ML20052G175

Monthly Operating Rept for Mar 1982

ML20052G175
Person / Time
Site:	Three Mile Island
Issue date:	04/15/1982
From:	Smyth C GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20052G172	List: ML20052G171 ML20052G175
References
NUDOCS 8205140375
Download: ML20052G175 (5)

Text

.

e OPERATING DATA REPORT -

DOCKET NO. 50-289

• DATE April 15. 1982 COMPLETED BY C. E Smyth TELEPHONE 'H W -8551 OPERATING STATUS Three P.ile Island Nuclear Station, Unit I

1. Unit Name:

2. Reporting Period: Mareh. 1982

3. Licensed Thermal Power (MWt):

2535 .

871

4. Nameplate Rating (Gross MWe):

019

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): {0

7. Maximum Dependable Capacity (Net MWe):

ie6 _

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted.lf Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cumulatise 744. 2160. 66433.

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 0.0 0.0 33731.8 0.0 0.0- 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9

14. Hours Generator On Line U*U 0.0 0.0

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 0.0 0.0 76531071.

U* U* # 0"33U*

17. Gross Electrical Energy Generated (MWH)

u. u. me .

18. Net Electrical Energy Generated (MWH)

?.0 0.0 46.9 l 19. Unit Senice Factor U*U U*U 4D 9 l 20. Unit Availability Factor 0.0 0.0 45.7

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 43.8

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 47.3

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

, 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITI A L CRITICALITY j INITIAL ELECTRICITY COMMERCI A L OPER ATION i

l K0 PDR R

.. -- _-_ ___ ~. . _ . _ _ - , - - - _ _ . _ _ ._ _ _ _ -_ _ _ . - _ . . _.

M AVER AGE D AILY UNIT POWER LEVEL DOCKET NO. 50-289 nII~I E'IT April 15, 1982 DATE COMPLETED BY C. k'. Smyth TELEPHONE (717) 948-8551 March, 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Neo (Mbe Net 1

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6 0  :: 0

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9 25 0 0 0 10 26 0

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. OPERATfNG

SUMMARY

o The Unit was shutdown the entire report period by order of the WRC. Core cooling was provided by the Decay Heat Removal System. The RCS was partially drained the entire month to permit OTSG tube inspections.

MAJOR SAFETY RELATED MAINTENANCE In addition to continuing work on restart modifications, the following maintenance work was performed:

OTSG Inspections

1. Templates fabricated and installed for Westinghouse tube plugging.

2. Installed ninety-one (91) Westinghouse plugs on RC-H-1A.

3. Installed forty-six-(46) Westinghou e plugs on RC-H-1B.

4. Continued Eddy Current Testing.

Reactor Vessel Intervals Inspection Preparations for Reactor Vessel Head Removal progressed with the following work accomplished:

1. APSRs and CRDMs uncoupled and parked.

2. Spare Reactor Vessel 0-rings inspected and accepted for use.

3. Disconnected power cables, thermocouple cables, and position indicating cables from control rod drives.

4. Disconnected and removed cooling water lines to head area.

5. Detensioned Reactor Vessel Head.

6. Lead screw inspection in support of Unit 2 Reactor Vessel Head Intervals Inspection work.

i

7. Reactor Vessel Insulation removed.

l

' HPI Thermal sleeve Inspections l

RT and UT inspections of the High Pressure Injection Line Thermal Sleeves were performed (see IE Notice 82-09 dated 3/31/82). No abnormal indications were

observed.

i

! EG-Y-1B l

Emergency Diesel Generator lB work was accomplished and the unit was returned to service. The modification of the air intake line to the supercharger is still required, however, acceptable vibration levels have been reached through modification of the exhaust piping.

i

. NS-C-lD Nuclear Service Heat Exchanger,ID tube leaks were identified while placing the cooler in cervice. The cooler was removed from service, the end covers removed, and a leak test was performed. Two tubes were found to be leaking. The cause of the leaks were under investigation at the end of the report period.

AH-E-1 High vibration was encountered on Reactor Building Recire. Fan AH-E-1. The motor was removed and repair work initiated. The fan was removed from service at the end of the report period.

WDG-V-4 Waste Gas Disposal Valve WDG-V-4 was found to have a crack indication on the nipple. The nipple was removed and a new one installed. PT inspections of all welds verified satisfactory weld results.

REFUEU EG IE70EATION REOUEST

1. Name of Facility:

Three Mlle Island Nuclear Station, Unit I

2. Scheduled date for next refueling shutdown:

Unknown

3. Scheduled date for restart following refueling:

Unknown

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If answer is yes, in general, what will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Com=ittee to determine whether any unreviewed safety questions are associated with the core reload 4

(Ref. 10 CFR Section 50.59)?

If no such review has taken place, when is it scheduled?

Amendment No. 50, Cycle 5 reload, was approved on 3-16-79.

5. Scheduled date (s) for sub=1tting proposed licensing action and supporting-information:

9 N/A

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:

N/A

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

(a) 177 (b) 208

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 asse=blies:

The present licensed capacity is 752. There are no planned increases at this time.

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

1987 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

. . . . _ . - . , . .