ML20056E168

Monthly Operating Rept for Jul 1993 for TMI-1

ML20056E168
Person / Time
Site:	Crane
Issue date:	07/31/1993
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-93-2123, NUDOCS 9308200169
Download: ML20056E168 (8)

Text

GPU Nuclear Corporation 2 TNuclear m::="'"

Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial Nurnber:

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(717) 948-8005 August 11, 1993 C311-93-2123 l

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

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Gentlemen:

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Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for July 1993 Enclosed are two copies of the July 1993 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely,

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T.G.Brouston Vice Presi ent and Director, TMI-1 WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector 9308200169 930731 D

PDR ADOCK 05000289 L <

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h GPU Nuclear Corporation is a subsidiary of General Public Uti!mes Corporation

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OPERATIONS

SUMMARY

July 1993 I

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The plant entered and ended the month operating at 100% power. The plant i

electrical output averaged approximately 830 MWe during the period.

l MAJOR SAFETY RELATED MAINTENANCE i

During July the following major safety related maintenance was performed:

Radwaste Motor Control Center Repairs to the Radwaste Motor Control Center 1B were completed. Work included replacement of the control power transformer and the 71X relay coil. Upon completion of the repairs, the motor control center was satisfactorily tested 4

and returned to service.

Boric Acid Mix Tank Mixer CA-M-1 The Boric Acid Mix Tank Mixer, CA-M-1, was removed from service to permit inspection of the unit. The mixer lantern ring was suspected as the source of brass particles found in the mix tank. Work performed on the mixer unit included: shaft replacement, fabrication of a stuffing box bushing and reconfiguration of the stuffing box arrangement, replacement of the brass lantern ring with a non-metallic lantern ring and tack welding the impeller shroud in place.

Post maintenar.ce testing was satisfactorily completed and the unit was returned to service.

Miscellaneous Waste Evaporator WDL-Z-1B Miscellaneous Waste Evaporator, WDL-Z-1B, was removed from service due to low output. Maintenance activities accomplished included: cleaning the eductor, repairing a distillate cooler flange leak, checking the stroke on valve WDL-V-262B, cleaning the level control valve, and cleaning WDL-CE-20B. Upon satisfactory completion of post maintenance testing, WDL-Z-1B was returned to service.

Station Blackout Diesel Startina Air Compressor EG-P-11B The Station Blackout Diesel Starting Air Compressor, EG-P-11B, was not loading and was removed from service to permit investigation and repair. Maintenance action included replacement of the loading and unloading valves, the 3-way valve and the pilot valves.

EG-P-11B was returned to service after post maintenance tests were satisfactorily performed.

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OPERATING DATA REPORT i

DOCTST NO.

50-289 DATE August 11, 1993 COMPLETED BY W G HEYSEK l

OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISIAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

JULY 1993 l

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3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWe) :

871 l l

5. 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

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8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

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9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):

10. REASONS FOR RESTRICTIONS, IF ANY:

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THIS MONTH YR-TO-DATE CUMMULATIVE 11.1;OURS IN REPORTING PERIOD (HRS) 744.0 5087.0 165792.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5021.3 90498.0 i

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2283.8

14. HOURS GENERATOR ON LINE (HRS) 744.0 5017.3 89417.4

15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1908127 12516227 218562931

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 614638 4245835 73590909

18. NET ELECTRICAL ENERGY GENERATED (MWH) 579562 4004432 69106739

19. UNIT SERVICE FACTOR

(%)

100.0 98.6 53.9

20. UNIT AVAILABILITY FACTOR

(%)

100.0 98.6 53.9

21. UNIT CAPACITY FACTOR (USING MDC NET) 99.1 100.2 53.0

22. UNIT CAPACITY FACTOR (USING DER NET) 95.1 96.1 50.9

23. UNIT FORCED OUTAGE RATE

(%)

0.0 1.4 40.5 UNIT FORCED OUTACE HOURS (HRS) 0.0 69.7 60759.4

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

> REFUELING;- September 10, 1993; 45 Days <

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1

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DATE August 11, 1993 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 i

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MONTH:

JULY i

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWe-NET) 1 792 17 786 2

792 18 786 3

788 19 781 j

4 780 20 776 5

778 21 782 j

6 776 22 785 7

777 23 785 8

777 24 782 i

9 773 25 778 10 768 26 776 11 774 27 773 12 773 28 771 13 774 29 773 14 773 30 780 15 776 31 780 16 783 i

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A UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-2 fl9 UNIT NAME TMI-1 REPORT MONTH July 1993 DATE August 11, 1993 COMPLETED BY W.

G.

Heysek TELEPHONE (717) 948-8191 Method of Licensee System :omponent Cause & Corrective No.

Date Type' Duration Reason' Shutting Event Code Code Action to (Maurs)

Down Report #

Prevent Recurrence Reactor' None 1

2 3

4 F Forced Reason Method Exhibit G - Instructions for 5 Scheduled A-Equipment Failure (Explain) 1-Manual preparation of Data Entry Sheets B-Maintenance or Test 2-Manuel Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic scram File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & Licensing Examination 5 Exhibit 1 same source F-Adninist rat ive G-Operational Error (Explain) 6 Actuatly used exhibits F & II NUREG 0161 H-Other (Explain) i 5

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h REFUELING INFORMATION RE0 VEST

1. Name of Facility:

Three Mile Island Nuclear Station, Unit 1

2. Scheduled date for next refueling shutdown:

September 10, 1993 (10R)

3. Scheduled date for restart following current refueling: NA

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? YES In general, these will be:

a) Use of urania-gadolinia fuel in Cycle 10 and B&W Fuel Corporation (BWFC) changes in core physics methods will require change to T.S. 6.9.5.2 which lists approved analytical methods references to support the Core Operating Limits Report cycle-specific limit values.

Based on recent NRC SER approval of BAW 10179, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses", which includes the new physics methodology BAW-10180, Rev.1, NE.10 by reference, BAW 10179 will replace l

the current list of approved methods in T. S. 6.9.5.2.

Use of the gadolinium integral burnable poison will also require changes to the l

Reactor Core fuel descriptions in T.S. 5.3.1.

b) Based on higher fuel loadings planned for Cycle 10 ar.d beyond, the borated water storage requirements of T.S. 3.3.1.1 need to be increased.

BWFC final boron results have confirmed that an increased boron concentration (to about 2500 ppm) is necessary for the BWST as part of the ECCS.

(Note: these results have also confirmed the current Core Flood Tank minimum boron concentration requirement of 2270 ppm (T. S. 3.3.1.2)).

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

a) Per 4a and 4b above, a GPUN TSCR for the changes to T.S. 6.9.5.2, T.S.

5.3.1 and 3.3.1.1 was submitted on June 7, 1993.

6.

Important licensing considerations associated with refueling, e.g. new cr different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

a) BWFC and GPUN have completed the fuel cycle design for cycle 10, which is scheduled for startup in October 1993. As stated in 4a above, this design incorporates reload fuel that contains urania-gadolinia. The NRC SERs approving GDTACO and NEMO Rev1 support the TMI-1 reload schedule.

l b) TMI-1 will use the new Mark B9 fuel assembly in the Cycle 10 reload batch. This design is an upgrade of the Mark B8 assembly used in Cycles 8 and 9.

The Mark B9 provides improved fuel thermal limits (LOCA, DNBR, 6

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CFM) and repair capabilities. The Mark B9 design meets current BWFC fuel design criteria and has been used previously at other B&W 177 FA plants.

Since the Mark B9 was designed to meet the BWFC design criteria approved in BAW 10179, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses", it is expected to be implemented in Cycle 10 under 10 CFR 50.59 guidelines.

c) The B&W Model B container is restricted to one fuel assembly per container when enrichment exceeds 4.6 wt/o U".

To preserve TMI-1 shipments with two fuel assemblies per container, BWFC submitted a criticality analysis in May demonstrating the applicability of the B&W Model B container for two-FA shipments of fuel up to 4.8 wt/o U" for a one-time-only special approval. This was approved by the NRC with a limited duration authorization which expires on September 30, 1993.

Cycle 10 fuel shipments started in June 1993 and were completed in July 1993.

d) GPUN will continue to improve the review process by submittal of Technical Specification changes concerning the reload-related areas of fuel assembly reconstitution and removal of cycle-dependent core limits to the Core Operating Limits Report (COLR).

1) GPUN has withdrawn TSCR No. 200 to modify the THI-1 Technical Specifications to permit the substitution of Zr-4 or stainless steel replacement rods for failed fuel rods, in accordance with USNRC Generic Letter 90-02, dated February 1, 1990. Generic Letter 90-02, Supplement I was issued on July 31, 1992, to clarify limitations on the application of currently-approved analytical methods and withdraw and replace the model TS recommended by Generic Letter 90-02. The B&W Owners Group Topical Report BAW-2149, " Evaluation of Replacement Rods in BWFC Fuel Assemblies", December 1991, was approved in April 1993. This report justifies the use of up to ten replacement stainless steel rods located anywhere in a single fuel assembly based on currently-approved methodology.

BAW-2149 provides the basis for reconstitution repairs of BWFC Mark B assemblies to be done under the provisions of 10 CFR 50.59 (i.e., the repair does not represent an unreviewed safety question). A new TSCR will be submitted in August 1993 in response to Generic Letter 90-02, Supplement I referencing BAW-2149.

2)

B&W Owners Group Topical Report BAW-10179P, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses", February 1991, was approved in March 1993. This topical provides a basis for changes to l

cycle-specific limits and to the Mark B fuel design to be under the provisions of 10 CFR 50.59. Per NRC Generic Letter (GL) 88-16, BAW-10179P also provides the basis for removal of additional cycle-specific limits from the T. S. to the COLR. A TSCR will be submitted in August 1993 consistent with GL 88-16 and the BAW-10179P Safety Evaluation (March 16,1993) for the removal of cycle-specific protective and maximum allowable setpoint limits for axial power imbalance and other applicable cycle-dependent limits.

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7.' The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 177 (b) 521

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 l

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.

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1 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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