ML20067E569
| ML20067E569 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/31/1991 |
| From: | Elms A NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20067E549 | List: |
| References | |
| NUDOCS 9102150141 | |
| Download: ML20067E569 (3) | |
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""*" NRC OPERATING STATUS RLPORT CaMPLETED ST REACTOR ENGINEERING **""*
1.
DOCKET.... 50 423 QPERATING STATUS 2.
REPORTING PERIOD... JANUARY 1991 SJTAGE
- ONLINE MER$..199.1
- 554.9 e 764.0 3.
UT I L I TY CON T ACT................. A. L. ELMS 203 444 534E l
4 L I CE N SED T HE RMAL P0WE R......................................... 3411
- NILtsTONE
- 5.
hAME PL A T E RAT I NG ( GR oss MWE )................................... 1,25 3 MW
- UNIT 3 6.
DE S I GN E LECTR I CA L RAT I NG (NE T MWE )............................. 1,1 $3.6 i
7.
MAXINLM D:R-
- RLE CAPAC I T Y (GROSS MWE )........................ 1,184.2 8.
MAXIMLM ( w : f CAP AC I T T ( NE T MWE ).......................... 1,13 7.0 9.
IF CHANGES V i A80VE SINCE LAlf REPORT, REASONS ARE...........
N/A
- 10. POWER LEVEL TO WICH At$f RICTED, lF ANT (NET MWE)...............k/A
- 11. REASON FOR RESTRICTION, IF ANT....N/A MOW 1H TEAR TO DATE CLMULAflVE TO DATE enau.neus.n' anos een nesen
- 12. NOURS IN REPORTING PEkl0D 744.0 744.0 41,880.0-
- 13. m.MBER OF WOURS THE REACTOR WAS CRITICAL 574.6 574.6 34,159.7-i
- 14. REACTOR RESERVE $NUTDOWN NOURS 169.4 169.4 1,698.3
- 15. NOUR$ GENERATOR ONLINE 554.9 554.9 33,520.4
- 16. UNIT RESERVE SMUTDOWN NOUR$
0.0 0.0 0.0
- 17. Gross THERNAL ENERGY GENERATED (NWN) 1,384,282.0 1,384,282.0 109449094.0
- 18. Gross ELECTRICAL ENERGY GENERATED ( M )
456,486.0 456,446,0 37,765,462.5
- 19. NET ELECTRICAL ENERGY GENERATED (MWN) 426,453.0 426,453.0 36,000,062.5
- 20. UNIT SERVICE FACTOR 74.6 74.6 80.0
- 21. UNIT AVAILAtiLITY FACTOR 74.6 74.6 80.0
- 22. UNIT CAPACITY FACTOR (U$1NG mc NET) 50.4 50.4 75.4
- 23. UNIT CAPACITY FACTOR (U$1NG DER NET) 49.7 49.7 74.5
- 24. Latif FORCED QUTAGE RATE 25.4 25.4 10.1-j.
- 25. UNI.T FORCED OUTAGE HOUR $
189.1 189.1 3,767.6
$NUTDOWW$ SCHEDULED OVER NEXT $1X MONTNS (TTPE, DATE, AND DURAfl0N OF EACN)..............
N/A IF CURRENTLY $NUTDOWN, ElflMATED STARTUP DATE...... March 21, 1991 i
l 9102150141 910211 PDR ADOCK 05000423 g
FDR
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DOCKET NO. 50-423 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MILL:f.:oNE 3 DATE 2-7-91 COMPLETED BY A.
EIJtS TELEPHONE (203) 444-5388 No.
Date e
Dura-Reason Method of Licensee System Component Cause and Corrective
(
tion (2)
Shut down Es.ent Code Code Action to Prevent Hours Reactor (3)
Rept No.
Prevent Recurrence 93-13 12-31-90 F
189.1 A
2 90-030-00 SB LCV Manually tripped reactor due to two ruptured mois-tur9 seperatgr reheater drain tank pipes. The cause of the break was single phase erosign/
corrogion. Correctlye ac-tion 4ncluded removing the pipes fr9m servicg by capping, adding the pipe to the erosign/ corrosion program and investigating why the pipes wer9 not already included in the program.
i 1: F: Forced 2: Reasons:
3: Method 4: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual 9 cram Ent a Sneets for Licensee C-Refueling 3-Automatle Scram Event Report (LER) File D-Regulatory R9striction 4-Continued from (NUREG-Ol61)
E-Operator Training & License Exam 5 previous month
.F-Adminigtrative Power Reduction 5: Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration = 0 9-Other (Explain))
H-Other
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REFUELING INFORMATION REOUEST January 1991 1.
Name of facility: Millstone 3.
2.
Scheduled date for next refueling shutdown: February 1.1991 (currently in refuell 3.
Scheduled date for restart following refueling: March 21.1991 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendments?
As a result of the new fuel desien, Technical Specifications chances to the Axial Flux Difference. Heat Flux Hot Channel Factor and Refueline Water Storane Tank sec-tions will be recuired. Furthermore. the Fuel Storace section of Desien features wil D.Lghanced to allow continued recionalized storaire of spent fuelin the spent fue ;
ocol. Also. the Instrumentation section will be changed to reflect a new High Flux at Shutdown setpoint.
5.
Scheduled date for submitting licensing action and supporting information.
. All Technical Specification chances submitted.
6.
Important licensin considerations associated with refueling, e.g., new or different fuel design or sup ier, unreviewed design of performance analysis methods, signifi-cant changes in fu design, new operating procedures:
Cvele 4 fuel assemblies will be of the Westinchouse Vantace SH desien. This desien includes debris filter bottom nozzles. intermediate flow mixinc crids. intecral fuel rod burnable absorbers. and axial blankets.
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7.
The number of fuel assemblies (a)in the core and (b)in the spent fuel storage pool:
(a): 122 (b): 2.48 4
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:
Present size 756.
No increase requested.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assummg the present licensed capacity:
End of cycle 5.
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