ML20154F854
| ML20154F854 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/31/1988 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| C311-88-2124, NUDOCS 8809200154 | |
| Download: ML20154F854 (6) | |
Text
.
OPERATIONS
SUMMARY
AUGUST 1988 The ur,it edtered August in refueling shutdown with the RCS partially drained swa on 'A' Pecay Heat Removal. The plenum and Reactor Vessel head were reinstalled August 1.
During the first week of August, preparations were made 40 startup the secondary plant by placing the cire water system in service.
The RCS was filPM cd pressurized. All RCP's were run and the condensate system ated gland se:1 were established during the second week of August.
0., August 12, plant heatup commenced. During ICS testing at hot shutdown, all 4 RCP's tripped resulting in an EFW actuation.
When the pumps were restarted, 6e RPC, tripped, insorting the withdrawn safety rods.
This event is detailed i.i LER E 004.
Criticality was achtete i on August 14 Low power physics testing was conducted. Torsional resonance testing of the main turbine generator was completed with no modifications necessary.
MWt) generator was placed on line The and plant power was escalated to 100% (2568 The unit closed the month operating at 100% power.
i MAJOR SAFETY RELATED MAINTENANCE During August, the following major maintenance activities were performed on safety-related equipmen'.:
Once Through Steam Generators RC-H-1 A/B - Once Through Steam Generator (OTSG) work was completed in August.
Work accoglished included restoring secondary side instrumentation, reinstalling manway/handhole insulation and removal of work platforms and scaffolds.
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Reactor Vessel Head Work - Reactor refueling support work activities were l
completed in August.
Work accomplished included removal of the fuel transfer canal seal plate, plenum installation, reactor head installation, and recoupling of the APSR/CRDM's.
Pressurizer Code Safety Valve RC-RV-1B - Pressurizer Code Safety Valve RC-RY-1B work was completed in August.
The valve in the RC-RV-1B position was sent to Wyle Labs for inspection.
During an inspection of the inlet flange to the valve (pressurizer side), an indication was found that required repairs.
Af ter the indication was repaired, a spare tested valve was installed in the RC-RV-1B position.
Local Leak Rate Testing - Local Leak Rate Testing of valves and penetrations was completed during the month. All 95 scheduled tests were conpleted during i
the outage.
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ggo9200154 880931 ADOCK0500igp, PDR R
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OPERATING DATA REPORT DOCKET NO.
50-289 l
DATE 08/31/88 COMPLETED BY, C. W. SHYTH TELEPHONE (717) 948-8551 f
OPERATING STATUS i NOTES I
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 1 1
- 2. REPORTING PERIOD:
AUGUST
,1988. I l
- 3. LICENSED THERNAL POWER (NWT):
2568. I i
- 4. NAMEPLATE RATING (GROSS NWE):
871. I l;
- 5. DESIGN ELECTRICAL RATING (NET NWE):
819. I I-
- 6. NAX1NUM DEPENDA8LE CAPACITY (GROSS MWE):
824. I i>
- 7. MAXIMUN DEPENDA8LE CAPACITY (NET NWE):
776. 1 I I i
i 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIUC REASONS:
LICENSED THERMAL POWER INCREASED FRON 2535 TO 2568 NWT PER LICENSE ANENDMENT NO. 143.
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET NWE)
- 10. REASONS FOR RESTRICTIONS, IF ANY:
l
?
THIS NONTH YR-TO-DATE CUNNULATIVE,
- 11. HOURS IN REPORTING PERIOD 744.
5855.
122712.-
- 12. NUNSER OF HOURS REACTOR WAS CRITICAL 417.7 4409.2 50929.6"
- 13. REACTOR RESERVE SHUTDOWN HOURS O.O 61.6 1947.7'
- 14. HOURS GENERATOR ON-LINE 365.5 4354.4 49954.2' l
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0I
- 16. GROSS THERMAL ENERGY GENERATED (NWH) 881954.
10946107.
121433807.
- 17. GROSS ELECTRICAL ENERGY GENERATED (NWH) 299762.
3754265.
40622486.t
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 275009.
3536039.
38040321.I
- 19. UNIT SERVICE FACTOR 49.1 74.4 40.7
- 20. UNIT AVAILABILITY FACTOR 49.1 74.4 40.7l
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 47.6 77.8 39.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 45.1 73.7 37.9
- 23. UNIT FORCED OUTAGE RATE O.0 1.4 54.4' l'
24 SHUTDOWNS SCHEDULED OVER NEXT 6 NONTHS (TYPE, DATE, AND DURATION OF EACH 1
+
t i
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP:
i 1
AVERAGE DAILY UNIT POWER LEVEL
_ DOCKET NO.
50-289 UNIT TMI-1 DATE 08/31/88 COMPLETED BY C. W. SMYTH TELEPHONE (717) 948-8551 MONTH:
AUGUST DAY M/ERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1
-5.
17 511.
2
-6.
le 602.
3
-6.
19 726.
4
-10.
20 828.
5
-12.
21 825.
r 6
-13.
22 830.
j 7
-13.
23 829.
8
-13.
24 823.
9
-17.
25 822.
10
-17.
26 823.
11
-19.
27 819.
12
-36.
28 815.
13
-40.
29 824.
14
-42.
30 833.
15
-42.
31 835.
16 1.
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50-289 DOCKET M.
UNIT SHUIDOWNS AND POWER REDUCTIONS Ml-I UfGT NAME DATE 08-31-88 CORWIKTED BY C.W. Smyth l
REFORT MONTH AlfCUST 1988 TEtJF9 TONE (717) 948-85S1 e
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4 ed
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Cause & Cinvective
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1 08/01/88 S
378.5 C
1 Unit shutdown for Refueling Outage.
Outage comenced 6-17-88.
Total number of. outage hours as of this report period is 1437.
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l~' E.**cd Reas.m.
Methent:
Ealuben G-Instrustums S k twJedrJ A Iqimpracan Fada.e11splaui)
I muual for riepanaiam of Data B Wensenance a4 les:
2 mnual Scram.
Ensry Sheess foe Laiensee 3 Aus.nuatic Sssam.
Event Repost ILE RI Fde iNUREG-C-Refuciang 4 4)iles il s 4amil 01614 D Regulas.wy Rcss:As= =
i Opesanos isaiming & 1xca < 1 uunnas==
5 f Adammastsassic Estiebs I-Sanw S mece G Opesaapual I isue al spian t 11ihiwa ti.splama t 6
Actually und Oxhibits F & 11 NbREC 0161
REFUELING INFORMATION REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 l
2.
Scheduled date for next refueling shutdown:
January 5,1990 (8R) 3.
Scheduled date for restart following refueling: March 1, 1990 (8R) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes If answer is yes, in general, what will these be?
j Basic Refueling Report.
If answer is no, has the reload fuel design and core j
configuration been reviewed by your Plant Safety Review L
Committee to determine whether any unreviewed safety i
questions are associated with the core reload j
(Ref.10 CFR Section 50.59)?
l If no such review has taken place, when is it scheduled?
5.
Scheduled date(s) for submitting proposed licensing action and supporting l
information: October 1,1989 (estimate).
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6.
Important licensing considerations associated with refueling, e.g. new or i
dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
None 1
7 The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 360 4
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The present Itcensed spent fuel pool storage capacity and the size of any 1
increase in licensed storage capacity that has been requested or is j
planned, in number of fuel assemblies:
{
The present licensed capacity is 752.
Preliminary planning to j
increase licensed capacity through fuel pool reracking is in process, t
~
9.
The projected date of the last refueling that can be discharged to the j
spent fuel pool assuming the present licensed capacity:
I 1991 is the last refueling discharge which allows full i
core off-load capacity (177 fuel assemblies),
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6 GPU Nuclear Corporation Nuclear
,om s,s
Middletown, Pennsylvania 17057 0101 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
Septenber 15, 1988 C311 2124 i
U. S. Nuclear Regulatory Cornrnission Attn: Document Control Desk Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I (THI-1)
Operatina License No. DPR-50 Docket No. 50-289 Monthly Operating Report August 1988 Enclosed are two copies of the August 1988 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, e
D. Inkill Vice President & Director, THI-1 HDH/SM0:spb cc:
W. Russell, USHRC R. Conte. USNRC Attachrnents 0015C GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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