ML19318A412

Monthly Operating Rept for May 1980

ML19318A412
Person / Time
Site:	Three Mile Island
Issue date:	06/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19318A411	List: ML19318A410 ML19318A412
References
NUDOCS 8006200496
Download: ML19318A412 (5)

Text

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l

. 4 O OPERATING

SUMMARY

l Repairs of IGSCC indications in the "A" Decay Heat string were completed and following the appropriate testing, the system was declared operable. At the end of the month, with both Decay Heat strings operable, the Reactor Coolant System was drained down to a level that will permit the installation of a high pressure in-jection cross-connect. While the system is drained, a sampling of tube inspections will be performed on the "B" OTSG and the Reactor Coolant System check valves will be inspected and re-paired as necessary.

MAJOR SAFETY RELATED MAINTENANCE During this month, the Unit operated in the cold shutdown condition.

Restart modification activities were in progress. Major maintenance activities are as follows:

Decay Heat Loop "A" weld repair on the suction line to the "A" Decay Heat Pump (D-Il6) was performed. This repair was performed with Decay Heat Loop "B" in oper-ation.

Work on D-116 included:

1. Weld indication was cut.

2. Weld preps performed.

3. Dutchmen fitup to pipe.

4. Cleanliness and fitup inspections.

5. Root / Hot pass weld performed.

6. Information x-ray of hot /rcot pass.

7. Weed-out of welds.

8. Final x-ray of weed-out.

This work was performed with satisfactory results.

8006200yqg

OPERATING DATA REPORT

• DOCKET NO. 50-289 DATE June D. 1980 COMPLETED BY n. c. Mitchell TELEPHONE (71 % 921-6579 -

OPERATING STATUS .

1. Unit Name:

Three Mile Island Nuclear Station Unit I

• May 1980

2. Reporting Period:

2535 .

, , 3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe): .

819

5. Design Electrical Rating (Net MWe):

840

6. Maximum Dependable Capacity (Gross MWe):

776

7. Maximum Dependable Capacity (Net MWe):

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

9. Power LevelTo Wluch Restncted,if Any (Net MWe):

1 10. Reasons For Restrictions.If Any:

i Dia Month Yr to Date Cumulative 79n_ 3623. 50352.

11. Hours la Reporting Period 0.0 0.0 31731,8

12. Number Of Hours Reactor Was Critical 0. O. 838.5

13. Reactor Reserve Shutdown Hours 31180,9 0.0 0.0

14. Hours Generator On-Line 00 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 76531071.

0.0

16. Grom Thermal Eaergy Generated (MWH) U48433u.

U* 0.

17. Grom Electrical Energy Generated (MWH) u.

u. 4as4uusa.

18. Net Electrical Energy Generated (MWH) 0.0

19. Unit Service Factor 0.0 61 0.0 u.0 61.9

20. Unit Availability Facta, 0.0 0.0 60.1

21. Unit Capacity Factor (Using MDC Net) 57.8 0.0 0.0

22. Unit Capacity Factor (Using DER Net) 27.4 1

100.0 100.0

23. Unit Forced Outage Rate

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

l

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

26. Units in Test Status (Prior io Commercial Operation): Forecast Actueved )

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i (9/77)

.1 I

i

- - .,- - - - - , . ., . , . . . . , . - --,...,n- - - , , , - - .-.--. . ,,

?f i

AVERAGE DAILY UNITPOWER LEVEL DOCKET NO. 50-289 TMI-I UNIT l June 15, 1980 DATE l

COMPLETED BY D C. Mitchell hl TELEPHONE (215) 921-6579 l

l MONTH May 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) IMWe-Net) 1 0 17 ,,_

0 2 0 gg a 3 0 y, o 4 0 0 3

5 0 21 0

6 0 22 0 7 0 n 0 )

8 0 0 f 24

, 0 0 0 10 26 0

' 27 0 0

3 ~3 28 0 0

13 29 0

'14 0 0

- 30 I3 31 0 16 0 A

, . l

DOCKET NO.

50-289 UNITSHUTDOWNS AND POWER REDUCTIONS UNIT NAME TML-I DATE June IL 10A0 COMPLETED BY D C Mieche11 REPORTMONTH May 1980 TELEPHONE (215) 921-6579 "t. '

c es 3 se 3 Ev h Cause & Corrective

.2 _e f Licensee 4

. No. Date M } .s g M Event Ei 3 Action to

• {

3

$ ~g Report * '50 Prevent Recurrence cE j (5 = [O -

2 Reguistory Restraint Order 1 5/1/80 F 720 D 1 i 2 3 4 l F: Forced Reason: Method: Exhibit G. Instructions J S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee Event Report (LER) File (NUREG-

, C Refueling 3 Automatic Scram.

l D Regulatory Restriction 4 Other (Esplain) 0161)

E Operator Training & License Examination 1 F Administrati.e 5 -

G Operptional Errur (Esplain) Exhibit I Same Source l

ll Other (Esplain) j .

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

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'11 censed 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:

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

__ ~. _.