ML20044D633

Monthly Operating Rept for Apr 1993 for TMI-1.W/930513 Ltr

ML20044D633
Person / Time
Site:	Three Mile Island
Issue date:	04/30/1993
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-93-2077, NUDOCS 9305200074
Download: ML20044D633 (8)

Text

GPU Nuclear Corporation G U Muclear ""a'"Jntr*

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

(717) 948-8005 May 13, 1993 C311-93-2077 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subjer.t: Three Mile Island Nuclear Station, Unit I (TMI-1)

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

Sincerely, xb T.G.Broutjhton j Vice President and Director, TMI-1 l

l WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector l

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9305200074 93o43o ,

kDR ADOCK 0500 I

[] 9 GPU Nuclear Corporation is a subsid;ary of General Pubhc Utthties Corporation I l

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i OPERATIONS

SUMMARY

i April 1993 l The plant entered and ended the month operating at 100% power producing 860 .

MWe. '

MAJOR SAFETY RELATED MAINTENANCE  !

l During April, the following major safety related maintenance was performed:  !

Make-up System Control Valve MU-V-17 l After the air actuator and internals were removed from MU-V-17, an inspection  !

l of the piping upstream of the valve was performed. Small metallic particles  !

! were retrieved from the upstream piping and sent to the GPUN System Laboratory l

for analysis to determine their origin. To assure that proper RCS make-up {

flow is maintained, the original valve stem was machined to open the.

clearances between the lobes and the seat retaining guide. The valve actuator j was rebuilt using a new stem, diaphragm and adjusting nuts and was reinstalled on the valve. The valve was satisfactorily stroke tested and returned to service.

Station Blackout Diesel A c Start Comoressor EG-P-11B l The Station Blackout Diesel air start compressor EG-P-IIB was removed from ,

service because of sticking unloader valves and internal noises indicating an [

additional problem. The high pressure piston, its piston rings and connecting  ;

rod were worn. The worn parts were replaced and new low pressure piston rings -

were also installed before the unit was reassembled. The compressor was ,

reinstalled and returned to service after satisfactory completion of post l maintenance testing. i Emeraency Diesel Fuel Oil Flow Indicator DF-FI-1151 i The indicator was replaced because of erratic indication during operation. A spare flow indicator was installed and put in service.

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l OPERATING DATA REPORT DOCKET NO. 50-289 DATE May 13, 1993 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: APRIL 1993 l l

3. LICENSED THERMAL POWER: 2568 l l

4. NAMEPLATE RATING (GROSS MWe): 871 l l S. DESIGN ELECTRICAL RATING (NET MWe): 819 l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 834 l l

7. MAXIMUM DEPENDABLE CAPACITY (FET 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 (NET MWe):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMMULATIVE

-- _=__ _=_= .-- -- . -.....

II. HOURS IN REPORTING PERIOD (HRS) 719.0 2879.0 163584.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 719.0 2813.3 88290.0

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

14. HOURS GENERATOR ON-LINE (HRS) 719.0 2809.3 87209.4

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1569151 6853478 212900183

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 614808 2396297 71741371

18. NET ELECTRICAL ENERGY GENERATED (MWH) 580599 2258792 67361099

19. UNIT SERVICE FACTOR (%) 100.0 97.6 53.3

20. UNIT AVAILABILITY FACTOR (%) 100.0 97.6 53.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 102.7 99.8 52.4

22. UNIT CAPACITY FACTOR (USING DER NET) 98.6 95.8 50.3

23. UNIT FORCED OUTAGE RATE (%) 0.0 2.4 41.1 UNIT FORCED OUTAGE HOURS (HRS) 0.0 69.7 60759.4

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

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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 UNIT TMI-1 DATE May 13, 1993 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 HONTH: APRIL i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-NET) (MWe-NET) 1 807 17 806 2 809 18 808 3 811 19 804 4 813 20 802 5 812 21 805 6 811 22 814 7 810 23 809 l

8 808 24 811  !

9 805 25 805 10 804 26 806 11 807 27 813 12 809 28 811 13 809 29 808 14 808 30 805 15 800 31 NA 16 796 a

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-289 UNIT NAME THI-l REPORT MONTH April 1993 DATE May 13, 1993 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 Method of Licensee System :orrponent Cause & Corrective No. Date type' Duration Reason' Shutting Event Code Code Action to (Hours) 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 8-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File (NUREG-0161) 4 Other (Explain)

D-Regulatory Restriction E Operator Training & Licensing Examination 5 Exhibit 1 same source F- Achinistrative G-Operational Error (Explain) 6 Actually used exhibits F & 11 NUREG 0161 M Other (Explain) 5

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REFUELING INFORMATION RE0 VEST

1. Name of Facility: Three Mile Island Nuclear Station, Unit 1 l c

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) l 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 i Acceptable Cycle Reload Analyses", which includes the new physics i methodology BAW-10180, Rev.1, WEMO by reference, BAW 10179 will replace 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  ;

Reactor Core fuel descriptions in T.S. 5.3.1. l t

b) Based on higher fuel loadings planned for Cycle 10 and 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. 7

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

information:

a) Per 4r 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 will be submitted in May 1993 (this was previously i estimated to occur in April).

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! 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:  ;

a) BWFC and GPUN have completed the fuel cycle design for cycle 10, which is i scheduled for startup in October 1993. As stated in 4a above, this 1 design incorporates reload fuel that contains urania-gadolinia. Use of l urania-gadolinia fuel will need to be supported by approval of BWFC topical reports on reload design methods revisions that account for the Gd effects in the analyses. The NEMO, Rev 1 physics code, noted above, has been approved. Approval of BAW-10184P, GDTACO is also required to support fuel thermal analysis. To ensure that no delays occur to reload analyses, fuel manufacturing and plant startup schedules, approval of 6

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l these topicals was requested for April 1,1993. In subsequent discussions, the USNRC comitted to a completion date for GDTACO of May 1993 with review started early enough to identify any major concerns by March. It is GPUN's understanding that no major NRC concerns have been identified to BWFC to date and that the review is on schedule for May ,

completion.

. b) TMI-I 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, CFM) and repair capabilities. The Mark B9 design meets current BWFC fuel design criteria and has been used previously at other BLW 177 FA plants.

c) BWFC has a licensing change under USNRC review for certification of the Siemens fuel assembly shipping container design for shipment of two BWFC Mark B fuel assemblies up to 5.0 wt/o U"'. This change is necessary to support the TMI-1 Cycle 10 fresh fuel receipt by reducing the number of fuel shipments and fuel handling activities. The risk of fuel damage is  !

also minimized. Based on the 12/3/93 BWFC/NRC meeting on this issue, approval had been expected by March 1993. Expected approval was then deferred to early May 1993 due additional information submitted by BWFC at NRC request. However, GPUN understands that BWFC received a further reviewer request for information in April and the expected approval date is now unknown. As a further effort to preserve shipments with two fuel .

assemblies per container, GPUN understands that BWFC intends to submit 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. Cycle 10 fuel shipments will start in .

June 1993.

dl) GPUN will continue to improve the review process by submittal of a i Technical Specification change concerning the reload-related areas of fuel assembly reconstitution and removal of cycle-dependent core limits to the Core Operating Limits Report (COLR). A TSCR review completion date ,

consistent with the next TMI-1 refueling outage in September 1993 will be  :

requested. GPUN has withdrawn TSCR No. 200 to modify the TMI-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 1 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 repai: does not represent an unreviewed safety question). A I new TSCR will be submitted in June 1993 in response to Generic Letter 90-02, Supplement I referencing BAW-2149.

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t d2) 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 the basis for changes to 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 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.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel l storage pool: (a) 177 (b) 521 ,

8. The present licensed spent fuel pool storage capacity and the size of any l 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 l full licensed capacity will be attained.

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9. The projected date of the last' refueling that caa be discharged to the spent '

i 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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