ML20085E503
| ML20085E503 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1995 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-95-2269, NUDOCS 9506160555 | |
| Download: ML20085E503 (7) | |
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GPU Nuclear Corporation Nhh hf P.O. Box 480 Route 441 South Middletown, Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Number:
(717) 948-8005 June 12,1995 C311-95-2269 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for May 1995 Enclosed are two copies of the May 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincen:ly, T. G. Broughton Vice President and Director, TMI WGli i
Attachments cc: Administrator, Region I TMI Senior Resident Inspector 195001 9506160555 950531 PDR ADOCK 05000289 R
PDR GPU Nuclear Corporaton is a subsidiary of General Public Utilities Corporation 1
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- r l
d OPERATIONS
SUMMARY
May 1995 The plant entered the month operating at 100% power and remained at that level throughout the entire month. Net unit elenrical output averaged approximately 807 MWe during May.
MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items accomplished during the month.
Fire Service Hydrant FS-H-22 Fire Service Hydrant FS-H-22 was removed from service because the valve could not be operated. After excavating the hydrant, the valve was disassembled and the stem nut was found to be stripped. Based on the condition of the valve components upon inspection, it was decided to rebuild the valve using a new stem, disc, and stem nut. After reassembly, FS-H-22 was retested, backfilled, and returned to service.
Pmcoat Filter Rdief Valves WDL-V-386/387 Precoat Filter Relief valves WDL-V-386/387 were replaced during the scheduled Precoat Filter System Outage. The valves were replaced because they were socket welded to the system piping and could not be easily removed for periodic set point testing. They were also l
of an obsolete design with no repair parts available. After the piping was rerouted to accommodate the new flanged valve design, the new valves were installed, leak tested and retumed to service with other system components at the completion of the Precoat Filter System Outage.
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE June 12,1995 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191 1.
UNIT NAME:
THREE MILE ISLAND UNIT 1 l NOTES:
l
- 2. REPORTING PERIOD:
MAY 1995 l
l
- 3. LICENSED THERMAL POWER:
2568 l l
4.
NAMEPLATE RATING (GROSS MWe):
872 l l
S. DESIGN ELECTRICAL RATING (NET MWe):
819 l l
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
834 l l
7.
MAXIMUM DEPENDABLE CAPACITY (NET MWe):
786 l l
l l
8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY INET MWe):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD (HRS) 744.0 3623.0 181848.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 3623.0 105211.7
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2284.0
- 14. HOURS GENERATOR ON-LINE (HRS) 744.0 3623.0 104078.1
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1908127 9295338 255211609
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 634852 3131794 85815048
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 599986 2959020 80614438
- 19. UNIT SERVICE. FACTOR
(%)
100.0 100.0 57.2
- 20. UNIT AVAILABILITY FACTOR
(%)
10 0. ~0 100.0 57.2
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 102.6 103.9 56.4
- 22. UNIT CAPACITY FACTOR (USING DER NET) 98.5 99.7 54.1
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 36.8 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
Re-fueling outage / September 8, 1995 / 45 days
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
9 3
e, AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT THI-1 DATE ilunn 12_1995 COMPLETED BY W G HEYSEK TELI: PHONE (717) 948-3191 MONTH:
MAY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEA LEVEL (MWe-NET)
(MWe-NET) 1 814 17 802 2
813 18 798 3
811
- 9 809 4
811 20 807 5
812 21 805 6
812 22 808 7
813 23 802 8
815 24 789 9
812 25 794 10 811 26 801 11 808 27 805 12 808 28 808 13 809 29 796 14 813 30 803 15 806 31 801 16 807 4
DOCKET NO. 50-289 UNTI' NAME TMI-l REPORT MONTH May 1995 DATE June 12,1995 COMPLETED BY W. G. Heysek TELEPIIONE (717) 948-8191 b'*****
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Canae & Cmective I
CNw MMd No.
E rers Code Action to Type' Duratvm Reason 2 Shutting Code g
Prevent Recurnnce Okers)
Down
.g.
Reactor' s g.
None 1
2 3
4 F Forced MN O ' I*h* I" Resa Method N'"
S Scheduled A-Equipment Failure (Explami 1-Manual B-Mamtename or Test 24tanual Scram C-Refuelmg 3-Autanatic Scram D-Reguhtory Restrictne 40Aer (Explam)
Goperator Trammg & Ixen=mg Exammanon 5 Exinwir i name.our.
F-Admmistranve
(.'@nmal Enw $1phe 6 Actually used exhibita F & 11 NUREG 0161 11es er (Explain) 5
REFUELING INFORMATION REOUEST 1.
Name of Facility: Three Mile Island Nuclear Station, Unit 1
- 2. Scheduled date for next refueling shutdown: September 8,1995
- 3. Scheduled date for restart following current refueling: NA 4.
Will refueling or resumption of operation thereafter require a technical specification change i
or other license amendment? YFS. See 6.c and d below.
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
i NA i
)
6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating procedures:
a) TMI will use the new Mark B10 fuel assembly in the Cycle 11 reload batch which i
is an upgraded design of the Mark B9 assembly used in Cycle 10. The Mark B10 provides a leaf-type cruciform assembly holddown spring to replace the previous coil spring design which has experienced random failures during operation and requires visual inspection each outage. The Mark B10 design meets all current BWFC fuel design criteria and is in use at other B&W 177 FA plants.
b) TMI also will use four new Westinghouse Imad Test Assemblies (LTA) in the Cycle 11 reload batch. Their planned operation is for three consecutive cycles with diwharge at end-of-Cycle 13.
The four E LTAs inserted in Cycle 9 were discharged at EOC-9 due to detection I
of fuel rod failures caused by grid-to-rod fretting similar to that seen in E Vantage SII fuel designs. The Cycle 11 LTAs will use the generic E recommended design fix of rotated intermediate spacer grids to minimize flow-induced fuel vibrations and thus eliminate fretting. A prototype LTA was flow-tested to demonstrate the effectiveness of the fix. The production LTA will use ZIRLO fuel rod cladding, guide tubes and instrumentation tube and intermediate grids in place of Zircaloy 4 l
l materials used for the Cycle 9 LTAs. Otherwise, the Cycle 11 LTA design is i
basically the same as the Cycle 9 design.
The LTAs will meet current E fuel design criteria while operating within TMI core operating limits. LTA enrichment and core location will ensure that an LTA will not be the lead (hot) assembly at any time during the cycle and will not set any l
safety or operating limits. The LTAs will remain bounded by existing UFSAR safety analyses results.
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j c) GPUN plans to place two types of BWFC advanced non-zircaloy cladding in TMI-1 Cycle 11; eight rods each. The two types will be equally distributed in two Mark B10 fuel assemblies; one rod of each material in each of the four peripheral rows per assembly. These cladding materials are also being irradiated in the McGuire reactor and other international reactors with no negative performance observed.
Use of the cladding requires NRC acceptance of an exemption request regarding 10CFR50.46 which was submitted as Attachment II to Technical Specification Change Request number 251. Exemption approval was requested no later that July 21,1995 to support final fuel delivery schedules for the 11R Outage.
d) GPUN submitted Technical Specification Change Request number 252 to relocate the volume and boron concentration requirements of TS section 2.3 for the chemical addition system boric acid mix tank and reclaimed boric acid storage tanks to the existing TMI-1 Core Operating Limits Report (COLR). The proposed change is consistent with the intent of NRC Generic Letter 88-16 guidance. The change will preclude the need for a TSCR to revise the parameters to meet Cycle 11 specific requirements.
7.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 601
- 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 1990. Phase 1 of the reracking project to increase spent fuel pool storage capacity permits storage of 1342 assemblies. Upon completion of Phase II of the reracking project, the full licensed capacity will be attained. Phase II is expected to be started in 2002,
- 9. The pmjected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Completion of Phase I of the reracking project permits full core off-load (177 fuel assemblies) through the end of Cycle 14 and on completion of the rerack project full core off-load is assured through the end of the current operating license and beyond.
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