ML20084P252

Monthly Operating Rept for Apr 1984

ML20084P252
Person / Time
Site:	Crane
Issue date:	04/30/1984
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
5211-84-2116, NUDOCS 8405180065
Download: ML20084P252 (7)

Text

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1 3

OPERATING DATA REPORT E C E

DOCKET NO.

50-289

[

D-DATE May 15, 1982 t

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COMPLETED BY c3tcNvnt t-TELEPHONE 717-948-855:

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E OPERATING STATUS

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NOTES 5

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 6:

2. REPORTING PERIOD:

APRIL

,1984.

I

3. LICENSED THERMAL PONER (MWT):

2535..

2

4. NAMEPLATE RATING (GROSS MWE):

871.

l_

(i

5. DESIGN ELECTRICAL RATING (NET MWE):

819.

b 6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

824.

[ '~

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

776.

5

~_

C-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:

@L E

E=

I THIS MONTH YR-TO-DATE CUMMULATI

11. HOURS IN REPORTING PERIOD 719.

2903.

8469 t-12 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 83%

14 HOURS GENERATOR ON-LINE 0.0 0.0 31186 I f,Z

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0

P

16. GROSS THERMAL ENERGY GENERATED (MWH) 0 O.

7653107 E

17 GROSS ELECTRICAL ENERGY CENERATED (MWH) 0 O.

2548433 b Er

18. NET ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

2384005

[

19. UNIT SERVICE FACTOR 0.0 0.0 36 F

20 UNIT AVAILABILITY FACTOR 0.0 0.0 36

% 69

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 36 a

22 UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 34

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23. UNIT FORCED OUTAGE RATE 100.0 100.0 59

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

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

- 9F 8405180065 840430 PDR ADOCK 05000289

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R PDR 1

3-AVERAGE DAILY UNIT POWER LEVEL c?.

DOCKET NO.

50-289

..?,

UNIT TtiI-1 DATE May 15, 1984 t

COMPLETED BY C.W.sMrm

,3-TELEPHONE 11/-946-0331 i

_ MONTH:

APRIL 9

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

(MWE-NET) 1-O.

17 0

2-2 0

18 0

3 0

19 0

4 0.

20 0

i 1

5 O.

21 0

6 0

22 0.

7 0.

23 0

9 8-0 24 0

9 0

25 0

l 10

~0.

26 0

9 11 0.

27 0

12 0

28 0

13 0

29 0

9:

14 0.

30 0

15 0

31 N/A

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16 0

J I

g i

f t

a.

i

n y

O l

a o

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1

' May 10, 1984 3200-84-164 OPERATIONS

SUMMARY

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

Core cooling was provided by the Decay Heat Removal System.

.Until April 15 the Primary System was pertially drained to 10-15 inches above the cold leg centerline, depressurized with temperature being maintained between 120 -

130 F.

On April 15 the RCS was filled and as of ghe end of the month the RCS was being maintained at about 300 PSI and 130 - 150 F.

MAJOR SAFETY RELATED MAINTENANCE During the month the following major maintenance items were completed.

RC-PlB Repairs to Reactor Coolant pump RC-P-1B continued with the reassembly of the pua internals and reinstallation into the casing.

The motor stand was reinstalled and torqued.

The motor was installed on the motor stand and aligned with the pump.

Interferences were rein' stalled and electrical leads reconnected. All ser injection, seal leak off, and purge piping was reinstalled on the pump and preparg tions for hot and cold balancing were in process.

Balancing and testing of RC-1B will continue in May.

RC-P-1A, C, and D Reactor Coolant pump RC-P-1A, RC-P-lC and RC-P-lD work completed during April included Ultrasonic Testing of pump shafts and realignment of the pumps and motg The UT analysis showed no indication of shaft failure.

Hot and cold balancing @

the pumps will be completed in May.

LLRT Local Leak Rate Testing continuad in April with the satisfactory testing of AH-V-1A/lB/1C/lD, MU-V-2A/B, MU-V-3, and penetrations 104, 210, and 211.

This testing will continue in May.

ILRT The scheduled Integrated Leak Rate Testing of the Reactor Building was completed in April with preparation of the Reactor Building and setup / installation of air compressors. The Reactor Building was pressurized, stabilized, and leakage rec @

ed then depressurized. The ILRT was satisfactorily completed.

--r-m

.1-s.

' May 10, 1984 3200-84-164 BS-P-1B Building Spray pmp BS-P-1B was overhauled as a result of a failed weekly surveillance (pmp would not rotate by hand). The thrust bearing was found to be defective. 'Ihe pmp was disassenbled, inspected, the bearing was replaced and the pmp was reassembled. Testing of the pm p was satisfactory.

OTSGs Once 'Ihrough Steam Generator RC-H-1A/B marway and handhole backing plate flatness inspections were ampleted in April. The lorer marway backing plate-on IO-P-1B required machining and all other plates were found satis-factory. 'Ihe OTSG manway and handhole covers were reinstalled.

10-RV2 (PORV)

'Ihe pressurizer electromatic relief valve (RC-RV2) was replaced with a spare that had been modified with a new heavy-duty spring designed to prevent leakage at law pressure. 'Ihe new valve was electrically tested following installation.

No significant signs of damage or corrosion were identified in the old valve which has been shipped to Wyle Lab for testing and modification.

1 i

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e 50-289 DOCKET NO.

UNIT SilUIDOWNS AND POWER REDUC 110NS UNIT NAME El-1 DATE Avil 15, 1994 COMPLETED BY J. W. Smvth REPORT MONm Anril. 19R4 TELEPHONE him o A o_ o nq1_

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ci 5 en e t

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E

,.s 'A Licensee E r, E".,

Cause & Corrective 8.

Action to No.

Date g

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3g$

Event t; T

[3 c$ E 5

j di g Report #

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Prevent Recurrence c5 1

84/04/01 F

744 D

1 N/A ZZ ZZZZZZ 7

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l 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain)

1. Manual for Preparation of Data B. Maintenance of 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-Administrative 5

G-Operational Error (Explain)

Exhibit I Same Source II-Other (Explain)

9, i?

. REFUELING 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 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 L.

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 T.

The number of fuel assemblies (a) in the core, and (b) in the spent fuel stora6e 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).

GPU Nuclear Corporation Nuclear

,ome:r8o s

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

May 14,1984 5211-84-2116 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. 2D555

Dear Mr. Mcdonald:

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

Operating License No. DPR-50 Docket No. 50-289 April Monthly Operating Report Enclosed please find two (2) copies of the April Operating Report for Three Mile Island Nuclear Station lhit.

Sincerely, H

. Hukil Director, TMI-l HDH:mle Attachments cc:

V. Stello Dr. E. T. Murley

+$ i \\

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation