B16150, Monthly Operating Rept for Dec 1996 for Millstone Nuclear Power Station Unit 1
| ML20133M579 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1996 |
| From: | Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B16150, NUDOCS 9701220437 | |
| Download: ML20133M579 (6) | |
Text
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"N , Northeast siai, ion, otrm . nor.,1 erry na., woierrora. er
./p/ p Utilitics System i,.o. n.. 128 Waterrord, CT 06381-0128 r (20'3) 447 179i January 15,1997 i
Docket Nos. 50-245 B16150 Re: 10CFR50.71(a)
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 i i
Millstone Nuclear Power Station, Unit No.1 ;
Facility Operating License No. DPR-21 Monthly Operating Report I
in accordance with the reporting requirements of Technical Specification Section 6.9.1.6 for Millstone Unit No.1, enclosed is the monthly operating report for the month of December 1996.
Very trt?, yours, NORTHEAST NUCLEAR ENERGY COMPANY l
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Paul Hinnenkamp 'V I Director- Unit Operations ,
l Millstone Unit No.1 ,
L Attachments (1)
I cc: Dr. W. D. Travers, Director, Special Projects H. J. Miller, Region I Administrator S. Dembek, NRC Project Manager, Millstone Unit No.1 T A. Easlick, Senior Resident inspector, Millstone Unit No.1
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4 9701220437 961231 .
I PDR ADOCK 05000245 , s l R PDR mm. uv. i..s l
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l Docket No. 50-245 B1615Q 1
l Attachment 1 Millstone Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report- December l
i i January 1997 i
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OPERATlWG DATA REPORT UNIT NAME Mil! stone Unit 1 ~
DATE 1/8/97 ~ - - ~ ~
COMPLETED BY G. Newkurgi{
TELEPHONE (860)444_5730 _ _
OPERATING STATUS
- 1. Docket Number 50-245 ~
- 2. Reporting Period Decenibei~1996 ~~ Notesi~~ ---~~ ~'
- 3. Utility Contact ~G. Newburgh ~ ~ ~ ~ ~~
- 4. Licensed Thermal Power (MWt): ~~~ 2011~-'
- 5. Nameplate Rating (Gross MWe): ~ ~662 ~ ~ ~ ~
- 6. Design Electrical Rating (Net MWe): 660
- 7. Maximum Dependable Capacity (Gross MWe): ,__ _____670 _ _ _ ___
_g
- 8. Maximum Dependable Capacity (Net MWe): __ 641 __
- 9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, j Give Reasons: '
N/A I
~ ~ ~ ~ ~ ~ ~ ~ ~
' ~ - ~ ~ ~ ~ ~ ~ ~ ~ - - ~ ~ ~ ~ ~ -
- 10. Power Level To Which' Restricted. lf any'(Net MWe):'~ - ~
0 ~
~ ~ ~ ~ ~ ~
- 11. Reasons For Restrictions,if Any: NRC Category lli FacilityfNRC Confirmatory Order requiring ~ ~ ~"
implementation of an independent corrective actiorive'nfication program; NRCr O' der requiring a third party review ~~~ ~
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of the empidyee concerns program at Millstone Statio_n[; design basis venfication response pursuant to 10CFR'O.54(f){.
This Month Yr.-To-Date Cumulative
- 12. Hours in Reporting Period 744.0 8784.0 228000.0
- 13. Number Of Hours Reactor Was Critical _ _ 0.0 _ _ _ _0 0 _ ,170529.9 l
- 14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3 1
- 15. Hours Generator On-Line __ ___0.0 0.0 _ _ 166560_.7
- 16. Unit Reserve Shutdown Hours _ _ _ _ __
, 0.0 _ _ _ _ __ _ 0.0
__ 93.7_
- 17. Gross Thermal Energy Generated (MWH) __ 0.0_. __ _
0.0 314372827.0 _
- 18. Gross Electrical Energy Generated (MWH) .
0.0 _ _
_ 0.0 _105938737.0
- 19. Net Electrical Energy Generated (MWH) -
-2254.0 ~ ~ ~ ' ~
-26402.0 101043549.0
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- 30. Unit Service Factor ~ ~ ~
~0.0 00 ^
~~73.1
- 21. Unit Availability Factor ~'0.0 -~~0.0 73.1
- 22. Unit Capacity Factor (Using MDC Net) _ ._
-0.5 _ _ _ . _-0.5 ______67.8 ,
- 23. Unit Capacity Factor (Using DER Net) _
-0.5 _ ._ -0.5 _ _ 67.1
- 24. Unit Forced Outage Rate .
,100.0 . . 1_ _00.0 _
15.7
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): ~' ~~ ~
Shutdown at time of this report
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- 26. lf Unit Shutddwn At End Of Report Period. Es'timated DMe of Startup:
l
- 27. Units in Test Status (Prior to Commercial Operation):
^ _ _ ))To be determined ~ ~ ~ '_ ]
Forecast Achieved l lNITIAL CRITICALITY N/A _ _ N/A__ __
j INITIAL ELECTRICITY N/A _ N/A ]
l COMMERCIAL OPERATION __
. _ .N/A _
N/A I 1
r UNIT SHUTDOWMS AND POWER REDUCTIONS .
DOCKET NO. 50-245 ,
UNIT NAME Millstone Unit 1 DATE 1/8/97 COMPLETED BY G. Newburah TELEPHONE (860)-444-5730 -
REPORT MONTH: December 1996 2
No. Date Type' Duration Reason Method of Licensee System Component Cause & Corrective (Hours) Shutting Event Code' Code' Action to Down Reactor' Report # Prevent Recurrence 95-10L 951213 F 744 D 4 N/A N/A N/A NRC Category lil facility; NRC Confirmatory Order requiring independent corrective action verification; NRC Order requiring third-party review of Millstone Station employee concems program; design basis verification for response to NRC pursuant to 10CFR50.54(f).
RFO activities continue.
2
' F: Forced Reason Method
- IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual
- Recommended Practices B - Mainteneance or Test 2 - Manual Scram for System Identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) 5 F - Administrative 6 - Other (Explain) IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function identifiers"
UNIT SHUTDOWNS AND POWER REDUCTIONS -
DOCKET NO. 50-245 .
UNIT NAME Millstone Unit 1 DATE 1/8/97 COMPLETED BY G. Newburgh TELEPHONE (860)-444-5730 -
REPORT MONTH: December 1996 2
No. Date Type' Duration Reason Method of Licensee System Component Cause & Corrective (Hours) Shutting Event Code' Code 5 Action to Down Reactor Report # Prevent Recurrence 95-10L 951213 F 744 D 4 N/A N/A N/A NRC Category til facility; NRC Confirmatory Order requiring independent corrective action venfication; NRC Order requiring third-party review of Millstone Station employee concems program; design basis venfication for response to NRC pursuant to 10CFR50.54(f).
RFO activities continue.
2
' F: Forced Reason Method
- IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices B - Mainteneance or Test 2 - Manual Scram for System identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) 5 F - Administrative 6 - Other (Explain) IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function identifiers"
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 UNIT: Millstone Unit 1 DATE: 1/8/97 ,
COMPLETED BY: G. Newburah l TELEPHONE: (860)444-5730 l i
l MONTH: December 1996 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
l 4 REFUELING INFORMATION REQUEST
- 1. Name of the facility: Millstone Unit 1 l 2. Scheduled date for next refueling outage: Current refuelina e ;taae started i
November 1995. Next refuelina outaae date to be determined.
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- 3. Scheduled date for restart following refueling: To be determined l 4. Will refueling or resumption of operation thereafter require a technical specification i change or other license amendment?
l Yes. however the entire scope is to be determined.
l 5. Scheduled date(s) for submitting licensing action and supporting information:
l None at this time
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- 6. Important licensing considerations associated with refueling, e.g., new or different !
fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
l 184 GE-11 fuel assemblies l
- 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage ;
pool:
l In Core: (a) 0 In Spent Fuel Pool: (b) 3068 Unconsolidated i t
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l 8. The present licensed spent fuel pool storage capacity and the size of any increase l l in licensed storage capacity that has been requested or is planned, in number of )
l fuel assemblies: l Present Capacity: Maximum 3229 fuel assembly locations l
l 9. The projected date of the last refueling that can be discharged to the spent fuel l l
pool assuming present license capacity: !
1998/1999. spent fuel pool full, core offload capacity is reached ):
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