ML20050F845
| ML20050F845 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 10/02/1981 |
| From: | Newburgh G NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20050F837 | List: |
| References | |
| NUDOCS 8204130392 | |
| Download: ML20050F845 (7) | |
Text
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AVERAGE D ALLY UNil POWER LEVEL DOCKET NO.
50-245 Millstone 1 UNIT 810210 DATE COMPLETED BY G. flewburgh TELEPil0NE (203)447_1791 X 4400 MONE SeDtember DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) j 588 543 37 2
588 18 465 589 3
19 E89 4
544 589 20 0
588 s
2r 22 589 262 7
23 589 551 594 g
24 586 9
25 593 to 587 593 26 587 is 27 592 587 3 ^,
28 592 587 594 g3 29 14 281 591 30 N/A _________________
IS 3
I6 251 INSTRUCTIONS On this format,hst the average daily unit power levelin MWe. Net for each day in the reporting miinth. Compute to the nearest whole megawatt, MDC of 654 based on commitment to New England Power Exchange.
(9/77I 8204130392 011013 PDR ADOCK 05000245 R
PDR 9
e September 1981 Operating History September 1, 1981 Reactor power at 100%
September 4, 1981 2100 Hours Decreasing reactor power to shutdown for main turbine balancing.
2355 Hours Generator off line.
September 7, 1981 2356 Hours Reactor critical, rod 18-15, notch 6, period 114 sec., moderator temp. 230 F.
September 8, 1981 0711 Hours Generator on line.
September 8, 1981 1800 Hours Reactor power at 10C%.
September 14, 1981 1131 Hours Reactor scram due to low scram air header pressure caused by spurious ATWS system isolation.
2225 Hours Reactor critical, rod 38-39, notch 6, period 238 sec., moderator temp 470 F.
September 15, 1981 1057 Hours Reactor scram due to IRM Hi-Hi flux.
2150 Hours Reactor critical, rod 18-31, notch 4, period 163 sec.,
Moderator temp. 453 F.
September 16, 1981 0528 Hours Generator on line.
September 17, 1981 1600 Hours Reactor power at 100%.
September 18, 1961 0045 Hours Reactor power at 40% for main condenser repairs.
2030 Hours Reactor power at 100%.
September 23, 1981 0015 Hours Reactor power at 90% for turbine stop valve testing and main condenser backwashing.
0117 Hours Reactor power at 100%.
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September 30, 1981 0015 Hours Reactor power at 90% for turbine stop valve testing and main condenser backwashing.
0150 Hours Reactor power at 100%.
e 4
9
OPERATING DATA REPORT DOCKET NO.
50-245 DATE 810902 G. Newburgh
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COMPLETED BY(203) 447-1791 TELEPHONE X4400 OPERATING ST ATUS
- 1. Unit Name:
Millstone Unit 1 Notes
- 2. Reporting Period:
August, 1981 (Corrections)
- 3. Licensed Thermal Power (MWt):
2011
- 4. Nameplate Rating (Gross MWe):
662
- 5. Design Electrical Rating (Net MWe):
660
- 6. Maximum Dependable Capacity (Gross MWe):
684 j
654
- 7. Masimum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Gise Reasons:
N/A N/A l
- 9. Power Level To Which Restricted.lf Anv (Net MWe):
595 MWe
- 10. Reasons For Restrictions.If Any:
Main turbine complete 14th stage removal.
This Month Yr.-to.Date Cumulatise II. Hours In Reporting Period 744 5831 94,295
- 12. Number Of Hours Reactor Was Critical 672.4 1916.4 68,375.4
- 13. Reactor Reserve Shutdown Hours 0
1248.5 2,775.8 l
- 14. Hours Generator On Line 656.4 1728.9 65.855.1
- 15. Unit Resene Shutdown Hours 0
0 26.5
- 16. Gross Thermal Energy Generated (MWH) 1.278.019 3.176.646 117.606.773
- 17. Gross Electrical Energy Generated (MWH) 393.600_,_.
975,300 39,771,196
- 18. Net Electrical Energy Generated (MWH) 373.447 910.902
- 37.940.856
- 19. Unit Senice Factor 88.2 29.7 69.8
- 20. Unit Asailability Factor 88.2 29.7 69.9
- 21. Unit Capacity Factor (Using MDC Net) 76.7 23.9 61.5
- 22. Unit Capacity Factor (Using DER Net) 76.1 23.7 61.0
- 23. Unit Forced Outage Rate 11.8 46.2 16.6
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):
N/A N/A
- 25. If Shut Down At End Of Report Period. Estimated Date af Startup:
N/A
- 26. Units in Test Status IPrior to Commirc~ial Operationi:
Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY N/A COMMERCI A L OPER ATION August corrections due to mathematical errors (9/771
OPERATING DATA REPORT DOCKET NO.
50-245 DATE 810210
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COMPLETED BY(G. Newbura TELEPHONE 203) 44/-I791 X4400 OPERATING STATUS Millstone Unit 1 Notes
- 1. Unit Name:
- 2. Reporting Period:
September, 1981
- 3. Licensed Thermal Power (MW ):
2011
- 4. Nameplate Rating (Gross MWe):
662
- 5. Design Electrical Rating (Net MWe):
660
- 6. Maximum Dependable Capacity (Gross MWe):
684
- 7. Maximum Dependable Capacity (Net MWe):
654
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gise Reasons:
N/A N/A
- 9. Power Lesel To Which Restricted.lf Any (Net MWe):
595 MWe IG. Reasons For Restrictions,1f Any:
Main Turbirie complete 14th stage removal This Month Yr..to.Dat e Cumulatise
- 11. Hours in Reporting Period 720 6551 95,015
- 12. Number Of Hours Reactor Was Critical 698.2 2614.6 69,073.6
- 13. Reactor Reserve Shutdown Hours 0
1248.5 2.775.8
- 14. Hours Generator On.Line 622.8 2351.7 66,477.9
- 15. Unit Reserve Shutdown Hours 0
0 26.5
- 16. Gross Thermal Energy Generated (MWH) 1.198.531 4.375.177 118.805.304
- 17. Gross Electrical Energv Generated (MWH) 3 70.100_....
1.346.000 40.141.896
- 18. Net Electrical Energy Generated (MWH) 351.493 1.262.395 38,292,349
- 19. Unit Service Factor 86.5 35.9 70.0
- 20. Unit Asailability Factor 86.5 35.9 70.0
- 21. Unit Capacity Factor (Using MDC Net) 74.6 29.5 61.6
- 22. Unit Capacity Factor (Using DER Net) 74,0 29.2 61.1
- 23. Unit Forced Outage Rate 13.5 40.2 16.6
- 24. Shutdowns Scheduled Over Nest 6 Months (T pe. Date.and Duration of Each):
3 N/A
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
N/A
- 26. Units in Test Staeus (Prior :o Commercial Operation):
Forecast Achiesed i
INITI A L CRITICA LITY INITI A L ELECTRICITY N/A CO4tMERCI AL OPER ATION 08/77)
UNIT SliUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-245 UNIT N AME Millstone i DATE 811007 REPORT MONTH 5eptember COMPLETED BY G. Newburah LEPHONE (203) 447-1791 X4400
}?
3 h.E k Licensee P,
Cause & Corrective No.
Date 3,
3g j
jg5 Event
~g
- o. 3 Action to f:
~@=
Report a mV 5'
Prevent Recurrence.
H g
u e
c 11 810905 S
55.2 B
1 N/A HA TURBIN Shut down to balan~ce main turbine 12 810914 F
42 A
3 N/A IA ZZZZZZ Power surge to A.T.W.S. system causing scram air header to depressurize i
2 3
4 F: Forced Reason:
Mr' bod:
Exlubit G Instructions S. Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data ll Maintenance of Test 2 Manual Scram.
Entr> Sheets for Licensee C Refueling 3-Automatic Scram.
Event ReporI (LLR) File (NURLG.
D-Regulatur> Restriction 4 Other (Explain) 0161) li-Operator Training & l.acense Examination F Administrative 5
=
G-Operational Enror (Explain)
(9/77)
Exhibis 1 - Same Sourec Il-Othes (Explain) 9
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' f,*.
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REFUELING I;;r0RMAT10n REQUEST 1.
Name of facility:
Millstone 1 2.'
S'cheduled date for next refueling shutdown:
Fall 1982 3.
Scheduled date for restart foll,ouing refueling:
Winter 1982 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
Technical Specification changes regar'ing:
d (1) Maximum average planar linear heat generating rate
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(2) Maximum critical power ratio 5.
Scheduled date'(s) for submitting proposed licensing action and supporting in formation: _
Summer 1982 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unrevieued design or performance analysis methods, significant changes in fuel design, new operating procedures:
172." Retrofit" 8 X 8 fuel ass'emblies are s'cheduled for insertion in Cycle 9 (Reload 8) 7.
The number of fuel assenblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
580 (b) In SFP:
954 8.
The present licensed spent fuel pool storage capacity and the size of any in-crease in licensed storage capacity that has bee'n requested or'is planned, in l
nurber of fuel assemblies:
2184 Assemblies l
9.
The projected date of the last refuelino that can be discharged to the spent
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fuel pool assuming the prese'nt. licensed capacity:
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1985, Spent fuel Pool, full core off load capability is reached.
1991, Core Full, spent fuel pool contains 2120 bundles hkH:rmj e