ML20211K521
| ML20211K521 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/31/1987 |
| From: | Creamer K, Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 0487K, 487K, NUDOCS 8702260621 | |
| Download: ML20211K521 (18) | |
Text
_
TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC JANUARY 1, 1987 - JANUARY 31, 1987 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l
l Submitted by:
A
- 11. M Plant Manag4'r 0487k 8702260621 870131 gDR ADOCK 05000259 A
4b PDR l
7
\\
\\\\\\
CONTENTS Operations Summary............................
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 October 1986 Report 15 t
4 i
i 1
i c.
~.._.-. _ -
Operations Summary JANUARY 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 three reportaDie 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.
I i
l l
l 1
l i
Operations Summary (Continued)
JANUARY 1987 Fatigue Usage 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 i
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 dystem Approximately 1.50E+06 gallons of waste liquids were discharged containing approximately 2.82E-02 curies of activity.
I C
2
Refueling Information JANUARY 1987 Unit 1 Unit I was placed on administrative hold in March 1985 to resolve TVA and MRC 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 1
)
unit 1 items are environmental qualification of electrical equipment j
(10CFR50.49), torus modification (NUREG 0661), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) i (all), NSIV modifications,
{
modification of masonry walls (IEB 80-11), evaluation of the vent drain and test 1
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 line modification (LER 81050), radiation monitors modification (LER 80033) EECW 22 carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which are scheduled
~
i' i
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 j
with a scheduled restart date to be determined.
On September 3, 1985, the unit i
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),
j environmental qualification of electrical equipment (10CFR50.49),
torus modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial), NSIV modifications, modification of j
masonry walls (IEB 80-11), aridition 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 I
I, 3
1
_ - -...., _,,. ~., _ _ _...
Refueling Information JANUARY 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 assemblies in the reactor vessel.
At month end there were 303 new assemblies, 764 FOC-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 j-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 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 masonry 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 78-45),
H0 88mple line modification (LER 81050), radiation monitor modification 22 (LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07) change out of switches in SBCT (LER 83018), EECW carbon to stainless pipe change l
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 I
locations.
C 4
Significant Operational Events JANUARY 1987 Unit 1 01/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
01/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit 2 01/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
01/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
Unit 3 01/01/87 0001 Unit remains on administrative hold to resolve various IVA and NRC concerns, and environmental qualifications and modifications continues.
01/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
I l
E 5
l 5
l
AVER A'GE DAILY L' NIT POWER LEVEL DOCKET NO. 50-259 UNIT nw DATE 2-1-87 COMPLETED BY K. L. Creamer TELEPHONE 205-729-2960 MONT11 Jan.
DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe Neil IMWe-Net) 1
-1 17
-3 2
-I is
_4 3
-3 19
-4 4
-3 20
-3 5
-3
-3
-3 6
22
-3 7
-3 23
-3
~
8
-3
- 4
-3 9
-3 25
-3 10
-1 26
-3 II
-3 37
_4
-3
-4 28 13
-3 29
-4 14
-3 33
-3 is
-1 31
-4 16
-4 E
INS TRUCT10NS On th sformat. hst the.nerage dah us.i pi. we leul in \\ lwr Nei for e.nh day in the r porting inon the nearest whnie nwgawaii.
6 (9/771 l
6
AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT N DATE 12-1-87 COMPLETED BY
_K. L. Creamer TELEFHONE 205-729-2960 MONTH hn -
DAY AVER AGE DAILY POWEP. LEVEL DAY (MWr NetI AVER AGE DAILY POWER LEVEL MweN,,g 3
-2 37
-2
-2
-2 g3 3
-2 gg
-2 4
-2 yo
-2 5
-2 yg
-2 6
-2 72
-2 7
-2 73
-2 4
-2 2.g
-2 9
-2 25
-2
-2 10 26
-2 II
-2 27
-2 1:
-2 23
-2 13
-2 29
-3 l.:
-_2 30
-1 15
-2 3:
-2 f t.
-2 IN51Rt:CP.ONS On ih.ijoamat. list the ver.p dash us.. ps.ur leselin MWc Net foi cath day in the teporti the r.earnt whole megawait.
(9/77) s 7
AYER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 ggy THREE DATE -
2-2-87 COMPLETED BY K. L. Creamer TELEPHONE 205-729-2960 MONT11 En-DAY AVERACE DAILY POWER LEVEL DAY (Mhe Neti AVER AGE D AILY POWER LEVEL (MWe Net) l
-8
-4 g7 2
-8 33
-4 3
-5 39
-4 4
-4
-4 20 5
A 21
-5 6
-4 22
-4 7
-4 23
-5 3
-4 24
-6 9
-5 23
-5 10
-5 26
-5 II
-4 27
-5 12
-4 23
-5 13
-4 29
-5 I
14
-5 30
-5 15
-4 3:
-5 16
-5 E
INSTRUCTIONS On thejoimst.lat the ascrage duh oi..t p mse leselin MWe Net for cash day in the seportm the nearest whole nxgawatt.
K (9/771 8
4 OPERATING DATA REPORT DOCKET NO.
50-259 DATE
?-1-87 COMPLETED BY K. L. Creamer TELEPflONE 205/729-2_960 OPER ATING STA1 US
- 1. Unit Name:
Browns Ferry One Notes
- 2. Heporting Period:
January 1987
- 3. Licensed Thermal Power (Mht):
3293
- 4. Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Mating (Net MWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4
- 7. Maximum Dependable Capacity (Net MWel:
- 1065
- 8. If Changes Occur in Capacity Matings (Items Number 3 Through 7)Since Last Report. Give Reasons:
N/A
- 9. Power Leiel To hhich Rotricted,if Any INet MWe):
N/A
- 10. Meawns For Restrictions. lf Any:
N/A i
This Month Yr. to.llate Cumulative II. Ifours in Reporting Period 744 744 109,664
- 12. Number Of floun Rescior has Critical 0
0 59.521.38 ~
- 13. Reactor Hewrse Shutdown Hours 0
0 6,997.44
- 14. Ilours Cenerator On Line 0
0 58,267.26
- 15. Unit Newne Shutdown floun 0
0 0
- 16. Grow Thctmal Energy Generated lMWHI O
O 168,066.787~
- 17. Grou Electrical Energy Generated (MWH) 0_,,,,,,,,,,,
0 55,398,130 lb. Net Electrical Energy Generated (MWH)
-2383
-2383 53,718,252
- 19. Unit Senice Factor 0
0 53.L
- 20. Unit Availability Factor 0
0 53.1
- 21. Unit Capacit.s Factor (Uning MDC Net) 0 0
46.0 2.'. Unit Capacity Factor (Using DER Net) 0 0
46.0
- 21. Unit Forced Out.ip Nate 100 100 35.9.
- 24. Shutdowns Scheduled User Nest 6 Months IType. Date, and llutation of fach t:
- 23. If Shut Down At Lnd Of Report Period Estimated llate of Startup:To be deterinined.
2ri. I' nits in Test Status irrior to Connnercial Operationi:
. Forecast Achiesed i
INiilA L CRiflCAI.lTY INiilA L I LLC TRICITY j
C0\\D11 RCI g1. Ol'l:R A flON 03/77) 9
OPERATING DATA REPORT DOCKET NO.
50-260 DATE 2-1-87 COMPLETED BY K. L. Creamer l
lELEPflONE 205/729-2960 l
OPERATING STATUS
- 1. Unit Name:
Browns Ferry Two Notes
- 2. Reporting Period: _ January 1987
- 3. Licen>ed Thermal Power Olbt):
3293 1152
- 4. Nameplate Rating (Gross MWe):
1
- 5. Design Electrical Rating (Net MWe):
1065
- 6. Masimum Depend.able Capacity (Gross MWe):
1098.4
- 7. Masimum Dependable Capacity (Net MWel:
1065
- 8. If Changes Occur in Capacity Ratmgs tirems Number 3 Through 7)Since Last Report. Give Reasons:
N/A l
l l
- 9. Power Lesel To Which Restricted. lf An Net MWe):
N/A l
- 10. Reasons For Restrictions. lf Any:
A 1
l This Month Yr. to.Date Cumulative
- 11. Ifours in Reporting Period 744 744 104;551 l
- 12. Number Of Ilours Reictor Wu Critical 0
0 55,860.03
- 13. Reactor Reserse Shutdown ilours U
U 14,200.44 ~
- 14. Iloun Generator Osi.Line 0
0 54.338.36 li. Unit Rewne Shutdown flours 0
0 0
- 16. Grow Thermal Energy Generated (MWil) 0 0
153,245,167 l
17 Gross Electrical Energy Generated (MWH) 0 0
50,771,798
- 14. Net Electrical Energy Generated (MWH)
-1470___,,, _
-1470 49,216.833 i
- 19. Unit Senice Facto, 0
0 52.0
- 20. Unit Availability Facto, 0
0 52.0
- 21. Unit Capacity Factor IUsing MDC Net, 0
0 44.2 l
2.'. Unit Cap.acity Factor (Uning 1)ER Net) 0 0
44.2
- 23. Unit Forceil Outage Rate 100 100 34.5.
- 24. Shutdowns Scheduled User Nest 6 Months (Type. llate.and Duratmn of Eacht:
I
- 25. If Shut llown At f.nd Of Report Period, Estunated Date of Startup: - To be determined.
24, Units in icit Status (Prior to ronunercial Operation):
Forecast Achieved INill \\ L L RillCA LII)
INiilA L 1.L LCIRICI TY E
CO\\f \\lEllCl \\ L OPI'R A flON 19/77) l0 t
4 OPERATING DATA REPORT DOCKET NO.
50-296 DATE - ')- 1 -R 7 COSIPLETED BY K.
T. Creamer TELEPilONE 205/729-2960 OPER ATING STATUS
- 1. Unit Name:
Browns Ferry Three N"I'5
- 2. Reparting Period:
January 1987
- 3. Licensed Thennal Power IN!Wt):
3293
- 4. Nameplate Rating (Gross SIWE):
1152 1065
- 5. Doign Electrical Rating (Net MWe):
- 6. Matimum Dependable Capacity (Gross MWe):
1098.4
- 7. Masimum Dependable Capacity (Net MWel:
1065
- 8. If Changen Occur in Capacity Ratings litems Number 3 Through 7) Since Last Report, Gise Rea>ons:
N/A
- 9. Power Level To Which Restricted,if Any INet MWe):
N/A LO. Reasons For Restrictium. If Any:
N/A This Month Yr. to-Date Cumulative
- 11. Ifours in Reporting Period 744 744 36,976
- 12. Number Of flours Reactor Was Critica!
0 0
45,306.08
- 13. Reactor Reserse Shutdown llours 0
0 5,149.55
- 14. Ilours Generator On.Line 0
0 44,194.76
- 15. Unit Rewne Shutdown llours 0
0 0
- 16. Grow thermal Energy Generated lMWill 0
0 131,868,267 17 Grow Electrical Energy Generated IMWHi 0
0 43,473,760
- 14. Net Electrical Energy Generated IMWil)
-3578
-3578 42,088,550
- 19. Unit Senice Factor 0
0 50.8
- 20. Unit Asadability f actor 0
0 50.8
- 21. Umt Capacity FactorIUsing MDC Neti 0
0 45.4 2.'. Unit Capacity Factor IUsing DER Net) 0 0
45.4
- 23. Unit Forced Outage Rate 100 100 37.1,
- 24. Shutdowns Scheduled Oser Nest 6 MonthslType. Date,and Duration of Facht:
E
- 25. If Shut Down At I ud Of Report Period, Estimated Date of Startup:
To be determined.
2tt Units la lest Status (Prior to CommerciJI OperJtion):
forecast Achiesed INill \\L CRillCallIY INill \\l. ! LI CTRICI TY Z
CO\\l\\ll'RL I \\ L OPI R.\\ llON P8/77) 11
l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-259 UNIT NAME ONF DATE 2-1 a7 l
REPORT MONTH Jan.
COMPLETED BY r i cem,_m.
TELEPilONE ?ns-7?o-?q6n~
l 1
E c
.5 g 3
$ E3 Licensee "c g ge, Cause & Corrective N...
Date i
3g d,4
.s g E Event p
g'E Action to, fE 5 5 =!
Report a mV o'
Pievent Recurrente 6-e u
6i 315 1-1-87 F
744 F
4 Administrative hold to resolve various (cont. )
TVA and NRC concerns.
C f
'r N
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 Scram.
Event Report (1.E!U File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
G. Operational E ror (Explain)
Exhibit I Same Source
)
(9/77) llother(Explain) 1
b P
UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAME 'No DATE 7-1-R7 REPORT MONTH Jan.
COMPLETED BY r r c..,-
TELEFIIONE. gg5 h2hl2950 E
e.
E E
]3 jY3 Licensee 3 t, Cause & Corrective No.
Date i
3g 4
.3i5 Event 3,y 9-?
Action to, l
H jE 55:
Report mO E'
Prevent Recurrence 2
0 6
305 2-1-87 F
744 F
4
~
Administrative hold to resolve (cont.
various TVA and NRC concerns.
=
-w 1
t i
2 3
4 F: Forced Reason:
Method:
Exhibit G. Instructions S Scheduled A Equiprnent Failure (Explain)
- 1. Manual for Preparation of Data B-11aintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C Refueling 3 Autom.itic Scram.
Event Report (t.Elti File t NUREG-D Regulatory Restriction 4-Other (Explain)
~
016II E Operator Training & Uecuse Esamination F-Administ rati<e 5
Goperational Error (Explain)
(4/77)
Iforher(Explaint Exhibit I - Same Source r
4'W**'
UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT NAME THRFF DATE ? t A7 COMPLETED BY K.
L.
Creamer REPORT MONTit Jan.
TELEPilONE 205-7?9-?960 c
e,
= -
Licensee gg
{%
Cause & Corrective i?
g f s.a =
~
a N..
Date i
5?
4
.255 Event 3?
E
Action to
$E E
5 5, =!
Report =
di0 EU Present Recurrence e
v 6
157 2-1-87 F
744 F
4 Administrative hold to resolve various (cont.)
TVA and NRC concerns.
T
'e w
I 2
3 4
F-Forced Reason:
Method:
Exhibit G. Inst:uctions S' Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data B-Maintenance or Test 2 Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Repor (I.ER) File int RFG-D-Regulatory Restriction 4 Other (Explain) 0161)
E-Operator Training & Ucense Examination F Administrative 5
G-Operational Error (Explain)
Estubit I - Same Source 19/77)
II4)ther (Explain)
M M
II
2 OPERATIONS
SUMMARY
(Continued)
OCTOBER 1986 Fatigue Usage 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 2"
Approximately 13.93E+05 gallons of waste liquids were discharged containing approximately
- 2.63E-02 curies of activity.
- Revision lgt 15
TENNE 5;SEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 FEB191987 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 - JANUARY 1987 Enclosed is the January 1987 Monthly Operating Report to NRC for Browns Ferry b
Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY d a
- n. 9ew!
Robert L. L hPlantManager Enclosure cci Mr. G. E. Gears Mr. G. G. Zech, Director Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Conselssion U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 101 Marietta St., W. Sulte 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Conselssion Browns Ferry Resident Inspector d
Region II Browns Ferry Nuclear Plant Attn: Dr. J. Nelson Grace.
P.O. Box 311 Regional Administrator Athens, Alabama 35611 101 Marletta Street, W. Sutto 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power Mr. Ted Marston, Director Operations Electric Power Research Instituto Suite 1500 P. O. Box 10412 1100 Circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389 yp1
't An Equal Opportunity Employer