2960 CPERATING STATUS
'M
- 1. Unit Name:
November 1986
- 2. Reporting Pened 32E3
- 3. Licensed Thermal Power (MWt):
115L
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electncal Rating (Net MWe):
1065 1098.4
- 6. Maximum Dependable Capacity (Gross MWe):
- 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 N/A
- 9. Power Level To Which' Restricted. If A (Net MWe):
- 10. Reasons For Restrictions,If Any:
/A i
This Month Yr to.Date Cumulative 720 8,0 16 103,063
- 11. Hours In Reporting Period 0
0 55,860.03 i,
- 12. Number Of 14ours Reactor Was Critical I
- 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
~
0 0
153.245.167 l
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH) 0 0
50,771,798-
- 18. Net Electrical Energy Generated (MWH)
-2,185
-45,141 49,220,223 j
- 19. Unit Senice Factor 0
0 52.8 0
0 52.8
- 20. Unit Availability Factor 7
- 21. Unit Capacity Factor (Using MDC Net) 0 0
44.8
- 22. Unit Capacity Factor (Using DER Net) 0 0
44.8 I
- 23. Unit Forced Outage Rate 100 100 33.3 s
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date,and Duration of Each):
- 25. If Shut ihmn At End Of Report Period, Estimated Date of Startup:
To be determined.
I
- 26. Uniss in Test Status IPrior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 4
(9/77)
[
t 50-259 DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME One DATE 12-1-86 COMPLETED BY K-T-
1'ra===.r_
REPORT MONTH November TELEPHONE 205/729-2960 "e
.$ ?
3
.h.Ek Licensee Et Cause & Corrective N"-
Date h
5?
i 255 Event E$
k%
Action to,
$E 5
j di g Report
- E0 f
H Prevent Recurrence d
315 11-1-86 F
720 F
4 Administrative hold to resolve
-(Cont.'
various TVA and NRC concerns.
i U
L I
2 3
4 F: Forced Resson:
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 ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucepse Examination F-Administrative 5
Goperational Error (Explain)
Exhibit I - Same Source (9/77)
Il-Other (Explain)
-a
n-- --
- - - -, = - -
=: n; :_
c_ g- -
11 4
OPERATING DATA REPORT
~
DOCKET NO. 50-296
}
DATE 12-1-86 COMPLETED BY K.
L. Creamer TELEPHONE 205/729-2960 OPERATING STATUS
- 1. Unit Name: Browns Ferry Three Notes
- 2. Reporting Period:
November 1986 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 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( et MWe):
N/A
- 10. Reasons For Restrictions,if Any:
This Month Yr..to.Date Cumulative 720 8,016 85,488 i1. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 0
0 45,306.08
- 13. Reactor Reserve Shutdown Hours 0
0 5,149.55
)
- 14. Hours Generator On-Line 0
0 44.194.76
- 15. Unit Reserve Shutdown Hourt 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
131,868,267
- 17. Gross Electrical ninergy Generated (MWH) 0 0
43,473i760-
- 18. Net Electrical Energy Generated (MWH)
-4,298
-37,334 42,096,439
- 19. Unit Service Factor 0
0 51.7
- 20. Unit Availability Factor n
0 51.7
- 21. Unit Capacity Factor (Using MDC Net) 0 0
46.2
- 22. Unit Capacity Factor (Udng DER Net) 0 0
46.2
- 23. Unit Forced Outage Rate 100 100 35.7 s
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date.and Duration of Eacht:
- 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 Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION l
(9/77) -
4 50-2M DDCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS UNITNAME ho DATE 12-1-R6 0
{
COMPLETED BY r.
- v. _ cr.._,
REPORT MONTH November TELEPHONE 2 05 /729-? 06n l
=
c
.$ g 3
yY3 Licensee Ev,,
gg Cause A Cor,rective No.
Ihre
(
3g s
25E Event p
g}
6.
Action to, E
$E 5
} p,i g Report a mu Prevent Recurrence H
6 305 11-1-86 F
720 F
4 Administrative hold to resolve (Cont.:
various TVA and NRC concerns.
~
U 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 Scra..
Event Reporn (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucepse Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit 1 - Same Source (9/77) 1101her (Explain)
i i
i 50-296 i
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNITNAME Three DATE 17-1 M November COMPLETED BY K.
L. Creamer REPORT MONTH TELEPHONE 205/729-2960
'i 1
w.
J b
j
,5 g 3
j.E5 Licensee Eg g.
Cause & Corrective
/
No.
Ihte g
3g s
yg&
Event p
g{
Action to, f:
5 j di g Report a mO H
Prevent Recurrence j
6 G
157 11-1-86 F
720 F
4 Administrative hold to resolve
- Cont.)
various TVA and NRC concems.
7 2
i 1
..I 1
'.i 4
}
.t 1
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-Refueli.sg 3 Automatic Scram.
Event Repor (LERI File (NUREG-f D-Regulatory Restriction 4-Other (Explain) 0161)
EOperator Training & Ucepse Examination F-Administrative 5
Goperational Error (Explain)
Exhibit I - Same Source (9/77)
II-Other (Explain) g 4
-/.
i
.- a TENNESSEE VALLEY AUTHORITY Browns Ferry Nuc. lear Plant Post Office Box 2000 Decatur Alabama 35602 l
l DEC 111986 Nuclear Regulatory Commission l
Office of Management Information and Program Control Washington, D.C.
20555 Gentlemen:
Enclosed is the November 1986 Nonthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY bortL.Lewks Plant Manager Enclosure cc: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, Georgia 30303 (1 copy)
Atlanta, Georgia 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D.C.
20555 (10 copies)
Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 An Equal Opportunity Employer
_ _..