ML20077H708

Monthly Operating Rept for June 1983

ML20077H708
Person / Time
Site:	Crane
Issue date:	07/15/1983
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
5211-83-202, NUDOCS 8308110230
Download: ML20077H708 (11)

Text

.

OPERATLNG DATA REPORT DOCKET NO.

50-289 DATE July 15, 1983 COMPLETED BY C. W. Smyth TELEPHONE

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v48-8551 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

June, 1983

2. Reporting Period:

3. Licensed T'hermal Power (MWt):

2535 671

4. Nameplate Rating (Gross MWe):

819

5. Design Electrical Rating (Net MWe):

840

6. Maximum Dependable Capacity (Gross MWe):

//6

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions,if Any:

This Month Yr to.Date Cumulatis e 720.

4343.

77376.

11. Hours in Reporting Period

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

13. Reactor Reserve Shutd'own Hours 0.0 0.0 31180.9

14. Hours Generator 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.

2.5454330.

17. Gross Electrical Energy Generated (MWH) u.

u.

ce4vu:23.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 40.3

19. Unit Senice Factor U+U U.0 40.3

20. Unit Availability Factor 0.0 0.0 39.3

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 37.6

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 55.5

23. Unit Forced Outage Rate

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

1

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 INITIA L ELECTRICITY -

COMMERCIAL OPERATION -

gpE 8308110230 830715 l

F/77 6 PDR ADOCK 05000289

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i AVER AGE D AILY UNIT POWER LEVEL DOCKET NO.

50-289

" -I UNIT July 15, 1983 DATE COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 MONTH June, 1983 DAY AVERAGE D IL P WER LEVEL DAY AVER AGE DAILY POWER LEVEL j

(MWe Net) 1 0

17 0

0 2

0 ig 3

0 0

39 4

0 0

20 5

0 0

7i 6

0 o

77 2

7 0

23

_0_

0 24 i

0 9

25 0

0 10 26 0

II 2-0 I2 0

28 0

0 13 29-0 I4 30 0

I5 0

0 31 16 0

Y a

+

50-289 DOCKET NO.

UNIT SilU1 DOWNS AND POWER REDUCTIONS UNIT N A%f E

'I f f l-1 DATE July 15, 1983 C04IPLETED ilY C. W.

Scyth REPORT MON HI June, 1983 T7T7T MB;B53r TELEPilONE

.[ g 3

5h Licensee

,E-t, o ".

Cause & Correc:ive No.

Date i

5?

4 1~5 Event p7 a.g Actiim to

~ jj c Repoit 2r rE U Present Recurrence

$~

5 H

f u

e O

D 1

N/A ZZ ZZZZZZ Regulatory Restraint Order 83/06/01 y

744 1

l l

l l

l l

l l

2 3

4 i

! - I orteil Itcason :

Metluxl:

Inhibit G - Instructions l

S Scheiluted A l:tpipment railure(INplain) 1 -M uinal for Preparation of Data ll41aintenance or 'Icst 24f anual Scram-I ntry Sheets Ior I.icemcc C Refueling 3-Automatic Scram.

ISent Repini (LI.R) file INURI G-D Regulatin) Itcstriction l-Ot her ilsplain) 01611 E-Operator Training & license ITamination F-Ad minist ra t i.c 5

G Operaljonal 1:rror (ITplaist)

IThibit 1 - Same Source 11-01her (INplain)

OPERATIONS

SUMMARY

During the month of June the unit was in cold shutdown by order of the NRC.

Core cooling was provided by the Decay Heat Removal System.

On June 25, a final closeout of OTSG "A" was performed.

On June 26, the RCS was filled from the "B" bleed tank and the secondary side of both OTSGs were pressurized to about 140 psig to check for tube leaks.

On June 27, the "A" OTSG (primary) was pressurized to 50 psig and reactor coolant pumps were hand rotated.

On June 28, the "B" OTSG was closed out and placed in wet layup.

On June 29, the "A" OTSG was placed in wet layup.

On June 30, the RCS was filled and vented and pressurized to 80 psig.

To date, no OTSG tube leakage has been identified (RCS at 300 psig on 7/8/83).

~

Additionally, several Technical Specification Surveillances were performed on primary systems in support of plant startup. All surveillances were performed satisfactorily.

MAJOR SAFETY RELATED MAINTENANCE During the month of June, major restart maintenance activities were completed and the following major maintenance items were performed:

1.

The Once Through Steam Generator (OTSG) repair program was co=pleted in June with re=aining leaking tubes stabilized and plugg'ed, satisfactory drip and bubble tests, removal of hot leg plugs, removal of cold leg covers, satisfactory closeout inspections, and the reinstallation of handhole/manway covers.

Preparations for the Hydrogen Peroxide Flush

. of the RCS were in progress.

e 2.

The snubber testing program continued during the month and work will con-tinue into the month of July.

3.

Decay Heat Removal System work items completed consisted of DH-V-64A/

DH-V-69 overhaul and repairs with satisfactory leak rate testing, DH-P-1A motor oil change, satisfactory breaker testing of DC-P-1A, and the pack-ing adjustnent of DH-V-4A.

A magnetic brake assembly was installed on DH-V-4A.

A stroke test was performed with satisfactory results.

4.

Hydrogen monitoring valves (EM-V-3A/B; 4A/B) were replaced under task LM-26B.

Local leak rate testing was satisfactorily performed on these valves.

5.

Air handling purge valve work completed during June included the stop adjustment and snoop testing of AH-V-1A and satisfactory leak rate test-ing of AH-V-1A/B.

6.

Vaste Gas Syste= repair activities completed during June included satis-factory testing / inspections on relief valves WDG-V-36 and WDG-Y-37, satisfactory inspections on WDG-T-1A pressure switches and transmitters, and the overhaul of waste gas compressor WDG-P-13.

i

i EEF"JELIEG INFORMATIC" ?I;UIST 1.

Home of Facility:

Three Mile Island Huclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

Unknown 3

Scheduled date for restart following refueling:

Unknown L.

Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment?

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

If an:ver is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cc=rittee to determine whether tny unreviewed safety questions are associcted with the core reload (Bef. 10 CFR Section 50.59)?

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

Amendnent No. 50, Cycle 5 relo&d, was approved on 3-16-79 5

Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A 6.

Important licensing censiderations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysic methods, significant changes in fuel dasign, new operating procedures:

N/A 7

The number of fuel a:semblies (a) in the cere, and (c) in the speat fuel storage pool:

(a) 177 (b) 208 6.

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:

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

OPERATING DATA REPDF.T DOCKET NO.

SG-2E9 DATE July 15, 1983 COMPLETED BY C..W.

Smyth TELEPHONE

' /1/ > v46-6551 OPERATING STATUS Three l'.ile Island Nucles.: Station, l'ni: :

1. Unit Name:

June, 1983

2. Reporting Period:

2535

3. Licensed Thermal Power (Mht):

671

4. Nameplate Rating (Gross MWe):

619

5. Design Electrical Rating (Net MWe):

0

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

//

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.lf Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr.t o.Da t e Cumulatis e 720.

4343.

77376.

11. Hours in Reporting Period

~

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.s 0.0 0.0 839.5

13. Reactor Reserve Shutd'owTi Hours 0.0 0.0 31160.9

14. Hours Generator On.Line 00 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0

76532071,

16. Gross Thenna! Energy Generated (MWH) u.

v.

2 x e..,33g.

17. Gross Electrical Energy Generated (MWH) v.

v.

Jae.u m,

16. Net Electrical Energy Generated (MWH) 0.0 0.0 40.3

19. Unit Service Factor U*U v.U 40.3

20. Unit Availability Factor

~

0.0 C.0 39.3

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 37.6

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 55.5

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 Feriod Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCI AL OPERATION (oi7' o

AVER AGE D A!LY L' NIT FOWER LEVEL DOCKET NO.

50-259

-I LWIT July 15, 1983 DATE COMPLETED BY C. W. Smvth TELEPHONE (717) 948-8551 U""*'

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OPERATIONS

SUMMARY

During the month of June the unit was in cold shutdewn by order of the NRC.

Core cooling was provided by the Decay Heat Removal System.

On June 25, a final closeout of OTSG "A" was performed.

On June 26, the RCS was filled from the "B" bleed tank and the secondary side of both OTSGs were pressurized to about 140 psig to check for tube leaks.

On June 27, the "A" OTSG (pri=ary) was pressurized to 50 psig and reactor coolant pumps were hand rotated.

On June 28, the "B" OTSG was closed out and placed in wet layup.

On June 29, the "A" OTSG was placed in wet layup.

On June 30, the RCS was filled and vented and pressurized to 80 psig.

To date, no OTSG tube leakage has been identified (RCS at 300 psig on 7/8/83).

Additionally, several Technical Specification Surveillances were performed on primary systems in support of plant startup.

All surveillances were performed satisfactorily.

MAJOR SAFETT RELATED MAINTENANCE I

During the month of June, major restart maintenance activities were completed and the following major maintenance items were performed:

1.

The Once Through Steam Generator (OTSG) repair program was completed in June with re=aining leaking tubes stabilized and plugged, satisfactory drip and bubble tests, removal of hot leg plugs, removal of cold leg covers, satisfactory closeout inspections, and the reinstallation of handhole/canway covers.

Preparations for the Hydrogen Peror.ide Flush

. of the RCS were in progress.

2.

The snubber testing program continued during the month and work will con-tinue into the month of July.

3.

Decay Heat Removal Syste= work items completed consisted of DH-Y-64A/

DH-V-69 overhaul and repairs with satisfactory leak rate testing, DH-P-1A motor oil change, satisfactory breaker testing of DC-P-1A, and the pack-ing adjustment of DH-V-4A.

A magnetic brake assembly was installed on DH-V-4A.

A stroke test was performed with satisfactory results.

4.

Hydrogen monitoring valves (EM-V-3A/B; 4A/B) were replaced under task LM-26B.

Local leak rate testing was satisfactorily performed on these valves.

5.

Air handling purge valve work ce=pleted during June included the stop adjustment and snoop testing of AH-V-1A and satisfactory leak rate test-ing of AH-V-1A/B.

6.

Waste Gas System repair activities completed during June included satis-factory testing / inspections on relief valves WDG-Y-36 and WDG-V-37, satisfactory inspections on WDG-T-1A pressure switches and transmitters, and the overhaul of waste gas compressor WDG-P-lE.

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Scheduled date for next refueling shutscv.:

Unkncvn 9

3 Scheduled date for restart fellowin refuelinr:

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specification Change or cther license a.end ent?

If answer is yes, in genera.1, what vill these be?

If answer is no, has the reload fuel design e.nd Ccre Ccnfiguration teen reviewed by ycur Plant Safety Revier Oc

' :ee to determine whether an"J unreviewed safetv questions are ass Cisted vith the Ccre relcad (Eef. 10 CFE Section 50.59)?

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GPU Nuclear Corporation Nuclear

,o m s r 8o e

Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84-2386 Writer's Direct Dial Nurnber:

July 15, 1983 5211-83-202 Office of Management Information and Program Control Attn:

W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Montitly Operating Report for June Enclosed please find two (2) copies of the June Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, e

11 D. Ilukill Director, TMI-l llDil:vj f Enclosures ec:

V. Stello Dr. T. E. Murley

(

ZS 2.9 l

/

GPU Nucioar Corporation is a subsidiary of the General Public Utilities Corporation l

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