ML20027B510

Monthly Operating Rept for Aug 1982

ML20027B510
Person / Time
Site:	Three Mile Island
Issue date:	09/15/1982
From:	Smyth C GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20027B509	List: ML20027B508 ML20027B510
References
NUDOCS 8209210170
Download: ML20027B510 (6)

Text

. . _

J OPERATING DATA REPORT .

DOCKET NO. 50-289 DATE September 15, 1982-COMPLETED BY C. W. Smyth TELEPHONE /> "4M-M531 OPERATING STATUS Three Mile Island Nuclear Station, Uni: I I. Unit Narae:

August, 1982

2. Reporting Period:

3. Licensed Thermal Power (MWt)

2535 ,

4. Nameplate Rating (Gross MWe):

871 819

5. Design Electrical Rating (Net MWe)

6. Maximum Dependable Capacity (Gross MWe):

840 776

7. Maximum Dependable Capacity (Net MWe):

i

6. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since L.ast Report. Give Reasons:

J

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

10. Reasons For Restrictions,if Any:

t l

}

This Month Yr.-to.Date Cumulatise

11. Hours in Reporting Period 744. 5831. 70104.

12. Number Of Hours Reactor was Critical 0.0 0.0 31731.8 0.0 0.0 839.5

13. Reactor Reserve Shutdown Hours

' 0.0 0.0 31180.9

14. Hours Generator On-Line 00 0.0 0.0

15. Unit Reserve Shutdown Hours

16. Gross Therrnal Energy Generated (MWH) 0.0 0.0 7653,1071.

O. D. 23464330.

17. Gross Electrical Energy Generated (MWH)

u. u. zJe4uua;.

) IS. Net Electrical Energy Generated (MWH) 0.0 0.0 43,5 I 19. Unit Service Factor 0.0 u.o 44.5

20. Unit Availability Factor .

0.0 0.0 43.4

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 41.5

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 50.3

23. Unit Forced Outage Rate

24. Shutdowns Scheduled 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 (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY i INITIAL ELECTRICITY COMMERCIAL OPERATION i

82 0 9 210 l708

• gn, ,

4

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 UNIT E -I Sept. 15, 1982 DATE COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 August, 1982 MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe Nets

! O 1; _

0 2 0 18 0 3 0 19 0

4 0 0 20 5 0 ,,

o 6 0 22 0 7 0 23 0 8 0 24 0 9- 0 0 25 l

0 0 10 26 0

27 0 is* 0 0 25 0

f 13 29 0 14 0 0 30

(

15 0 31 0 16 0 i

..m, - 4.-+ -,- r-..-

DOCKET NO.

50-289 .

UNIT SifUTDOWNS AND POWER REDUCTIONS UNIT NAME W -I DATE Sept. 15, 1982 REPORT MONT11 August, 1982 COMPLETED RY C. W. Smyth 1TLEPHONE (717T 9/48-8551' e,

C F9 m LIC'"5 5. j1, Cause & Corrective g,,

• n, , '. 1>. 53 5

E 7-53

.E ; e Event  :; 7 o.$ Action to

• V

$E 5 j;gg Report sr eN G p, event Recurrence d

8/1/82 y 744 Regulatory Restraint Order 1 9 i I 2 1 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A fquipment Failure (Explain) 1 Manual for Preparation of Data li Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 1-Antomatic Scram. Event ReporI(LERn File (N'JREG-D Regulatory Restriction 4-Ot her (I!xplain) 0161) li-Operator Training & l.icense Examination F-Administrative 5 G-Operatjonal Ee vor (lixplain) Exhibit I - Same Source 11 Other ilixplain)

~

OPERATING SEM:4ARY The unit was shut down the entire report period by order of the NRC.

Tha Reactor Coolant System was partially drained to permit continued inspections of the OTSG's. Core cooling was provided by the decay heat removal system.

MAJOR SAFETY-RETATED MAINTENANCE Restart modifications continued through the month. Other maintenance included the following:

1. The once-through steam generator (OTSG) program continued with eddy current testing on both the "A" and "B" generators.

Additional testing performed this period included cal rad heater testing and crevis hunidity tests.

2. The replacement of valve WDL-V-307 was completed, with all g

NDE and operational tests being performed satisfactorily.

3. A scheduled decay heat (Loop "A") outage commenced with the repacking of various valves, cleaning and resetting of various relief valves, electrical PM's (breaker testing, meggering, oil changes and greasing), instrumentation calibrations (tech spec and PM) and the following major maintenance items:

a. DC-C-2A

1. Performed leak check on tubes.

2. Cleaned tubes, end covers and water boxes.

3. Applied PC-7 and coal tar Epoxy on end covers and water boxes.

4. Installed m. Inesium anodes on end covers.

b. DC-C-1A

1. Cleaned inlet / outlet flanges and rep?. aced gaskets to repair leaks.

c. DH-S-1

1. Cleaned strainer.

2. Repaired threaded pipe 3eaks.

o

d. Dil-P-1A

1. Repaired threaded pipe leaks.

2. Replaced threaded pipe on pump casing and seal. welded.

3. Commenced mechanical seal replacement. Will continue into next month.

4. Reactor building ventilation fan (AH-E-1) work continued with

, the following work _ accomplished

a. AH-E-1B

1. Balanced in fan unit.

2. Satisfactory testing of motor in fan unit.

b. AH-E-1A

1. Sandblasted and painted motor.

2. Manufactured and' installed dry seal.

3. Overhauled motor.

4. Shop balanced.

5. Shop tested.

6. Installed motor in fan unit.

5. Auxiliary and fuel-handling ventilation fan (AH-E-14) work commenced with the following work accomplished:

a. AH-E-14C

1. Sandblasted and painted motor.

2. Overhauled motor.

3. Mounted motor in test stand and bump tested.

__m_

. REFUELING INFORf4ATION REQUEST

1. Name of Facility:

Three Mile Island Nuclear Station, Unit 1

2. Scheduled date for next refueling shutdown:

Unknown 3 Scheduled date for restart following refueling:

Unknown L. .Will refueling or resumption of operation thereafter require a technical specification change or other license amend =ent?

If answer is yes, in general, whst vill 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 f.

I 5 Scheduled date(s) for submitting proposed licensing action and supporting i

information:

i i N/A i

j 6. Important licensing considerations associated with refueling, e.g. new j or different fuel design or supplier, unreviewed design or performance j analysis methods , significant changes in fuel design, new operating

. procecures:

i N/A ,

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

, storage pool:

(a) 177

(

(b) 208 l 8. . The present licensed spent fuel pool storage capacity and the si::e of l any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

l 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 j capacity (177 fuel assemblies).

_ ._ . . , - _ _ _ _ - _. _ _ - - -