ML19325F207
| ML19325F207 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/31/1989 |
| From: | Newburgh G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-13714, NUDOCS 8911170021 | |
| Download: ML19325F207 (5) | |
Text
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mM o.n.,.i on,c... s.io n sir..i. 8.mn. conn.cucui E.7[Y2=,$sNE=~
P,0, BOX 270 w w o,.n,cm.=
HARTFORD, CONNECTicVT 061410270 k
1 J ~[,,,,I[$1'U~.
G03) 605-5000 t
ibvember 9,1989 MP-13714 Re:
10CrR50.*ll (a)
U.S Nuclear Regulatory Comission Document Control Desk Washington, D.C.
20555 Feference:
racility operating License DPR-23 Docket No. 50-245
Dear Sir:
In accordance with Millstone Unit 1 Technical Specification 0.9.1.6, the following monthly operating cata report !cr Millstone Unit 1 is enciesed.
One additional copy of the report is enclosed.
Very truly yours, t
NORTHEAST NUCLEAR ENERGY COMPANY i
.w ax44.
i Ste.en Scace Station Superintendent Millstone Nuclear Power Station SES/GSN:d1r f
U Enclostres:
(4) i ec:
W. T. Russell, Regional Administrator Region I
[
M. Boyle, NRC Project Manager, Millstone Unit No. 1 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 l
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AVERAGE DAILY UNIT POWER LEVEL
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L DOCKET NO.. 50-245
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UNIT Millstone 1 l
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DATE 891103 o
llpy s COMPLETE BY G. Newburgh
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' TELEPHONE (203) 447-1791 l
Extension 4400 l
MONTH Oct ober, 1989 l
[C DAY AVERAGE PAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' i
(M'Ae-Net)
(MWe-Net) 1 1
655 17 657 i
i
- 2 L62 18 658
-i I 654 19 277 4
'655 20 0
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5' 657-21 0
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655 22 0
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657 23 0
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'657 24 173 s
9 658 25 598
.j 10.
658-26 657 j
11 657 27 659
f 12.
652' 2B 659 t
13-658 29 687 14 657 30 660 I
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'15 658 31 659 i
16' 658 i
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INSTRUCTIONS l
i On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Computer to the nearest whole megawatt.
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- - - - - = - - - - - - - - -
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. OPERA'IING DATA REPCRT y
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DOCKET NO. 50-245 I
- DATE #91101
'C04PLETED BY G. Newburnh 1
3 LEPHCNE. G03) 447-1791
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Extension 4400 p.
'QPERhTING STA'!US
~1.
Unit Name: Millstone 1 Notes:
- Change to Eastern
' 2.
Reporting ieriod: October,1989
. Standard Timt
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3.
Licensed Thennal Power Dett): 2011
.i b
4.
Nameplate Rating (Gross lete): 662 f
,, ;5.
Design Electrical Rating (Net 190e): 660
.'6k Maximm Dependable. Capacity (Gross lee): UT
- *l,
. Maximum Dependable Capacity. (Net 196e) : "TET g,
B.
If Changes occur in Capacity Ratings (Items Number 3 Threpph 7)
Since Last Report, Give Reasons:
N/A V,
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9.
Power Level to Which Restricted, If Any (Net !$6e):
N/A j
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- 10.. Reasons For Restrictions, If Any:
N/A i
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3
, 11$. Hours In Reporting Period
- 745 7296 165,888 n
'18., N mber of Hours Reactor Was Critical 663.5 5913.3 130,900.9 N
13.: Reactor Reserve Shutdown Hours 0
0 3,283.3
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- -14.' Hours Generator On-Line' 629.2 5815.7 127,612.8
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h 15.- ! Unit Reserve Shutdown Hours 0
0 93.7 I
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.16. ; Gross Thermal Energy Generated (MfH) 1,230,234 11,329,715~
238,514,376 L 1*1... Gross Elec. Energy Generated 04fH) 420,200 3,866,600 BO,430,196 18 '. Net Electrical Energy Generated 09fH).
402,179 3,693,264 76,743,704 j
- 19. ' Unit Service Factor 84.5 79.7 76.9
- 20.. Unit Availability raetor 84.5 79.7 77.0
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c 21. > Unit Capacity. Factor. (Using LOC Net) 82.5' 77.4 70.7 f
- 22. Unit Capacity Tactor (Using DER Net) 81.8 76.7 70.1 l
23 ~ Unit Torood Outage Rate 15.5 3.6 10.4 j
~
24., Shutdowns Sebeduled Cver Hext 6 Honths (Iype, Date, and Duration of Each):
1
.N/A
- 25. :If Shutdown at End of Report Perios, Estimated Date of Startup:
N/A j
- 26..,. Units in ' test Status (Prior to Ccrnercial Operatien):
Porcast Achieved j
.s.,
INITML CRITICALITY N/A N/A i
i; INITIAL ELECTRICITY N/A N/A CCH4ERCIAL OPERATION N/A N/A I
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4-DOCKET N0. 50-245
$k UNIT SHUTDOWNS AND POWER REDUCTIONS ~
UNIT NAFE Millstone 1 DATE 891101 COMFLETED BT G. Newburgh REPORT MONTH _ October, 1989 TELEFNONE (203) 447-1791 -
.c Extension 4400 No.
Date Type Duration Reason 2 Method of Licensee System Component Cause & Corrective.
l (3ours)
Shutting Event Codei Code 5 Action to Down Reactor 3 Report f Prevent Recurrence 89-08 891019 F
115.8-A/H 3
89-021 SJ FCV A bolt from the feedwater pump discharge.
check valve had become lodg=d in the "A" Feedwater Regulating-Valve, causing it to remain in the full open position while returnir g tha "B" Feodwater Regulating Valve to service. This condition caused a high reactor water level turbine trip signal and subsequent reactor scram. A design change to improve the-lock bolt anti-rotation assembly for the seat ring on the chack valves, was implemented to prevent recurrence.
IF: Forced 2 Reason:
3 Method:
- Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee-C-Refueling 3-Automatic Scram Event Report (LER) pile D-Regulatory Resta'ction 4-Continued from (NUREG-0161)
E-Operator Training.& License Examination previous rvanth F-Administrative 5-Fower Reduction-5 Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration = 0)
H-Other (Explain) 6-Other (Explain) 4 e
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RETUELING INFORMATION REQUEST
)
- 1..
Name of facility: Millstone 1 t
2.
Scheduled date for next refueling shutdown: March 1991 3.
Schedule date for restart following refueling: April 1991 h~'
4.
Will refueling or resumption of operation thereafter require a.
f technical specification change or othe: license amendment?
i p
p Yes, Technicial Specification Changes Regarding:
(1) Maximum Average Plenar Linear Heat Generating Kate i
(2) Maximum Critical Power Ratio
(:
,5.
Scheduled da'te(s) for submitting licensing action and supporting
{
g information:
.i Winter 1990-91 j
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance 3
analysis methods, significant changes in fuel design, new operating c
procedures:
j 196 GEBB ruel Assemblies i
- 1.
The number of fuel assemblies (a) in the core and (b) in the' spent fuel storage pool:
E
.. t (a)
.In Core:
(a) 580 (b) 1928 j
l 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 o' fuel assemblies:
?
t Present' capacity, 3229 assemblies
-f The projected date of this last refueling that can be discharged to the j
9, spent fuel pool assuming the present licensed capacity:
[
p a
E 19B*l, Spent Fuel Pool, Full Core Off Load Capability is Reached I
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