ML20207G273
| ML20207G273 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1988 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| C311-88-2109, NUDOCS 8808240049 | |
| Download: ML20207G273 (8) | |
Text
_ _ _ _ _ _ _
OPERATIONS
SUMMARY
JULY 1988 The unit entered July in cold shutdown on "A" Decay Heat Removal with the RCS in a partially drained down condition.
Draindown conditions were maintained throughout the month.
OTSG tube plugging was cogleted with 13 tubes plugged in the "A" OTSG and 8 tubes in the "B OTSG. The reactor vessel head was remved and placed on the storage stand.
The plenum was then removed from the reactor vessel.
The fuel transfer canal was filled to support refueling.
Control rod and fuel shuffle were cogleted July 26, 1988.
OTSG mechanical cleaning (Waterslap) and sludge lancing were performed on both steam generators.
Sludge lancing of the "A" 0TSG produced 113 pounds of debris and the "B" OTSG produced 179 pounds. At the end of the month, the plenum was reinstalled in the reactor vessel and preparations for reactor vessel head reinstallation were undemay.
MAJOR SAFETY RELATED MAINTENANCE During July TMI-1 performed the following major maintenance activities on safety-related equipment:
Once Through Steam Generators RC-H-1 A/B - Once Through Steam Generator (OTSG) work continued in July.
The Eddy Current Testing program was cogleted with 2197 tubes tested in the "A" 0TSG and 1938 tubes in the "B" 0TSG.
Based on ECT test results,13 tubes in the "A" OTSG were plugged (1 tube required stabilization) and 8 tubes in the "B" OTSG were plugged (6 tubes required stabilization).
At the completion of repair work, all tools and equipment were removed and the primary handhole and manway covers were reinstalled.
OTSG secondary side mechanical cleaning work was accoglished. This involved isolating secondary instrumentation, waterslap equipment setup and completing the waterslap cleaning evolution.
At the completion of waterslap, the equipnent was removed and sludge lancing of the OTSG's commenced. After the sludge lancing evolution completed, all mechanical cleaning tools and equipment were removed and the secondary handhole and manway covers installed.
Secondary side instrucentation will be placed back in service in August.
Reactor Head Removal - During July, Reactor Head removal work included the uncoupling and parking of APSR/CRDM's, detensioning and parking RV head studs, removal of fuel transfer tube covers, and installing flood line cover plates.
After the fuel transfer canal was cleaned, the Reactor head and plenum were removed.
RV head stud holes were then sealed and the seal plate installed.
NI cover plates were sealed and the Reactor vent valves were exercised.
With the canal flooded and refueling in progress, RV studs were cleaned and APSR/CRDM closures cleaned.
The reactor head 0-Ring was removed and cut up
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for disposal.
The RV head 0-Ring groove was cleaned, inspected, and a new 0-Ring installed. Af ter refueling activities were cogleted, the fuel transfer canal was drained and preparation for head reinsta11ation began.
Herculite was layed in the canal, the indexing fixture was rigged and installed, reactor vessel studhole covers removed, studholes cleaned and the seal plate removed.
The plenum was then installed and the indexing fixture removed.
Reactor Yessel Head installation will be completed in August.
Reactor Coolant Pump Seal Inspections - Reactor Coolant Pump RC-P-1 A/B/C/D Teal inspections were completed during the month.
The seals on RC-P-1 A were removed, inspected and 0-Rings replaced as required. The seal packages were then reassembled using a new #1 insert, new
- 2 seal ring and seal runner, a new #2 seal insert, and a new #3 seal ring.
After the seals were reinstalled in the pump, the coupling was reinstalled on the pug, and the pump / motor aligned and the spool piece reinstalled.
RC-P-1B seal work included removal, inspection and 0-Ring replacement on all three seals.
The seal packages were then reassembled and installed using a new #1 insert, new #2 seal ring and runner, a rebuilt upper seal housing with a new #2 insert, and a new #3 seal ring and runner. Af ter the seals were reinstalled in the pump, the coupling was reinstalled on the pump, and the pump / motor aligned and spool piece reinstalled.
RC-P-1C seal work included removal, inspection and 0-Ring replacement on all three seals.
The seal packages were then reassembled and installed using a new #1 insert, new #2 seal ring and seal runner, a #2 insert and a new #3 seal ring and runner. After the seals were reinstalled in the pug, the coupling was reinstalled on the pump, and the pump / motor aligned and the spool piece reinstalled.
The RC-P-1D seal work included removal of all three seals, inspection and 0-Ring replacement as required. The seal packages were reassembled and installed using a new #1 insert, a new #1 seal ring and runner, a new #1 sleeve, a new #1 sleeve adapter, a new #2 seal ring, a new #2 insert and a new
- 3 seal ring. After the seals were reinstalled in the pump, the coupling was reinstalled on the pump, and the pump / motor aligned and the spool piece reinstalled.
After all seal work was completed on RC-P-1 A/B/C/0, seal inspection hardware was removed, thermocouples and instrumentation were reinstalled. Oil drip pans were reinstalled and the work area cleaned.
Local Leak Rate Testing - Local Leak Rate Testing of Yalves and penetrations continued in July with 78 of 95 tests completed.
One valve, WDL-Y-304, required repair work in order to meet test criteria.
The valve was disassembled and inspected.
Inspection revealed that the valve wedge required replacement. A new wedge was obtained and the seats and wedge were lapped and blue checked. The valve was reassembled and retested.
After an operator adjustment, the valve tested satisfactory.
l Pressurizer Pilot Operated Relief Yalve - The pressurizer pilot operated re11ef valve RG-RV-2 was replaced during the month.
The valve was removed from the pressurizer and a previously tested spare valve was installed.
The valve was sent off-site for inspection and testing by Wyle Lab.
Test results indicated the valve tested satisfactorily.
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Pressurizer Code Safety Yalves - Pressurizer Code Safety Yalve RC-RV-1A was removed from the pressurizer and replaced with a tested spare valve.
The valve was then shipped to Wyle Lab for inspection and test.
Inspection results indicated that the valve did not reet the test criteria of 2500 psi +
1%.
Repairs to the valve were co@leted by Wyle and Dresser Industries and --
the valve retested satisfactory.
Valve RC-RY-1B was removed from the pressurizer and preparaticns were made to ship the valve to Wyle for testing.
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OPERATING DATA REPORT 50-289 DOCKET NO.
07-31-88 DATE COMPLETED BY C.
W.
Smyth TELEPHONE (7171948-8551 OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
JULY
,1988.
- 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 CMANGES 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 ANY:
THIS MONTH YR-TO-DATE CUMMUIATIVE
- 11. HOURS IN REPORTING PERIOD 744.
5111.
121968.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 3991.4 50511.9
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 61.6 1947.7
- 14. HOURS GENERATOR ON-LINE 0.0 3988.9 49588.7
- 15. UNIT RESERVE SNUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH)
O.
10064153.
120551853.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
3454503.
40322724.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
O.
3261030.
37765312.
- 19. UNIT SERVICE FACTOR 0.0 78.0 40.7
- 20. UNIT AVAILABILITY FACTOR 0.0 78.0 40.7
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 82.2 39.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 77.9 37.8
- 23. UNIT FORCED OUTAGE RATE 0.0 1.6 54.6
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
- 25. IF SHUT DOWN AT END OF REPGRT PERIOD, ESTIMATED DATE OF STARTUP: 08/14/88
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT THI-1 DATE 07-31-89 COMPLETED BY C.W. Snifh__
TELEPHONE I71~1) 94 8 CLS51 MONTH:
JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0.
17 0.
2 0.
18 0.
3 0.
19 0.
4 0.
20 0.
5 O.
21 0:
6 0.
22 0.
7 0.
23 0.
8 0,
24 0.
9 0.
25 0.
10 0.
26 0.
11 0,
27 0.
12 0.
28 C.
13 0.
29 0.
14 0.
30 0.
15 O.
31 0.
16 0,
s 50-289 DOCKET NO.
UNIT SilUTDOWNS AND FOWFR REDUCTIONS UNIT NAME DATE UI-31-88 CONFLETTD EY C.W. Smyth REFORT MONTH tlULY TELEPHONE T717) 948-R55T o
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Date g
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I 88-02 07-01-88 S
744 C
1 Unit shutdown for Refueling Outage.
Outage conmenced 6-17-88.
Total number of _ outage hours ~as of this report period is 1058.5.
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4 f fansed Reason.
Methal:
Exlubis G. Instrutiions S St heduled A l'quipment Fadure(Explain)
I-Manual for Pseparation of Data B Maintenance of Tes 2 Manual Scram.
Entry Sheets l'or Licensee C Refueling 1 Autonutic Siram.
Event Repost tLERI FdeINUREG-D-Regulatory Restritsion 4 Thher 11'splain) 01611 1 -Operaio Training & luenw I saniinainm 5
F Adnunisisaine Eslubis I - Same Souwe
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G Operasymal 1:ssos 11'splauil 11 Other (l:splaini 6
Actually used Exhibits l
F & 11 NUREC 0161 i
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REFUELING INFORMATION REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
January 5,1990 (8R) 3.
Scheduled date for restart folloving refueling: August 14,1988 (for current 7R Outage) - March 1,19!9 (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?
Basic Refueling Report.
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)?
If.no such review has taken place, when is it scheduled?
5.
Scheduled date(s) for submitting proposed licensing action and supporting information: October 1,1989 (estimate).
6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures :
None 7.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 360 8.
The present licensed sper.t 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:
l The present licenseo capacity is 752.
Preliminary planning to increase licensed capacity through fuel pool reracking is in process.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed caoacity:
(
1991 is the last refueling discharge which allows full I
core of f-load capacity (177 fuel assemblier).
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s GPU Nuclear Corporation
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Nuclear
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s Middletown, Pennsylvania 17057 0191
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717 944 7621 i
TELEX 84 2386 Writer's Direct Dial Number:
Atgust 15, 1988 C311 2109 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555
Dear Sir:
Three Mile Isl6nd Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report July 1988 Enclosed are two copies of the July 1988 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely,
. D.
kill Vice President & Director, TMI-1 HDH/SMO:spb cc:
W. Russell, USNRC R. Conte, USNRC Attachments 0015C l
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[b GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation f
.