ML20058M496
| ML20058M496 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/30/1993 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-93-2172, NUDOCS 9312210008 | |
| Download: ML20058M496 (8) | |
Text
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GPU Nuclear Corporation E s Nuclear
- e;t 388 o
Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
(717) 948-8005 December 13, 1993 C311-93-2172 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. OPR-50 Docket No. 50-289 Monthly Operating Report for November 1993 Enclosed are two copies of the November 1993 Monthl) G 3 rating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely,
/
T. G. Bro,hton Vice President and Director, TMI-1 WGH Attachments cc: Administrator, Region I lMI Senior Resident Inspector n<nn'i 9312210008 931130 Q
PDR ADOCK 05000289 i;
R Pnn tid GPU Nuclear Corporation is a subsidiary of General Pubhc Ulikties Corporation
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OPERATIONS
SUMMARY
November 1993 The plant entered the month operating at approximately 100% power. On November 4, the failure of a suction isolation valve on one main vacuum pump led to a partial loss of main condenser vacuum. Operators reduced power to
=75% and manually closed the valve. The plant returned to full power about three hours later. The isolation valve's solenoid operator was later repaired. On November 14, the plant was taken off-line and brought to _a hot shutdown condition in an effort to reseat Pressurizer Code Safety Relief Valve RC-RV-1B which was leaking by the seat. Minimal success was achieved by efforts to reseat the valve and on November 15, the plant was taken to cold shutdown to replace the valve. Following RC-RV-1B replacement and other miscellaneous outage maintenance activities, the plant returned to power operation on November 19. The plaat electrical output averaged approximately 779 MWe while the unit was on-line during the period.
MAJOR SAFETY RELATED MAINTENANCE During November the following major safety related maintenance was performed:
Pressurizer Code Safety Relief Valve RC-RV-1B On 14 November, the turbine was taken off-line and the plant' brought to hot shutdown to try to reseat Pressurizer Code Safety Relief valve RC-RV-1B which was leaking by its seat. Using the valve lift lever, personnel initiated several manual lifts in an attempt to reseat the valve but it continued to leak. The plant was cooled down until cold shutdown conditions were attained and the RCS drained to allow RC-RV-1B replacement. The leaking valve was removed and replaced with a previously rebuilt and tested valve.
Following plant heatup, the RCS was pressurized to 2285 psig and Operations' personnel verified that there was no leakage.
Reactor Coolant 'B' Loop Cold Lea RTD RC5B-TE4 With the RCS depressurized for RC-RV-1B replacement, the RCS 'B' Loop cold leg was drained to repair a minor gasket leak on RTD RC5B-TE4.
The RTD and well were removed. The threads were cleaned on both components and a new gasket l
was installed.
Following reinstallation of the RTD and primary plant pressurization, RC5B-TE4 tested satisfactorily with no leakage evident.
1 2
Reactor Coolant Pump RC-P-1A/B/C/D Motors Reactor Coolant Pump Motor work accomplished during the outage included: the repair of minor oil leaks at mechanical fittings on all four pump motors, addition of oil to the reservoirs and balancing the motors of the 1A and ID pumps, and replacement and regapping of the proximity probes on the 1A pump motor.
Hiscellaneous Outage Repair Work The following miscellaneous work items were accomplished while the plant was off-line at cold shutdown:
- Replaced 6th stage drains collection tank relief valve HD-V-29.
- Repaired a tubing leak at instrument valve FW-V-1104.
j
- Replaced pump EHC-P-1B with a reconditioned pump.
- Repaired pipe plug leaks on Main Turbine Intercept valve TG-ICV-3.
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- Adjusted packing and replaced the air operator pilot valve on valve MU-V-3.
- Added packing to valves EX-V-2B and EX-V-11A.
- Replaced the spring on relief valve HV-V-15A.
- Replaced 104 capacitors in the Integrated Control System.
- Changed oil on Heater Drain pumps HD-P-1A/B/C.
- Replaced position indicator tubes on CRDM Group 2/ Rod 1 and Group 5/
Rod 8.
- Adjusted the position indicator tube on CRDM Group 7/ Rod 3.
- Replaced the Main Condenser ' A' Amertap flap motor.
- Replaced the operat; r diaphragm on valve MU-V-17.
- Replaced the amplif t on Loose Parts and Vibration Monitor Channel 2.
- Repaired a leak-off itting on RC-P-1A #3 seal.
- Retorqued OTSG RC-H-1B lower handhole studs.
- Replaced a module that had been giving improper light indications on HSPS 68/69 indicators.
- Repaired a tubing fitting leak on Main Generator Turbine Control valve TG-CV-3.
- Plugged and stabilized nine tubes in the Main Condenser 'A' side North waterbox due to erosion thinning and leakage on one of the nine tubes.
One leaking tube was plugged in the south waterbox.
- Replaced the solenoid valve on Feedwater Valves FW-V-16A/B and reconfigured tubing to obtain the proper response time.
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l OPERATING DATA REPORT l
DOCKET NO.
50-289
.i DATE December 13, 1993 COMPLETED BY W G HEYSEK l
i l
OPERATING STATUS TELEPHONE (717) 948-8191
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 l NOTES:
l
- 2. REPORTING PERIOD:
NOVEMBER 1993 l
l
- 3. LICENSED THERMAL POWER:
2568 l l-
- 4. NAMEPLATE RATING (GROSS MWe):
871 l l
j
- 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
l I;
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
- 11. HOURS IN REPORTING PERIOD (HRS) 720.0 8016.0 168721.0 1
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 605.4 7005.4 92482.2
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0
-0.0-2283.8
- 14. HOURS GENERATOR ON-LINE (HRS) 600.6 6960.6 91360.7 l
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0 l
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1534020 16913053 222959758 i
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 516111 5697734 75042808
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 484275 5353760 70456067
- 19. UNIT SERVICE FACTOR
(%)
83.4 86.8 54.1
- 20. UNIT AVAILABILITY FACTOR
(%)
83.4 86.8 54.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 85.6 85.0 53.1
- 22. UNIT CAPACITY FACTOR (USING DER NET) 82.1 81.5 51.0
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 1.0 39.9 UNIT FORCED OUTAGE HOURS (HRS) 0.0 69.7 60759.4 j
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
J
(
i
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
4 i
)
1 AVERAGE DAILY UNIT POWER LEVEL t
DOCKET NO.
50-289 UNIT TMI-1 DATE December 13, 1993-COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191
.i MONTH:
NOVEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j
(MWe-NET)
(MWe-NET) 1 817 17
-14 l
2 818 18
-41
]
3 817 19 421 4
805 20 816 5
811 21 819 6
816 22 817 I
7 820 23 817 8
820 24 817
]
9 820 25 820 i
10 819 26 821 11 818 27 814 12 814 28 811 j
13 817 29 819 i
14 240 30 816 15
-15 31 NA 16
-12 1
5
)
4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NAME TMI-1 REPORT MONTH November 1993 DATE DOCember 13, 1993 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 om a t u-o c.
yy,,e Demthen huma#
mamsg Code M""
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No.
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- as 93-06 11-4-93 F
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1 None SH ISV Failure of a suction isolation valve on one main vacuum pump led to a partial loss of main condenser vacuum. Operators reduced power.to ~75% and manually closed the valve.
The plant returned to full power about three hours later. The isolation valve's solenoid operator was later repaired.
93-07 11-14-93 S
119.4 A
1 93-008 AB RV Seat leakage on the
'B' Pressurizer Code Safety Valve had been worsening since the beginning of the operating cycle. The outage was scheduled for replacment of the valve. The replacement valve was verified not to be leaking at 2285 psig. The plant returned to power operation on November 19, 1993.
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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:
September 8, 1995
- 3. Scheduled date for restart following current refueling: NA l
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
NO
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
NA 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) GPUN will continue to improve the review process by submittal of l
Technical Specification Change Requests (TSCR) 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 withdrew 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 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 i
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). TSCR 232 was 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 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. TSCR 234 was submitted in November 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.
7
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- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel j
storage pool:
(a) 177 (b) 601
- 8. The present licensed spent fuel pool storage capacity and the size of any-1 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 i
full licensed capacity will be attained.
]
1
- 9. The projected date of the last refueling that can be discharged to the spent I
fuel pool assuming the present licensed capacity:
'l 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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