ML20070F744

Monthly Operating Rept for Nov 1982

ML20070F744
Person / Time
Site:	Crane
Issue date:	12/15/1982
From:	Smyth C GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20070F737	List: ML20070F734 ML20070F744
References
NUDOCS 8212210234
Download: ML20070F744 (6)

Text

. _.

OPERATING DATA REPORT DOCKET NO.

50-289 DATE December 15, 1982 COMPLETED BY C. W. Smyth TELEPHONE

'1 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

2. Reporting Period:

Novembe.r, 1982 2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

019

5. Desien Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): f0

/76

7. Maximum Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Siner Last Report.Gise Reasone

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

10. Reasons For Restrictions.lf Any:

This Month Yr..to.Date Cumulatne 720.

8016.

72289.

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critica!

0.0 0.0 31731.8

13. Reactor Reserve Shutdown Hours 0.0 1.0 840.5 0.0 0.0 31180,9

14. Hours Generstor On.Line 0.0 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Energy Generated (MWH)

O.

O.

2546*33v.

17 Gross Electrical Energy Generated (MWH) u.

U.

a buu m.

IS. Net Electrical Energy Generated (MWH) 0.0 0.0 43.1

19. Unit Service Factor O.U U.U

20. Unit Availability Factor 33,1

21. Unit Capacity Factor IUsing MDC Net) 0.0 0.0 42[1

~

0.0 0.0 40.3

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 52.0

23. Unit Forced Outage Rate

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

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 INITIAL ELECTRICITY COMMERCIAL OPERATION 8212210234 821215 PDR ADOCK 05000289 Pl??i R

PDR

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 THI-I UNIT December 15, 1982 DATE mph COMPLETED BY TELEPHONE (717) 948-8551-November, 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL OfWe-Net)

OfWe Neti I

O 1;

0 0

0 Ig 0

,19 4

0 0

20 5

0 0

22 0

6 0

7 0

0 23 8

0 0

24 0

9 25 0

0 0

10 6

0 27 0

0 12 0

13 29 0

~

0 14 30 0

15 0

0 31 16 0

s 50-289 UNIT Siltl1 DOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N AME MI-I DATE December 15, 1982 COMPl.ETED fly C_._ W._Smy t_h _._

RFPORT MON HI November, 1982 TELEPif0NE (717) 948-8551 "i

c_

ee 3 to 4 6

EX l icensee E t, g4 Cause & Corrective 2e E

7 No.

Date y,

3g g

jg$

Event u7 A'8 Action to

$3

[* @ C R epor t 8' t$0 hU Prevent Recurrence U

6 9

Regulatory Restraint Order 1

11/1/82 F

720 D

1 1

2 3

4 I forscil Reason Methoil:

Eshibit G - Instructions

% Siheiluted A liguiprnent l'ailure(I splain) 1-Mannat for Preparation of Data It-Maintenante or lest 2-Mannal Scram.

Entr> Sheets for 1icensee C Retncling 3 Anfornatic Scram.

Event ReporI (LER) File INUREG-D Regniatory Restriction 4-Other flNplain) 0161)

I' Operator t raining & I icense i samination F A !minisir ite.c 5

G Operatjonal l~ient II.splain)

Inhibit 1 S une Sontce 11 Ottier(rsptiinp

O OPERATING

SUMMARY

Unit I remained in a cold shutdown the entire month by order of the NRC. The Reactor Coolant System remained partially drained to permit repair work on both OTSGs.

Core cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RE1ATED MAINTENANCE In addition to continuing work ontestart modifications, the following mainten-ance activities were performed.

The Once Through Steam Generator (OTSG) program continued with the follow-ing ite=s acco=plished.

1.

RC-H-1A ("A" OTSG)

A.

Crevis drying and dehumidification.

B.

Completed first explosive expansion of approximately 15,270 tubes.

C.

Drained i==unol from generator.

D.

Prepared for tube cleaning and testing.

2.

RC-E-1B ("A" OTSG)

A.

Crevis drying and dehumidification.

B.

Co=pleted first explosive expansion of approximately 15,443 tubes.

C.

Drained i==unol from generator.

D.

Preparations for tube cleaning and testing.

The local Leak Rate Tesring program continued with the following valves testing satisfactorily.

1.

IC-V-2 2.

IC-V-4 3.

IC-V-6 4.

IC-Y-16 5.

WDG-V-3 6.

WDG-V-4 Tne River ir'ater Fire Pump (FS-P-2) overhaul was completed with the pu=n reasse= bled, electric motor reinstalled, and all tests being performed satisfactorily.

~

The WDG-V-4 piping replacement work commensed~ with the prefabrication of piping in prograss.

PT inspections of welds were performed.

A planned building spray outage commensed with the following major work items and inspections being completed.

1.

"A" Loop A.

Drained loop.

B.

Opened valves BS-V-21A/23A for chemistry samples and closed valves.

C.

BS-P-1A work items:

- (l) Removed suction spool piece for chemistry sample and reinstalled.

(2) Repaired various threaded pipe leaks.

(3) Repaired discharge flange leak.

(4) Installed pump shaf t coupling guard.

D.

Repaired flange leak on valve BS-V-34A.

E.

Installed blank flanges at valves BS-V-50A/56A.

F.

Repacked valve BS-V-60A/49A.

G.

Relief valve caintenance BS-V-45A/63A.

2.

"B" Loop A.

Drained loop.

B.

Repacked valve BS-V-3B.

C.

Completed radiography inspections as follows:

(1) B-99 (2)

B-ll (3) BS-FW-301 (4) BS-SW-302 (5) BS-SW-301 (6) BS-SW-303 (7) BS-SW-304 (8) BS-SW-305

-m v

=--

y 4

q REFUELING INFORMATION REQUEST is' l.

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 h.

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

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

If answer is no, has the reload fuel design and cere configuration been reviewed by your Plant Safety Review Co= ittee to detennine whether any unreviewed safety questions are associated with the core reload (Ref. 1C CFR Section 50.59)?

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

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

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

information:

i N/A 6.

Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfor ance analysis methods, significant changes in fuel design, new operating procedures:

N/A I

7 The number of fuel asse=blies (a) in the cere, 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 requected or is

]

planned, in nu=ber 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 assuning the present licensed capacity:

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

-