ML19351E908

Monthly Operating Rept for Nov 1980

ML19351E908
Person / Time
Site:	Three Mile Island
Issue date:	12/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19351E907	List: ML19351E906 ML19351E908
References
NUDOCS 8012190519
Download: ML19351E908 (6)

Text

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OPERATING DATA REPORT -

DOCKET NO. 50-289 DATE December 15, 1980 COMPLETED BY n. c. Mitche'l TELEPHONE D171018-8553 l

OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

I 2. Reporting Period: November. 1980 2535 l 3. Licensed Thermal Power (Mht):

871

4. Nameplate Rating (Gross MWe):

019

5. Design Electrical Rating (Net MWe):

840 l

6. Maximum Dependable Capacity (Gross MWe):

• 776

7. Maximum Dependable Capacity (Net MWe):

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

9. Power Loel To Which Restricted. If Any (Net MWe):

l 10. Reasons For Restrictions.lf Ariy:

This Month Yr.-to-Date Cumulatise 7 . 8040. 54769.

i 11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.8 0.0 q.0 839.5

13. Reactor Reserve Shutdown Hours 31130,9

[' 0.0 0.0

14. Hours Generator On-Line -

U*U C.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Energy Generated (MWF)

O. O. 25484330.

17. Gross Electrica' Energy Generated (MWH)

u. U. ZJd4UU)J.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 56.9

19. Unit Service Factor 0.0 0.0 56.9

20. Unit Availability Factor 0.0 0.0 55.3

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 53.1 j

i 23. Unit Forced Outage Rate 100.0 100.0 34.3

24. Shutdowns Seheduled Over Next 6 Months (Type. Date, and Duration of Each):

~

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

26. Units in Test Status (I'rior eo Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION (u/77) 8012 r905/7 .. . . . ._ .

~. .- ... .

f AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-28h WIT TMI-I DATE December 15. 1980.

COMPLETED BY D G. Mitchell TELEPHONE (717) 0/48 4553 MONTH November, 1980 DAY AVERAGE D. ILY P 'ER LEVEL DAY AVER AGE DAILY POWER LEVEL iMWe Nesi 1 0 17 _

0 2 0 ,g o 3 0 , ,9 o 0 0 4 20 0 2, 0

5 6 0 22 0

7 0 23 0

g 0 24 0

0 0 9 25 0 0 10 26 0

II 27 0 12 0 0 28 33 29 0 I4 30 0 15 0 31 0 16 0

a DOCKET NO. 50-289 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME IMI-I DATE December 15, 1980 COMPLETED BY D. C. Mieche11 REPORT MONTH November TELEPHONE (717) 948-855i

": c e ei _e 3 EIC'"5" Cause & Corrective

! 5d 5%

4 No. Date Il.

f_3$

?ge E Event g7 g gc,;,, ,,

$ 5-C Repost n cr> v O Prevent Recurrence OO $Gj O 6

W

• W Regulatory Restraint Order h d, l~ 11/1/80 F 720 D 1 ,W M

tD M

(C~'O)

(5L, 4

1 2 3 4 F: . Forced Reason: Method: Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LERIFileINUREG-D-Regulatory Restriction 4-Other (Espiain) 0161)

E-Operator Training A License Examination F-Administ rative 5 G-Opergtional Error (Explaint Eshibit 1 - Same Source 11-01her (Explain t e

O

i

• OPERATING

SUMMARY

The Unit was shutdown the entire month with core cooling provided by the Decay Heat Removal System.

At the beginning of the period the Reactor Coolant System was drained to a level of 10 to 15 inches above the centerline of the cold leg to perform maintenance work described below. This work was completed and the system was refilled on November 4, 1980.

During the week of November 17, 1980, the Secondary Plant was placed in service for the first time since shutdown following the Unit 2 accident. The purpose of this operation was primarily for Operations and Maintenance training and equipment checkout. The training value was extremely high and the effect on the morale of Unit 1 personnel was positive and probably the most worthwhile effect gained.

Each shif t was able to perform startup and shutdown evolutions and observe the operation of all secondary systems and major com-ponents except the Moisture Separator Pumps and the Heater Drain Pumps. All equipment operated satisfactorily, however, necessary maintenance work was identified in areas such as powdex vessels, feedwater heater leakage, and cire water tunnel leakage.

A satisfactory vacuum reading of 27.5" hg was obtained and secondary system chemistry was within satisfactory operating levels within a reasonable period of time. Both Steam driven Main Feed Pumps were satisfactorily overspeed tested.

It was concluded that with exception of relatively minor maintenance work, the Secondary System is ready for restart.

MMOR SAFETY RELATED MAINTENANCE New internals were installed in High Pressure Injection (HPI) check valves MU-V-86A/B, 94, 95, 107A/B/C/D. The work involved was as follows.

1. Remove bonnet bolts and bonnet.

2. Take measurements and clean inside valve.

3. Fit machine new internals to valve.

4. Install new internals.

5. Final cleanup.

6. Reinstall seal ring and bonnet.

7. Torque bonnet studs / nuts.

OTSG "A" lower primary manway and lower primary handhole were re-moved for inspection of seating surface due to boron build-up on two of the studs / nuts. This work was performed with loop "A" of the RCS partially drained.

The following work was performed.

1. Clean room installed with particulate filter.

2. Insulation removed.

3. Lower manway studs / nuts removed.

4. Manway lowered in place.

5. Manway diaphragm removed.

6. Lower handhole studs / nuts removed.

7. Handhole removed.

8. Inspection / cleaning of seating surface.

9. Replacing of manway gasket and handhole gasket.

10. Installation of manway and handhole covers.

11. Torque of studs / nuts.

During this evolution, the manway studs were MT with satisfactory

'- results.

During the week of November 17, 1980, the "Z" axis OTSG Auxiliary Feedwater nozzles were inspected as a result of cracking identified at other B&W facilities. No cracking was identified and additional inspections have been deemed unnecessary. _.

On November 8, 1980, the "A" Spent Fuel Cooling piping was drained to permit repair of a weld indication (#104) that was identified in the Intergranular Stress Corrosion Cracking investigation. At the end of November there remained six indications to be repaired before refilling the "A" SF piping.

REFUELING INFORMATION REOUEST

1. Name of Facility:

Three Mile 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 Committee to determine whether any unreviewed safety questions are associated with the core reload (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 submitting proposed licensing action and supporting information:

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 l

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 assemblies:

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:

4 1986 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

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