ML20207U005
| ML20207U005 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/28/1987 |
| From: | Creamer K, Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8703240494 | |
| Download: ML20207U005 (17) | |
Text
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0 TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT i
j MONTHLY OPERATING REPORT TO NRC FEBRUARY 1, 1987 - FEBRUARY 28, 1987 DOCKET NUMBERS 50'-259, 50-260, AN'D 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
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Submitted by:
Plant Manager 0487k h
8703240494 870317 PDR ADOCK 05000259
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- CONTENTS Operations Sununary.
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i 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 O
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Operations Sununary FEBRUARY 1987 The fo11'owing sununary describes the significant operation activities during the reporting period.
In support of this sunuaary, a chronological log of i
significant events is included in this report.
There were three 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.
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9 Operations Summary (Continued)
FEBRUARY 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 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 9.5E+05 gallons of waste liquids were discharged containing approximately 1.46E-02 curies of activity.
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Refueling Information FEBRUARY 1987 Unit 1 Unit 1 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 l
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), MSIV modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test 4
connections, VDTC, (LER 82020), valve modification (Appendix J), HPCI cone' erns, 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 O sample 2
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 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 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 (10CFR50.49), torus 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 (NUREG 0619), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J) (partial), D/G speed sensor 3
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Refueling Information FEBRUARY 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 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 E0C-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 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),
H022 sample line modification (LER 81050), radfatf'on monitor modification (LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07),
change out of switches in SBGT (LER 83018), E..CW 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 installed in the pool with the exception of six.
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Significant Operational Events FEBRUARY'1987 Unit 1 02/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
02/28/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit 2 02/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
02/28/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
Unit 3 02/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
02/28/87 2400 Unit remainsuon administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
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3 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 3-1-87 CO.\\lPLETED liY K. L.- Creamer -
TELEPilONE 205--729-2960 OPERATING STAT US I. Unit Name:
Browns Ferry One Notes
- 2. Reporting Period: _ February 1987 3293
- 3. Licensed Thennal Power i\\lbt):
1152
- 4. Nameplate Rating (Grow Slwe):
- 5. Design Electrical Ratimt(Net MWel: 1065
- 6. Stasimum Dependable Capacity (Gross 31We):
1098.4 1065
- 7. Stasimum ocpendable Capacity (Net MWel:
- s. If Change, Occur in Capacity Ratin;ts titems Number 3 Thruegh 7) Since Last Report.Give Reawns:
N/A
- 9. Po scr Lesel To Which Rntricted. lf Any (Net MWe):
N/A
- 10. Reawns for Restrictions. If Any:
N/A This Month Yr..to Date Cumularise i1. Ilours in Reputting Period 672 1,416 110,336
- 12. Number 01 flours Iteietor Was Critical 0
0 59,521.38
- 13. Hractor Resene Shutdown llours 0
0 6,997.44
- 14. llours Generator On Line 0
0 58,267.26 li. Unit Resene Shutdown flours 0
0 0
Ir2 Grow Thermal Energy Generated (MWil) 0 0
168,066,787 17 Grow Electrical Energy Generated IMWH) 0 0
55,398,130 lb. Net Electrical Energy Generated (MWH)
-1863
-4,246 53,716,389
- 19. Unit Senice Factor 0
0 52.8
- 20. Unit Asadability Factor 0
0 52~.8
- 21. Unit Capacity Factor (Using MDC bet) 0 0
45.7 2.'
Unit Cap.scity Factor (Using DLR Net) 0 0
45.7
- 23. Unit forced Outage Rate 100 100 36.4
- 24. Shutdowns Scheduled (her Nest 6 Months (T3pe. Date.and Duration of Eachl:
- 25. If Shut Down At Enit Of Report Period. Estimated D.: e of Startup:
To be determined.
2rt i nits in Test Status t Prior to Commercial Operationi:
Forecast Achiesed INill \\ L ( RillCAllIY INill Al. FL E CTit! CITY l
CO\\l\\lfRCl \\ L OPl R A IION
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OPERATING DATA REPORT DOCKET NO.
50-260 DATE 1-1-87 COMPLETED BY K. L.-Creamer.
TELEPilONE 205-729-2960
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. OPERATING STAlUS
- 1. Unit Name: Browns Ferry Two Notes
- 2. Reporting Period: February 1987
- 3. Licensed Thennal Power (Mhti: 3293 1152
- 4. Nameplate Rating IGrow MWe):
- 5. Design Electrical Rating (Net MWe): 1065
- 6. Maiimum Dependabic Capacity (Gross MWe): 1098.4
- 7. Masimum 1)cpendable Capacity (Net MWel:
1065 l
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Imt Report, Give Reasons:
N/A i
- 9. Power Lesel To hhich Rntricted,if Any (Net MWe):
N/A
- 10. Reasons For Restrictions.lf Any:
N/A This Month Yr..to Date Cumulative i
- 11. Ilours in Reporting Period 672 1,416 105,223
-12. Number Of flours Reactor Was Critical 0
0 55,860.03 _
13; Reactor Reserve Shutdown Hours 0
0 14,200.44
- 14. Hour 5 Generator On Line f
0 0
54,338.36
- 15. Unit Rewrse Shutdown flours j
0 0
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- 16. Cron Thermal Energy Generated (MWH) 0 0
153,245,167 i
17 Grow Electrical Energy Generated (MWH) 0 0
50,771,798
- 18. Net Electrical Energy Generated (MWH;
-1,426
-2,896 49,215,407
- 19. Unit Senice Factor 0
0 51.7 20c Unit Availability Factor 0
0 51.7
- 21. Umt Capacity Factor (Uning MDC Net) 0 0
43.9 2.'. Unit Capacity Factor (Using DER Net) 0 0
43.9
- 23. Unit Forced Outage Rate 100 100 35.0
- 24. Shutdowns Scheduled User Nest 6 Months tType.Date,and Duration of Each):
- 25. If Shur llown At End Of Report Period. Estimated Date of Startup: To be determined.
2ti. Units in Test Status (Prior to Commercial Operationi:
Forecast Achiesed
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INITIA L CRITICALITY i
INillA1. ELECTRICITY COMMERCI AL OPERATION 7
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3 OPERATING DATA REPORT DOCKET NO.
50-296 DATE
't/1/87 COMPLETED BY K.
L. Creamer i
TELEPilONE 205/729-2960 OPER ATING S TA T US
- 1. Unit Name:
Browns Ferry Three Notes
- 2. Reporting Period:
February 1987
- 3. Licensed Thennal Power tMht):
3293
- 4. Nameplate Rating IGrow Mhe):
1152
- 5. Design Electrical Rating (Net MWe):
1065
- 6. Maiimum Derendab!c Capacity (Grow MWe):
1098.4
- 7. M.asimum 1)ependable Cap.acity INet Mhen:
1065 M. If Changes Otcur in Capacity Ratings litems Number 3 Through 7) Since I.ast Report, Give Reamns:
N/A INet MWe):
N/A
- 9. Power Leiel To Which Rntricted,If Any/A N
- 10. Reawns For Restrictions. If Any:
,I This Month Yr.-to Date Cumulative l
- 11. Ilours in Reporting Period 672 1,416 87,648
- 12. Number Of Ilours Reactor Was Critical 0
0 45,306.08
- 13. Resesor Reserve Shutdown flour 3 0
0 5,149.55
- 14. Ilours Generator On-Line 0
0 44,194.76
- 15. Unit Rewrve Shutdown flours 0
0 0
0 0
131,868,267
- 16. Grow Thtrmal Energy Generated (MWH)
I7 Gross Electrical Energy Generated (MWH) 0 _,,,,,,
0 43,473,760
- 18. Net Electrical Energy Generated (MWH)
-2453
-6031 42.086,097
- 19. Unit Sersice Factor 0
0 50.4
- 20. Unit Asailability Factor 0
0 50.4
- 21. Umt Capacity Factor iUsing MDC Net) 0 0
45.1 2.'
Unit Capacity Factor (Using DER Net) 0 0
45.1
- 23. Unit Forced Outage Rate 100 100 37.7 l
- 24. Shutdowns Scheduled User Nest 6 Months IType. Date,and Duration of Eacto:
i
- 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 Achiesed j
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INiilA L CRITICALIT Y.
i INiilAl. FLLCTRICITY i
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.WER AGE DAILY UNIT POWER LEVEL DOCKET NO.
sn-?so UNIT "One DATE ~ 3-1-87~
COMPLETED BY L L crenmar TELEPHONE 205/729-2960 MONTH February 1987 DAY.
AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL IMWe Neti IMWe Net)
-3
-2
,7 2
-2 I
-2 3
-3 19
-3
-4 4
-2 20 5
-3
-2 6
-3
-3 22 7
s 23
-4 g
-4 24
-3 9
-3 25
-3
-3 10 26
-3 ll
-4 27
-4 12
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-3 23 O
13
-2 14
-2 30 31' l
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-2 INS TRUCT10NS
'. t t t On thaformatolist the averas dail> unit emer feelin MWe. Nit for enh day in the reporting month. Compute the Oedlebt whole megawJtt.
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AVER \\GE DAILY UNIT' POhER 1.EVEL DOCKET NO.
50-260 UNIT.TWO DATE ' 3-1-87~
COMPLE1ID BY K. L. Creamer TELEPHONE 205-729-2960 MONT}{
February 1987 DAY.
AVER AGE DAILY POWER LEVEL 0AY AVER AGE DAILY POWER LEVEL (MWe NetI (MWe-Net)
-2
-2 37 l
2
-2 is
-2 3
-2
-2 g
-2
-5 4
20 5
-2
-2 6
-2
-2 22 7
-2
-2 23
-2 8
-3 24
-2 9
25
-3
-2 10 26
-3 II
-2 27
-3 12
-2 23.
-2 0
13
-2 29
-2 14 30 15
-2 31-16
-2 I.
INSTRUCTIONS On th.* format.hs the average dails uros powse feelin MWe.Nei for enh day in the reporting month. C the nearest whole megawati.
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4 WEll \\GE DAILY UNIT l'OWER 1.EVEL t
DOCKET NO.
50-296 UNIT Three DATE ' 3-1-87 COMPLETED BY K. L. Creamer TELEPHONE 70s/729-296_0
- ""#7 HONTil DAY.
AVERAGE D AILY POWER LEVEL DAY AVEft ACE DAILY POWER LEVEL (MWeNett IMWe-Net)
-9 1
17
-3 2
-4 13
-3 3
~^
19
-3 4
20
-3 5
-5
-3
-4 6
22
-3 7
-4
-3 8
24
-3 9
25
-3
-4 10 26
-3 11
-3 27
-3 i *s 23
_3 13
-3 3
la
-3 30
-3 15 16
-3 INS TRUCT10NS On th.* format.lat the averase daily tici.t ix.wst lost les MWe.Wi fut each day its she tcporting snonth.
the nearest whole negawatt.
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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-259 f
UNIT N AhtE One i
I DATE 3/1/87 COMPLETED BY K.
L.
Creamer REPORT MON TH February TELEPHONE 205/729-2960 5
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3 se e 2 _:-
E 7 E4 Licensee 5%
Cauw & Currective co
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Date B.
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4 25E Esent U?
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Report :
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Present Recursen. e di i
315 2-1-87 F
672 F
4 Administrative hold to resolve va us M and NRC concerns.
(Cont. )
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F: Forced Reason:
Methtxt:
Exhibit G - Inst ructiiwis S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data i
B-Maintenance of Test 2 Manual Scram.
Entry Sheets for 1.icensee j
C Refueling 3-Automatic Scram.
Esent ReporI (l.I'R) File (NURI G-D Regulatory Resttietion 4 Other (Explam)
/'id E-Operator Training & License Fxamination
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T F Adrmnistrative 5
G-Operational Error (Explain t Exhibit I Same Source f
19/77)
IIOther (Explaini t
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l UNIT SilDTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-260 t
j UNIT N AME Two
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DATE 1/1/87 COMPLETED BY K.
L. Creamer REPORT MONTH Fohrunrv TELEPHONE 205/729-2960
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Date
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mV Present Recuirence c:
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672 F
4 Administrative hold to resolve various TVA and NRC concerns.
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Method:
Exhibit G Instructiims S: Scheduled A Equiprnent Failure (Explain) 14fanual for Preparation of Data B. Maintenance of Test 2 Manual Scram.
Eniry Sheets for l_icensee i
C-Refueling 3 Automatic Scram.
Event Report (I.1:R) rite (NtiRI.G-i D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
Eshibit I Same Source (9/77)
HOther (Explain)
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UNIT SilUTDOWNS AND POWER REDUCTIONS DOC KET NO.
50-296 UNIT N AME Three DATE 3/1/87 COMPLETED BY -- K.
L. Crenmer REPORT MONTil February TEl.EPHONE 205/729-2960
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$ $ 5' l.icensee
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$7, Cause & Currective l
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Date 3,
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Eseni pa f-?
Action to 3 5, =$
Report (E 0 E'
Present Recurr'ence j r.
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157 3-1-87 F
744 F
4 Administrative hold to. resolve (Cont..
various TVA and NRC concerns.
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Method:
Exhibit G-Instructions
.l S: Scheduled A Equipment Failure (Explain) l Manual for Preparation of Data l
B. Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3 Autonutic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-O:hcr (E xplam) 0161)
,f E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I Same Source (9/77)
IIOther (Explain)
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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 FbV? 171987 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
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - FEBRUARY 1987 Enclosed is the February 1987 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY Robert L. Lewis Plant Manager Enclosure cc: Mr. G. 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 Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power 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 l
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