ML20205D229
| ML20205D229 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/31/1986 |
| From: | Robert Lewis, Ratliff S, Tanya Smith TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 0033B, 33B, NUDOCS 8608150307 | |
| Download: ML20205D229 (19) | |
Text
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TENNESSEE VALLEY AUTHORITY 0FFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC MAY 1, 1986 - MAY 31, 1986 2
I DOCKET NUMBERS 50-259, 50-260. AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:
8 7M Plar:t Manag(r w.
]
CONTENTS Operations Sununary....
1 Refueling Information.........................
3 Significant Operational Events......................
5
~
Average Daily Unit Power Level......................
8 Operating Data Reports.
11 Unit Shutdowns and Power Reductions...................
14 6
e 00338 l
1 Operations Summary MAY 1986 c
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 nine 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 i
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.
00338
2 Operations Summary (Continued)
~ '
MAY 1986 c
Fatlaue Usaae Evsluation The cumulative usage factors for the reactor vessel are as follows:
Location Usaae 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 I
I NOTE: This accumulated monthly information satisfies Technical Specification Section 6.A.17.B(3) reporting requirements.
Common System Approximately 1.02E+06 gallons of waste 11gulds were discharged containing approximately 5.49E-02 curies of activities i
I 6
i 0 i
i i
00338
3
, Refueling Information MAY 1986
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Unit 1
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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), MSIV modifications, modifica-tion of masonry walls (188-80-11), 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 (IE' Notice 78-45), H 0 sample 22 line modification (LER 81-050), radiation monitors modification (LER 80033).
EECW carbon to stainless pipe change out, and all NRC commitment items excep)
Anticipated Transients Without Scram (ATWS) modifications which is scheduled for next outage.
There are 0 assemblies in the reactor vossel. The spent fuel storage pool presently contains 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblie's. The present available capacity of the fuel pool is 1,639 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), contalnment modification (NUREG-0737), electrical changes (Appendix R 10 CFR 50) (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/0 speed sensor 0033B
4 1
Refueling Information MAY 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 were 305 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 162 locations. All old racks have been removed from the pool and new HDRs are being installed.
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 March 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), 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 sample 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), EECW carbon to stainless pipe change out, and plant design uptrade 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.
I 00338
5
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Significant Operational Events NAY 1986 c
Unit 1 05/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues.
05/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 6 refueling and modifications continues.
O e
e 4
C0338
~.
6 Sir.nificant Operational Events '
MAY 1986 Unit 2 05/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
05/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifihations continues.
9 0033B
1 7
4 e
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Significant Operational Events MAY 1986 I
Unit 3 05/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
05/31/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
a h
4 00338
., ---- c---
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11 OPERATING DATA REPORT
, DOCKET NO.
50-259 DATE 6-1-86 COMPLETED 3Y -. T. hith TEL.EPilONE 20;/729-2955 OPERATING STATUS
- 1. Unit Name:
Browns Ferry One N"I
- 2. Reporting Period:
May 1986
- 3. Licensed Thermal Power (Mht p.
3293 1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
1065
- 6. S*nimum Dependable Capacity (Gross MWe):
1098.4
- 7. Masimum Dependable Capacity (Net MWe):
1065 ts. If Changes Oecur in Capacity Ratings (ltems Number 3 Through 7) Since Last Report. Give Reasonc N/A Net MWe):
N/A
- 9. Power Lesel To which Restricted,if Anv;A N
- 10. Reasons for Restrictions. lf Any:
This Month Yr..to.Date Cumulatise 744 ll, llours in Reporting Period 3.623 103,783
- 12. Number Of flohrs Reactor Was Critical 0
0 59.521.38 13 Reactor Resene Shutdown ll.ours 0
0 6,997.44
- 14. Ilours Generator On.Line 0
_0
_58,267.26 15 Unit Rewne Shutdown lluur, 0
0 0
- 16. Crus. Thermal Energy Generated IMWil) 0
_0 168,066,787
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0 0
17 (,ross Llectrical Energ> Generated lMWil) 55,398,130 lb. Net Electrical Energy Cencrated lMwil)
-1,280
_12,456 53,744,553
- 19. Umt Senice Factor 0
0 56.1 20 Umt Asailability Faetor 0
0 56.1
- 21. Unit Capacity Factor IUsing MDC Net 3 0
0
_48.6 l
22 Unit Capseit) Factor IUsing DER Nel, 0
0
_48.6
- 23. Unis Foried Outage Mate 100 100 31.5 24 Shutdowns Scheduled Oser Nest 6 Months IType. Date,and Duration of Eacht:
l
.. If Shut Down At End of Report Period. Estimated Date of Startup:
March 1989
> Umts la Test Status IPrior to Comraercial Operation):
Forecast Achiesed I
INill A L LRillCA ti f)
INITi \\ L l L EC TRICITY i
004tMERCI \\L Opl RT flON l
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n 12 OPERATING DATA REPORT DOCKET NO. _50-260 DrTt 6-1-s6 CO3IPLETED BY
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TELEPl!ONE OPFR ATING STATUS
- 1. Unit Name: _Brcwns Ferry Two
$"te5
- 2. sterortmg Period: May 1986 3293
- 1. Licensed Thermal Power 13tht):
1152
- 4. Nameplate Rating (Grow.\\lheP
- 5. Design Electrical Rating (Net.\\tWel:
1065 re. Stasimum Dependable Capacit) (Gross SIWet 1098.4 7 \\lasin.um Dependable Capacity (Net 31We):
1065
% If Changes Occur in Capacity Ratings titems Number 3 Through 7)Since Last Repost.Gise Reasone N/A
- 9. Power Leiel To hhich Restricted.If Anv INet SlWc):
N/A N/A
- 10. Rea oni F or Restrictiom. lf Any:
This Month Yr..to.Date Cumulatise 744 3.623 98,670
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- 11. Iloun in Reporting Period 0
0 55,860.03 12 Number Of il mrs Reictor has Critical 13 Reaetor Re ene Shutdown llourn 0
0 14,200.44
- 14. Ifoun Gus.erator On Line 0
0 54.3 & 36
- 15. Uma lle ene shntdoan lluur, 0
0 0
I t.
Gro.. Ihermal Energy Gentrated 1%!Wil) 0 0
_153.245.167
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-5.951
-25.661 49 239,703 2
0 0
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- 21. Unit CJpJsil,% fJ6tur lCning $1DC Nel) 0 0
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l' int Capacity FAtor (Usmg DER Nel) 0 0
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25 If hims Down \\t 1.nd Of Report Period. Estimated DJte 4f StJrlup.
b0.E0MbOI 198b 24 Cmt. In fest
- status (Prior io Commercial Operation 3:
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13 OPERATLNG DATA REPORT DOCKET NO. 50-296
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DATE 6-1-86
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COMPLETED BY T.
Smith TELEP110NE 9nc;/790 7955 OPERATING STATUS I
Browns Ferry Three Notes
- 1. Unit Name:
- 2. Reporting Period:
May 1986
- 3. Licensed Thermal Power IMht):
3293 1152
- 4. Nameplate Rating (Gross MWe):
1065
- 5. Design Electrical Rating (Net MWe):
- 6. Mnimum Dependable Capacity IGross MWe):
1098.4
- 7. Stasimum Dependable Capacity INet MWel:
1065
- 8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Give Reasons:
N/A Net MWe):
N/A
- 9. Power Lesel To which Restricted,if Anv;A' N
- 10. Reason, For Re>trictions,if Any:
a This Month Yr. to Date Cumulatise l
- 11. Hours in Reporting Period 744 3.623 81,095
- 12. Number OfIlours Resetor has Critical 0
0 45,360.08
- 13. Reaetor Rewne Shutdown flours 0
0 5,149.55
- 14. ilours Generator On-Line 0
0 44,194.76 li. Unit Newne Shutdown llours 0
0 0
- 16. Cron 1hermal Energy Generated tMhth 0
0 111.868.267 l' Gross Electrical Energy Generated iMhlh 0
O
...43 473.760 lb. Net Elvetrical Energy Generated IMhit)
-3.514
-16.312 42,119,695
- 19. Unit Service Factor 0
0 54.5 20 Umt Asailabdity Faetor 0
0 54.5 21 Unit rapacity Faetor IUning \\lDC Net) 0 0
48.8 22 Uno rapan) FictorIUsing HI:R Net) 0 0
48.8
- 23. Unit Forced out.ip Hate 100 100 31.4
- 24. Shutdowns Scheduled oser Nest 6 Monthil Ty pe. Dale.and Duration al l a h r
- 25. If Shut Down At Emi of Reimat Period. Estimated Date of Startup:
Flarch 1987
- 26. Umts in Test StatuilPrior to Commercial 0perationi:
Forecast Achiesad INITIA L CRlilCAl.IIY INITI \\L El.FCTRICITY l
COM\\lERCl \\L OPE R A TION i
19/77)
DOCKEl NO.
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e TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 JUN 2 71986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, D.C.
20555 Gentlemen:
Enclosed is the May 1986 Nonthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY
/ eh&
Ro ert L. Lewis Plant Manager Enclosure cc: Director, Region II INPO Records Center Nuclear Regulatory Comunission 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 Commissier Washington, D.C.
20555 (10 copies)
Mr. A. Rubio, Director Electric Power Research Institute P. O. Fox 10412 Palo Alto, California 94304
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An Equal Opportunity Employer
- - _. _ - _ _