ML19345G812

Monthly Operating Rept for Mar 1981

ML19345G812
Person / Time
Site:	Three Mile Island
Issue date:	04/15/1981
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19345G809	List: ML19345G808 ML19345G812
References
NUDOCS 8104220419
Download: ML19345G812 (5)

Text

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OPERATING DATA REPORT .

' DOCKET NO. 50-280 DATE 4-15-81 COMPLETED BY D. C. Md:chell TELEPHONE

'" 4' ***'

OPERATING STATUS ee le Island Nuclear Station, Ud: I

1. Unit Name:

2. Reporting Period: MCh1 A1 2535 .

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

OU

5. Design Electrical Rating (Net MWe):

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

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions,If Any:

This Month Yr.-to-Dat e Cumulatise 744. 2160. s7A71.

11. Hours in Reporting Period 0.0 0.0 32731.8

12. Number Of Hours Reactor Was Critical g3o,5 0.0 0.0

13. Reactor Reserve Shutdown Hours 3118o,9 0.0 0.0

14. Hours Generator On-Line U*U 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 7653,1071.

0.0

16. Gross Thermal Energy Generated (MWH) O' 20*o"33v-

~0*

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u. g j o.u u a .2 .

18. Net Electrical Energy Generated (MWH) 0.0 0.0 54.1

19. Unit Service Factor 0.0 0.0 54.1

20. Unit A.ai! ability Factor 0.0 0.0 52.6

21. Unit Capacity Factor (Using MDC Net) 50.5 0.0 0.0

22. Unit Capacity Factor (Using DER Net) 38.1 100.0 100.0

23. Unit Forced Outage Rate f 24. ShutdowTis Scheduled Over Next 6 Months (Type.Date.and Duration of Each):

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

26. Units in Test Status (Prior io Commercial Operation): Forecast Achicsed INITIA L CRITICA LITY INITIA L ELECTRICITY l

( COMMERCIAL OPERATION Wm o , na o9 0419

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AVER AGE D AILY L' NIT POWER LEVEL DOCKET NO. 289 L' NIT M ~I DATE A-M 1 15. 1981 COMPLETED BY - D. C. Mitchell TELEPHONE (717) 948-8553 MONni W rch 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (Mbe Net) (MWe Net)

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OPERATIONS SLM'.*aY The Unit was shutdown the entire month by order of the NRC. The Reactor Coolant System was cooled using the Decay Heat Removal System during the entire period.

MAJOR SAFETY RELATED MAINTENANCE During the month the Unit remained in cold shutdown while restart activities progressed. The following major maintenance items were perfo rmed.

A. Nuclear Services - River Water Pump overhaul (NR-P-1B)

B. Snubber Tech Spec Surveillance C. Local Leak Rate Surveillance Testing D. Decay Heat Pump remote vent tie-in E. Borated Water Storage Tank work Overhaul of the river water pump (NR-P-13) included removal of motor, disassembly of pump, inspection of pump parts, reassembly of pump, installation of motor, motor to pump alignment, and testing J of pump (IRD readings) . Testing was performed with satisfactory I i results. ,

Snubber testing (Refueling Outage Surveillance) was completed during March. The snubber-work included removal of snubbers, testing, repairing leaks, minor bleed rate adjustments and reinstallation of snubbers. Problems encountered were reported in Licensee Event Reports 81-02 and 81-04. 1 Local leak rate testing progressed through the month with one (1) i Liquid Waste Disposal System Valve identified as requiring main-tenance work. This valve will be repaired at a later date.

The restart modification on the Decay Heat Pumps remote 2n system was installed, flush performed, and leak checked with satisfactory 1 results. ,

Work on the Borated Water Storage Tank eight (8) inch recire line l flanga and twenty-four (24) inch spool piece started with the following items being performed: ,

! 8 Inch Flange l a. Bolts / nuts removed

b. Flange seating surfaces inspected j c. New gasket installed

! d. Bolts torqued Following this work, minor leakage remained that is expected

to be corrected by adjustment of the respective pipe hangers.

24 Inch Spool 1

i

a. Existing spool piece removed

b. Flanges removed from pipe

c. Pipe preped for fitup of new spool The remaining work will continue next =onth.

L

REFUT !NG INFORMATION RE01*EST

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 de er=ine whether any unreviewed safe:y questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

If no such review has taken place, when is 1: 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 ana2ysis 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 tha: has been requested or is planned, in number of fuel assemblies:

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

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

1986 is the last refueling discharge which allows full core off-load capacity (177 fuel asse=blies).

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