ML20106E720

Monthly Operating Rept for Sept 1984

ML20106E720
Person / Time
Site:	Three Mile Island
Issue date:	09/30/1984
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
5211-84-2261, NUDOCS 8410300086
Download: ML20106E720 (11)

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DATE October 15, 1984 COMPLETED BY C. W. Smy t.h 1

TELEPHONE (717) 948-8551

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't 8410300006 840930 PDR ADOCK 05000289 R

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OPERATING DATA REPORT V,

^l

• t' DOCKET NO.

50-289 DATE October 15.198 dj.

'"i' COMPLETED BY C. W. Smyth x

TELEPHONE (717) 948-8151

q. A (3'

y\\i

' OPERATING STATUS NOTES 1.JUNIT NAME:

THREE MILE ISLAND UNIT 1

.~2.. REPORTING PERIOD:

SEPT

,1984.

3. LICENSED THERMAL POWER (MWT) :

2535.

l

\\.6 NAMEPLATE RATING (GROSS MWE) :

871.

4 '

5. / DESIGN ELECTRICAL RATING (NET MWE) :

819.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

776.

j k$'

4

• 8.

IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)

10. REASONS FOR RESTRICTIONS, IF AN?!:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD 720.

6575.

88368.

12.iNUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8 i 13.' REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5 I.14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9 j

,15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.C

'16. GROSS THERMAL ENERGY GENERATED (,MWH)

O.

O.

76531071.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.

O.

25484330.

18. NET ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

23840053.

19. UNIT SERVICE FACTOR 0.0 0.0 35.3

20. UNIT AVAILABILITY FACTOR 0.0 0.0 35.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 10. 0 34.5

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 32.9

23. UNIT FORCED OUTAGE RATE 100.0 100.0 61.6 s

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH s, _.

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25. IF SHUT DOWN AT END OF REPORT PERTOD, ESTIMATED DATE OF STARTUP:

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50-289 DOCKET NO.

UNIT SIIUTDOWNS AND POWER REDUCTIONS TM1-1 UNITNAME DATE October 15, 1984 COMPLETED BY. C. W. Smyth REPORTMONTH eptember,1984 S

TELEPHONE ~ ( 7171 948-85 s1 E

E

,E E 3

j.$ 5 Licensee Eg l"'.

Cause & Corrective No.

Date R

Eg s

j ~$

Event p

gO8 Action to H

f5 5

3 ;f3 g Report a mU Prevent Recurrence o

e U

c5 I

84/09/01 F

744 D

1 N/A ZZ ZZzzzz

'k s

i I

2 3

4 F: Forced Reason:

Method:

Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administ rative S

G-Operational Error (Explain)

Exhibit I - Same Source Il-Other (Explain) i

N OPERATING

SUMMARY

The Plant remained in cold shutdown the entire month by order of the NRC.

Core cooling was provided by the Decay Heat Removal System. The RCS was partially drained to permit OTSG inspection and repair work as described below.

MAJOR SAFETY RELATED MAINTENANCE During the month of September, the following major maintenance items were completed:

OTSGs RC-H-1A/B - Repair work on the OTSGs in September consisted of Westinghouse rolled tube plug procedure development, Mock-up Training, and equipment set up. Field work commenced on the "B" 0TSG upper tubesheet, with wire brushing, rerolling, and pull-testing Westinghouse rolled tube plugs that had indicated movement during the August pull-testing evolution.

This was followed by wire brushing and rerolling the remainder of the Westinghouse rolled-tube plugs in the "B" OTSG upper tubesheet. The equipment was then moved to the "B" 0TSG lower tubesheet where work will continue in October.

NUCLEAR SERVICE CLOSED C0OLING COOLERS NS-C-lC/D - Work commenced on NS-C-1C/D with removing the end covers, inspection, tube cleaning, repairing surfaces with coal tar epoxy, and installation of magnesium anodes. The tubes were leak-checked and cooler close-up is in a hold status pending opening clogged drain lines.

DECAY HEAT REMOVAL CLOSED COOLING PUMP DC-P-lB - DC-P-1B was disassembled in September for new mechanical seal installation. The pump internalswere inspected, the shaft and impeller balanced, and the pump was reassembled with the mechanical SEAL. The pump / motor was aligned and coupled and inservice testing was performed per IST Procedure 1300-3C; the results were satisfactory. The job will continue in October with the reinstallation of piping supports.

DECAY HEAT REMOVAL CLOSED COOLING COOLER DC-C-2B - During September, DC-C-2B was opened for inspection, cleaning, and preservation.

The end covers were removed, tubes cleaned and inspected, water boxes repaired and preserved with PC-7 and coal tar epoxy. Magnesium anodes were installed, and the end covers reinstalled.

REFUELING IliFORMATION 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 h.

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 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:

1988 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

f

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' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-l 1

DATE October 15, 1984 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 MONTH:

SEPT DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 0.

17 0.

2 0.

18 0.

3 0.

19 0.

4 0.

20 0.

5 0.

21 0.

6 0.

22 0.

7 0.

23 0.

8 0.

24 0.

9 0.

25 O.

10 0.

26 0.

11 0.

27 0.

12 0.

28 0.

13 0.

29 0.

14 0.

30 0.

15 0.

31 N/A 16 0.

t f

't

OPERATING DATA REPORT DOCKET NO.

50-289 DATE October 15,19E ;

COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8151 l OPERATING STATUS NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

SEPT

,1984.

3. LICENSED. THERMAL POWER (MWT) :

2535.

4. NAMEPLATE RATING (GROSS MWE):

871.

5. DESIGN ELECTRICAL ' RATING (NET MWE) :

819.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

776.

8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)

10. REASONS FOR RESTRICTIONS. IF ANY:

1 THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD 720.

6575.

88368.

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5

14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.C

16. GROSS THERMAL ENERGY GENERATED (MWH)

O.

O.

76531071.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

25484330.

18. NET ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

23840053.

19. UNIT SERVICE FACTOR 0.0 0.0 35.3

20. UNIT AVAILABILITY FACTOR 0.0 0.0 35.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 34.5

)

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 32.9

23. UNIT FORCED OUTAGE RATE 100.0 100.0 61.6

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MOITHS (TYPE, DATE, AND DURATION OF EACH

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

i

50-289 UNIT SilUTDOWNS AND POWER REDUC 110NS DOCKET NO.

UNIT NAME TML-1 DATE October 15, 1984 S

COMPLETED BY C. W. Smyth REPORT MONTH eptember,1984 TELEPHONE (717) 948-8551 "i

c

-o.a :

a, es y

Lic nSe Cause & Corrective

~

g g ;e Event 2

3 Action to N"-

Da'C E

So N

.c 5E E

jisy Report a N0 0

Prevent Recurrence 5

1 84/09/01 F

744 D

1 N/A ZZ ZZZZZZ I

2 3

4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File INUREG-D Regulatory Restriction 4-O her(Explain) 0161)

E-Operator Training & Ijcense Examination F-Administrative 5

G-Operatp' >nal Error (Explain)

Exhibit I - Same Source Il-Other (Explain)

OPERATING

SUMMARY

The Plant remained in cold shutdown the entire month by order of the NRC.

Core cooling was provided by the Decay Heat Removal System.

The RCS was partially drained to permit OTSG inspection and repair work as described below.

MAJOR SAFETY RELATED MAINTENANCE During the month of September, the following major maintenance items were completed:

0TSGs RC-H-1A/B - Repair work on the OTSGs in September consisted of Westinghouse rolled tube plug procedure development, Mock-up Training, and equipment set up. Field work commenced on the "B" OTSG upper tubesheet, with wire brushing, rerolling, and pull-testing Westinghouse rolled tube plugs that had indicated movement during the August pull-testing evolution. This was followed by wire brushing and rerolling the remainder of the Westinghouse rolled-tube plugs in the "B" 0TSG upper tubesheet. The equipment was then moved to the "B" OTSG lower tubesheet where work will continue in October.

NUCLEAR SERVICE CLOSED COOLING COOLERS NS-C-lC/D - Work commenced on NS-C-lC with removing the end covers, inspection, tube cleaning, repairing surfaces with coal tar epoxy, and installation of magnesium anodes. The tubes were leak-checked and cooler close-up is in a hold status pending opening clogged drain lines.

DECAY HEAT REMOVAL CLOSED COOLING PUMP DC-P-1B - DC-P-1B was disassembled in September for new mechanical seal installation. The pump internals were inspected, the shaft and impeller balanced, and the pump was reassembled with the mechanical SEAL. The pump / motor was aligned and coupled and inservice testing was performed per IST Procedure 1300-3C; the results were satisfactory. The job will continue in October with the reinstallation of piping supports.

DECAY HEAT REMOVAL CLOSED COOLING COOLER DC-C-2B - During September, DC-C-2B was opened for inspection, cleaning, and preservation. The end covers were removed, tubes cleaned and inspected, water boxes repaired and preserved with PC-7 and coal tar epoxy. Magnesium anodes were installed, and the end covers reinstalled.

t, R_ N ING INFORMATION 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 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 in 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 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 j

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:

1988 is the last refueling discharge which allows full core off-load capacity (177 fuel asse=blies).

(-

GPU Nuclear Corporation Nuclear

,ome er8o s

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

October 15, 1984 5211-84-2261 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 Mr. Mcdonald:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report - September 1984 Enclosed please find two (2) copics of the September 1984 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.

Sincerely,

. D. Hukill Director, TMI-1 HDH:JGB:vjf Attachments cc:

V. Stello Dr. T. E. Murley r&2Y GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

-