ML20153F240
| ML20153F240 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/31/1986 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Macdonald W NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 0015C, 15C, 5211-86-2024, NUDOCS 8602250353 | |
| Download: ML20153F240 (6) | |
Text
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OPERATIONS SIM4ARY J ANUARY, 1986 The unit entered January operating at 87.5% reactor power (power was li#a s by steam generator level), with generator output at 750 MWe.
On January 1, 1986 the turbine was manually tripped per the final evolution of the Power Escalation Test Program resulting in automatic reactor trip. The reactor coolant pumps were secured and emergency feedwater automatically actuated.
Subsequent to acceptable post trip review, the reactor was taken criticale At 22% power during the escalation sequence a turbine trip / reactor trip occurred
~
as a result of high moisture separator level. A failed heater drains valve controller was replaced and later that day the reactor was taken critical and achieved the power level cutoff (92% reactor power) on January 4,1986 with steam generator levels at 68%.
On January 6,1986 at 14:05 the unit one reactor achieved 100% power.
On January 24, 1986 a partial loss of ICS auto power was experienced as a result of returning power (following maintenance) to the "B" side main feedwater flow transmitter. The plant was stabilized at approximately 97% during this event. Restoration of the ICS auto power was performed following controlled and deliberate trouble shooting by the Lead I&C Engineer and Maintenance Ma nager. The Unit returned to 100% steady state power.
The reactor was shutdown on January 27, 1986 and a cooldown was complete the following day to repair 8th stage extraction lines internal to the condenser.
The unit remained in cold shutdown through the end of January to effect repairs.
MAJOR SAFETY RELATED MAINTENANCE During the month of January, TMI Unit 1 performed no major maintenance on safety related equipment.
8602250353 e60131
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. OPERATING DATA REPORT DOCKET NO.
50-289 DATE 1-31-86 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
JANUARY
,1986.
- 3. LICENSED THERMAL POWER (MWT) :
2535.
- 4. NAMEPLATE RATING (GROSS MWE) :
871.
- 5. DESIGN ELECTRICAL RATING (NET MWE) :
- 819,
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :
824.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :
776.
8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
- 10. REASONS FOR RESTRICTIONS, IF ANX:
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD
- 744, 744.
100081.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 604.3 604.3 34420.9
- 13. REACTOR RESERVE SHUTDOWN HOURS 105.3 105.3 988.5
- 14. HOURS GENERATOR ON-LINE 595.9 595.9 33629.8
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL. ENERGY GENERATED
(. WH) 1473545.
1473545.
80823941.
M
- 17. GROSS ELECTRICAL ENERGY GENERATED
(, WH) 485365.
485365.
26877518.
M
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 453770.
453770.
25105482.
- 19. UNIT SERVICE FACTOR 80.1 80.1 33.6
- 20. UNIT AVAILABILITY FACTOR 80.1 80.1 33.6
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 78.6 78.6 32.1
- 22. UNIT CAPACITY FACTOR (USING DER NET) 74.5 74.5 30.6
- 23. UNIT FORCED OUTAGE RATE 15.6 15.6 63.7
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH Eddy Current Outage (Steam Generators); March 22, 1986; 35 days
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
[
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AVERAGE DAILY UNIT POWER LEVEL i
DOCKE1 NO.
50-289 UNIT TMI-1 DATE l-31-86~
COMPLETED ~BY C.W. Smyth TELEPHONE (717) 948_8551 MONTH:
JANUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 701.-
17 777.
2 334.
18 776.
39.
19 772.
3 4
200.
20 776.
5 726.
21 777.
6 769.
22 779.
7 806.
23 781.
8 804.
24 780.
9 792.
25 783.
10 724.
26 781.
11 782.
27 682.
12
-778.
28
-21.
13 781.
29
-10.
14 779.
30
-7.
15 777.
31
-7.
16
-773.
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m-.m m.
- m. -
5 m.
50-289 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS TMI-I UNIT NAME DATE 1/31/db COMPLETED ay C.W. Smyth JANUARY.
REPORT MONTH TELEPHONE T71 W 94Y~8T8il e
e
.$?
3 hI Licensee E,
Cause & Corrective Date
(
3g i
.3 s &
Event t; 7
- a. 3 Action to H
jE jgg Report se i$ v l0 Prevent Recurrence c5 1
1/2/86 S
34.5 B
3 N/A RC Instru Trip from 88% for ICS testing (final test in Power Escalation Program).
2 2/4/86 F
10.5 A
3 86-02 HH Valvex Anticipatory Reactor Trip on Turbine Trip caused by high moisture sepa-rator drain tank level.
Repaired heater drain level controller and associated high level dump valve.
3 2/27/86 S
100 A
1 N/A HJ HT Exch Shutdown to repair bellows on extraction steam line.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C. Refueling
- 3. Autonutic Scram.
Event Report (LERI File INUREG.
D Regulatory Restriction 4-Oiher IINplain)-
0161)
E-Operator Training & Licenw 17xaminat mn F-Administrative 5
Exhibit I Same Source G-Operatjonal 13ror (INplain)
Il-Other IE xplain) 6 Actually used Exhibits F & 11 NUREC 0161
b s
REFUELING INFORMATION REQUEST 1.
Name of Facility: Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
December 6,1986 3.
Scheduled date for restart ~ following refueling:
May 4, 1987 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?
Yes If answer is yes, in general, what will these be?
Conversion to 18 month fuel cycle with associated changes to Power Imbalance, Quadrant Tilt and Rod Insertion Limits.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?
No If no such review has taken place, when is it scheduled?
To be determined.
5 Scheduled date(s) for submitting proposed licensin] action and supporting information:
November, 1986 6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perforrance analysis methods, significant changes in fuel design, new operating procedures:
None 7.
The number of fuel ascamblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 208 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:
The present licensed capacity is 752.
There are no planned increases at this time.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
i
GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number February 13, 1986 5211-86-2024 Office of Management Information and Program Control Attn:
W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Mcdonald:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report January, 1986 Enclosed please find two (2) copies of the January,1986 Monthly Operating Report for Three Mile Island Nuclear Station Unit-l.
Sincerely, f
.)
H. D. Hukill Director, TMI-l HDH:DVH:spb Attachments cc:
V. Stello Dr. T. E. Murley 0015C 5,
I )
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation