ML19344A420
| ML19344A420 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 08/06/1980 |
| From: | Howlett G NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19344A417 | List: |
| References | |
| NUDOCS 8008200270 | |
| Download: ML19344A420 (5) | |
Text
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9 Ol'ER \\ flNG D \\ TA REPORT i>ocKEIso ]50-336].bW In f E LO'IPLE TED !!Y _G,d._H.owlett 1 EL EPl!ONE.(203 L44Z-1791 OPERATING STA TUS 1
- 1. Uni N..me: - Millstone 2 No te' Items 21 & 22, cumula-
- 2. neporiing reriod: _ July 1980
~
tive are computed using a
- 3. Lic.nsd Thennal Power iMWt): - 2700 weighted average.
- 4. Nameplate Rating (Gross MWe):
909
- 5. Dnign Electrical Rating (Net MWe): 870
- 6. Masimum Dependable Capacity (Gross MWe): 895
- 7. Maximum Dependable Capacity (Net MWe):
864
$. If Chanps Occur in Capacity Ratings titems Nwnber 3 Throu;h 7)Since Last Report. Gise Reasons:
I
- 9. Power Lesel To hhich Retricted.lf Any (Net MWe):
None
- 10. Reasons For Restrictions.lf Any:
N
- one This Month Yr..to.Da te Cumulatise j
- 11. Hours In Reporting Period 744 5,111 40,319
- 12. Number OfIlot:rs Reactor Was Critical 725.6 3,908.2 28,987.3
- 13. Reactor Resene Shutdoun ifours 0
0 2,072.4
- 14. Hours Generator On.Line 718.9 3,815.6 27,635.8
- 15. Unit Resene Shutdown Hours 0
0 33T.T
- 16. Cross Thermal Energy Generated (MWH) 1.900.317 10,062,2ST-67,760,88T- ~
17 Gross Electrical Energy Cencrated lMhii) 626.950 3 W8 527-~
zi,88ET72~-
- 15. Net Electrical Energy Generated (MbH) 604,166 3,168',M F 20,9T93T-
- 19. Unit Senice Factor 96.6 74.7 68.Y Unit Availabilitv Factor 96.6 74.7 69.4
- 21. Unit Capacity Faetor iU,ing \\tDC Net, 94.0 7T 8 ~
63 2-
- 22. Unit Capacity Factor iUsing DER Net) 93.3
- 71. 3 ~
61.9
- 23. Unit Forced Outage Rate 3.4 25.3 2ED~
- 24. Shutdowns Scheduled Oser Nest 6 Months aTspe. Date.and Duration of Facht:
Refueling, August 16, 1980, 9 Weeks
- 25. If Shur Dawn At End Of Report Period. Estimated Date of St::rtup:N/A i
- 26. Units in Test Status iPrior to Commercial Ogwrationi:
Forecast Achies ed INITI \\ L CRITIC \\ LITY N/A W
INITI \\L ELEC 1 RICI fY N/A
~ TA--
N COMMERCI \\L OPER \\ IlON
_JLA_,_
_N/A_
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i 8 0082 o n gyo
AVER ACE D ALLY 1; NIT POk ER LEVEL DOCKET NO.
50-336 Millstone 2 tJNIT DATE 8/6/80 G.H. Howlett COstPLETED BY -
TELEPHONE (2031447-1791X364
.<!ONTH July 1980 DAY AVER 4GE DAILY POhER LEVEL DAY AVERAGE DAILY POWER LEVEL Of We Net) 15fWe Neti 865 858 i
37 865 857 2,
ig i
3' B22 855 19 765 845 y
4
,o 860 855 j
s
'l
~
861 855 6
22 862 855 7
23 861 857 8
9 861 857 25 423 10 26 857 11 297 27 857 12 572 858 23 13 849 858 856 858 14 3g IS 3
857 16 857 i
INSTRUCTIONS
- he r ares: $5 ul in '.:We. Net for each day in the :epvrtin;;r.onth. C m;.uie to
" e un t'u o
" h 1
.,m.,
50-336 UNIT SliUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME Millstone 2 DATE 8/6/80 REPORT MONTil July 1980 COMPLETED ay G.II.tlow l e t t TELEPIIONE (203)447-1791X364 w.
.! ?
3 Y'
Licensee Cause & Corrective No.
Date i
5g s
j55 Event gE Q
Action to f'
$ I.,
5 j di g Report #
<a U H
Prevent Recurrence c5 10 80 07 10 F
21.4 A
3 till PIPEXX Instrument air line break, causing loss of speed control to main feed pump with a subsequent loss of the feed pump resulting in a Reactor trip on Low Steam Generator Level.
i 11 80 07 12 F
3.7 A
3 Hil INSTRU lleater Drains level control problems resulted in a Main Feed Pump trip on low suction pressure with a subsequent Reactor trip on Low Steam Generator I.evel.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data Il-Maintenance of Test 2-Manual Scram.
Entry Shests for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG.
D Regulatory Restriction 4-Ot her ( Explain )
0161) 1 Operator Trainmg & License Examination F-Administ:atise 5
G-Operational Envor (Explain)
Exhibia I - Same Source (9/77) ll-Other ( E xplain)
Docket No.
50-336 Page 1 of I Date R/a/an Unit Name Mil'Istone 2 Completed By G.li. Howlett Telephone (203) 447-1791 X364 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT Report Month June 1980 DATE SYSTEM COMP 0NENT MAINTENANCE ACTION 6/2/80 Aux. Feedwater Aux, feedwater Check Valve Replaced bearing support gasket.
2-FW-128 6/5/80 eactor Protection Steam Generator Level Trans-Replaced current / current converter, mitter LY ll23A 6/12/80 Service Water Service Water Strainer L-lC Rebuilt Strainer.
6/24/80 Chemical & Volume Charging Pump P-18A Replaced packing and two (2) plungers.
Control 5/80 - 6/80 Aux. Feedwater Aux. Feedwater Auto Initiation Installed system.
W
Docket No.
50-336 Date:
August 8, 1980 Completed By: G.H. Howlett III Telephone: 203/447-1971 X364 REFUELING INFORMATION REQUEST s
1.
Name of facility:
Millstone 2 2.
Scheduled date for next refueling shutdown: August 16, 1980 3.
Schedule date for restart following refueling: September 28, 1980 4.
Will refueling or resumption of ope ation thereafter require a technical specification change or other license amendment?
Technical Specification changes will be necessary as a result of the change in fuel and safety analysis supplier.
5.
Scheduled date(s) for submitting licensing action and supporting infonnation:
The schedule for submitting license action is as follows:
Basic Safety Report 3-6-80 Additional licensing documentation in support of cycle four (4) operation will be provided in response to Nuclear Regulatory Commission staff questions.
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:
Cycle 4 will be unique in that it will be the first where the fuel and safety analysis will be supplied by Westinghouse.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)
In Core:
217 (b) 144 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
667 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1985, Spent Fuel Pool, full core off load capability is reached.
1987, Core Full, Spent Fuel Pool contains 648 bundles.
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