ML20071A489
| ML20071A489 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/31/1991 |
| From: | Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-91-306, NUDOCS 9104160239 | |
| Download: ML20071A489 (5) | |
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P O. DOX 270 HART FORD, CONNECTICUT 061410270 m an n,m w a cww g
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April 9, 1991 MP-91-306 Re: 10CFR50.71(a)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Reference:
Facility Operating License No NPF 49 Docket No. 50-423
Dear Sir:
In accordance with reporting requirements of technical specifications Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 9104 covering opera-tion for the month of March is hereby forwarded.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
~ JY Q
Steph n E.Scace Director, Millstone Station Attachment cc: T.T. Martin, Region I Administrator W.J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 L-
' D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 l
0104160239 910331 PDR ADOCK 05000423 rDR g
k II i
- NRC OPERATING ST ATUS REPORT COMPLETED BY REACTOR ENGINEERING *******
1.
DOCKET.... 50 423 OPERATING STATUS 2,
REPORTING PERIOD... MARCH 1991 OUTAGE + DNLINE HOURS.. 744.0
+
0.0
= 744.0 3.
UT I L I T Y CONT ACT.,............... A. L. E LMS 203 444 5358 4 L I C E N SE D T H E R MA L P0WE R......................................... 3 41 1
- MILLSTON!
- 5.
N AME PL AT E R AT I N G ( GR OS S MWE )................................... 1,253 MW
- UNIT 3 6.
DESIGN ELECTRICAL RATlhG (NET r ()............................ 1,153.6 7.
MAXI MUM DEPEND ABL E CAP ACIT Y (Gross MWE )......................... 1,1B4.2 8.
MAX I MUM DEPE ND ABLE C AP ACI T Y ( NET MWE ).......................... 1,137.0 9 IF CHANGES DCCUR ABOVE SINCE LAST REPORT, REASONS ARE...........
N/A
- 10. POWER LEVEL TO WHICH RESTRICTED, I F ANY (NET MWE)...............W/A
- 11. REASON FOR RESTRICTION, IF ANY....N/A MONTH YEAR 10 DAfE CUHUlril%T TO DATE mains assamassaeas esasss===menessime i
- 12. HOURS IN REPORTING PER100 744.0 2,160.0 43,276,0
- 13. NUMBER OF HOURS THE REACTOR WAS CRITICAL 0.0 609.4 34,194.5
- 14. REACTOR RESERVE SHUTDOWN HOURS 0.0 169.4 1,698.3
- 15. HOURS GENERATOR ONLINE 0.0 581.5 33,547.0 16.' UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 17. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 1,448,011.0 109,512,823.0
- 18. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.0 476,917.5 37,785,894.0
- 19. NET ELECTRICAL ENERGY GENERATED (MWH) 4,612.0 434,684.1 36.008,293.6
- 20. UNIT SERVICE FACTOR 0.0 26.9 77.5
- 21. UNIT AVAILABILITY FACTOR 0.0 26.9 77.5
- 22. UNIT CAPACITY FACTOR (USING HDC NET) 0.0 17.7 72.9
- 23. UNIT CAPACITY FACTOR (USING DER NET) 0.0 17.4 72.1
- 24. UNIT FORCho OUTAGE RATE 0.0 24.5 10.1
- 25. UNIT 10RCED OUTAGE HOURS 0.0 189.1 3,767.6 SHUTDOWNS SCHEDULED 09:d NEXT SIX MONT HS (TYPE, DATE, AND DUR AT ION OF E ACH)..............
N/A IF CURRENTLY SHUTDOWN, ESilKATED STARTUP DATE...... April 9,1991
4 AVERAGE DAllt' UNIT POWER LEVEL DOCKET NO.
50-423 UNIT MILLSTONE UNIT 3 D \\TE April 3.109i COMPLETED BY A.1. ELMS 20L444 933 MONTH March 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE NET)
(MWE NET) l' O
16 0
2 0
17 0
-3 0
18:
0 4
0 19 0
5 0
20 0
6 0
21 0
.7 0
22 0
8' 0
23 0
9 0
24 0-10 0
. ~25 0
11 0
26 0-12.
0 27 0
13 0
28 0
14 0
29 6
'15 0
30 0
31 0
7-. -
.--m._
q
.R 3~x J
REFUELING INFORhiATION REOl]EST
~ March 1991-s
,1; _ - Name of facility: Millstone 3.
2.
Scheduldd date for next refueling shutdown: Febiuary 1El (currently in refuelt-3.
Scheduled drite for restart following refueling: April 9.1991 i.
Will refueling or resumption of operation thereafter require a technical specification -
change or other license amendments? -
- Emernency technical specification change for hydrocen recom^oiner flow, 5.
Scheduled date for submitting licensing action and supporting informetion, Submitted Antil 5.19d.
-i 6f Important liceniing considerations associated with refueling, e.g., new or different
-s fuel design or supplier, unreviewed design of performance analysis meticods, signifi.
cant changes in fuel design, new operating procedures:
Cycle 4 fuel assemblies wj{l be cf the Westinghouse Vatgane 5H higmThis desien
. includes debris filter bottom nozzles. intermediate flow mjhgM.teeral fuel rod
- burnable absorbers, and axial blankets.
L7.
The number of fuel assemblies (a) in the core and (b)in the spent fuel storage pool:
(a): 193 -
(b): 248
- 8.~
.;The present licensed spent fuel pool storage. capacity and the size of any increase in flicensed storage capacity that has been requested or is planned,-in number ed feel-
. assemblies:
'e Present size - 756..
No increase reauested?
9.
- The projected date of the last refueling that can be discharged to the spent fuel pool
- assuming the present licensed capacity:
End of cycle 5.
'l l
~
b
DOCKET ?O. 50-423 i
UNIT SHUTDOWUS AND POWER REDUCTIONS UNIT NA'IE MILLS 5:ONE 3 l
DATE 4-4-9:.
l' TELEPHONE (2031 444-5388 COMPLETED BY A.
ELMS-l i
Dura-Reason IMethod of Licensee ISyst5m Component Cause and Corrective No.
Date kfe tion (2)
- Shut down Event Code h Code Action to Prevent Hours
- Reactor (3)
Rept No.
Prevent Recurrence 91-01 3-01-91 S
744.0 C
4 N/A N/A
(
N/A
, Refuel outage 3 continued from previous month.
I i
l l
1: F: Forced 2: Reasons:
3: Method 4: Exhibit G - Instructions 1-Manual for Preparation of Data A-Equipment FailureB-Maintenance or Test (Explain)
S: Scheduled 2-Manual Scram Entn-Sheets for Licensee C-Refueling 3-Automatic Scram Event Report'(LER) File D-Regulato W Restriction 4-Continued from (NUREG-Ol61)
E-Operator Training & License Exam previous month i
F-Administrative 5-Power Reduction 5: Exhibit 1 - Same Source (Duration = 0 9-Other (Explain))
G-Operational Error (Explain)
H-Other m
- 3