ML20092L768

Monthly Operating Rept for May 1984

ML20092L768
Person / Time
Site:	Crane
Issue date:	05/31/1984
From:	Hukill H, Casey Smith GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
5211-84-2145, NUDOCS 8407020005
Download: ML20092L768 (7)

Text

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OPERATING DATA' REPORT DOCKET NO.

50-289 DATE June 15,1984 COMPLETED BY c, g,rh TELEPHONE (717uap_gs;1 OPERATING STATUS NOTES 1.-UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

MAY

,1984.

g 3.. LICENSED THERMAL POWER (MWT):

2535.

4.xNAMEPLATE-RATING (GROSS MWE):

871.

15. DESIGN ELECTRICAL RATING (NET MWE):.

819.

6.: MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

824.

7. MAXIMUM l DEPENDABLE CAPACITY - ( NET L'WE ) : '

776.

t k

V

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

1 9'.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE) 110. REASONS FOR' RESTRICTIONS, IF ANY:

l

=

THIS MONTH YR-TO-DATE CUMMULATIVL fil.-HOURS IN REPORTING PERIOD 744.

3647.

85440

-12. NUMBER'OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.0 13.fREACTOR 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 0.0

-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 36.5 20 UNIT AVAILABILITY FACTOR 0.0 0.0 36.5

21. - UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 35.6 22.SUNIT CAPACITY-FACTOR (USING DER NET) 0.0 0.0 34.1

23. UNIT FORCED OUTAGE RATE 100.0 100.0 60.1

[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 STARTi1P:

G D

DO O

O R

40 t

l

. o-.

l AVERAGE DAILY UNIT POWER LEVEL

~

,l-DOCKET NO.

50-289 UNIT TMI-1 4

DATE June 15, 1984 COMPLETED BY C. Smyth

.8 TELEPHONE (717)948-8551 p

i

= MONTH:

-MAY i.

I

-- DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL l

l (MWE-NET)

(MWE-NET) l 1-O.

17 0.

- 2' O.

18 0.

j

- 3 0.

19 0.

l 4

0.

20-O.

l

- 5 O.

21 0.

6 0

22 0

j

-7 0

23 0.

8 0.

24 0.

q~~

9 0.

25 0.

10 0.

- 26 0.

. 11 0

27 0.

i 12 0.

- 28 0

, O.

29 0.-

~

14-O.

30 0.

15 0

31 0

. 16~

~

0..

9 9

4*

4 9

4

+

e

3.

=,

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f 50-289-UNIT SilVTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME TM1-1 DATE M ma 14-lona COMPLETED BY c_ w_ %f-h

' REPORT MONTH Mg TELEPHONE r71 n nin-nqqi 4

e.

e n

3_e g

.2 _e s

g.E ;i Licensec ge,,

5;wl, Cause & Corrective No.

Date g

3g g

,g g 5 Event

w E.1

- Action to 33 5

jigg ReporI a r$0 0

Prevent Recurrence d

9 Regulatory Restraint Order i

i 1

84/01/01 F

744 D

1 N/A ZZ ZZZZZZ I

I 2

3 4

F: Forced Reason:

Method:

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

I-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 Operasjonal Error (Explain)

Exhibii 1. Same Source Il-Other (Explain)

. - -.~,.-.

.. = -

g, ;

i

.2:-

June 13, 1984 3200-84-211

~ OPERATIONS

SUMMARY

l LThe unit was shutdown the entire month by order of the NRC.

Core cooling

. as provided by the' Decay', Heat Removal System _except as described below.

i w

The following evolutions were. performed during the month to support Hot Functional Testing:

+

L5/7/84

' Started Circ Water System.

9 /9/84'- ~ Filled Condensate System.

5 5/14/84 - Partially drained both OTSGs.

~

~ 5/16/84 :- Established seal ~ injection to-RCPs.

Established RCS cleanup.

Commenced pressurizing RCS to 312 psig.

Started up Condens.te System.

Established vacuun in condensors.

5/21/84 - Set. containment:-integrity.

ur

~

'5/22/84 - Commenced-RCS heatup.

'5/23/84 - RCS at 525 F~, 2155 psig.

TheIfollowing testing was performed as part of Hot Functional Testing:

i' 8thLstage heaters operational hydro.

RCS-leak rate measurement.(new procedure and new computer program).

.-Hanger. expansion 1 tests for head vents and high point vents.

.. HPI cross-connect flow check..

=:

A7

. PORV ratesta(refurbished valve and modified. spring assembly).

.. Reactor coolant pump vibration analyses and-setting.

. Operational-hydro for:

..:.RCP Pump 1B, p-

^

All.0TSG primary.manways,;

.. - - Decay heat; drop line. tap,

p

.. ' Head vent, DHV-1,

... Main. steam relief valves setting.

No-major'~ problems were identified during this; testing.- On May 26,.1984 RCS cooldown was commenced and the plant remained in cold shutdown on Decay

- 1 Heat Removal for the remainder of the month.

' A Reactor Building' Integrated Leak' Rate Test was ~ performed on 5/8/84.

LThe test met the acceptance criteria with very_few problems encountered.

t

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4:~

MAJOR SAFETY RELATED MAINTENANCE

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~

During the month the following major maintenance items were completed.

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^

- m y

Pi'

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t-

_3 June 1:,.1984 2200-E;-223

. i Reactor Coolant Puro Balancing

~

. R'C-P1A/B/C & D were satisf actorily balanced following repair work on RC-PIB, and realignment of R C-P-1)( C & D.

Local Leak ' Rate-Testing Leak Rate. Valves LR-V2 and 3, the Reactor. Building Fire Service and the OTSG Drain Penetrations-were tested satisfactorily.

Intermediate

~ Cooling Valve IC-V3 failed its leak test and was tested satisfactorily following repairs to the valve seat and gate.

(Co=nonent'Retorquing During HFT, bolts were retorqued on the OTSG manway and handhcle covers as were bonnets on pressure segl valves CF-VIA/B, CF-V4A/B, DH-V1, 2 and 22A..

Main Steam Safety Valve Testing All main steam safety valves were tested satisfactorily during EFT.

L a

Waste Gas Pump Overhaul WG-P1A was overhauled following failure to pump to rated capacity.

The failure was attributed to moisture related corrosion and errosion l o f ' internals". Following' repairs the pump was tested with satisfactory results.

ESAS Relav Reolacement All LSAS relays were replaced because of the unreliability of the

-previously installed Clark relays. This work was performed to resolve problems identified in LER 83-24

~

Atmoseheric Dumo Valve's Replaced MS-V4A/B were replaced with a different model (Fisher Valves) because of a history of leaking by.

Prior to installation the g

internals were modified. _ Work also included valve operator inspection, weld NDT,' flush and hydro testing.

3 9

77 e

-.s REFUELING INFOR!ULTION REQUEST

,O_

T 1.-'Name of:Fae311ty:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

Unknown 3

Scheduled date for restart following refueling:

i Unknown

k. ' Will refueling or resumption of operation thereafter require a technical specifi',ation change or other license amendment?

If answer is yes, in gener6h, uhat vill these be?

~

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co=mittee to determine whether any_ unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50 59)?

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

Amendment No. 50, Cycle 5 reload, was approved on 3-16-79 s.+

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

'information:

N/A 6... Lmportant 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) it. th'e core, and (b) in the spent fuel storage pool:

(, a) 177 (b) 208

'8.

TDae 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 assemblics).

e

GPU Nuclear Corporation 198r Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Nurnber:

June 15, 1984 5211-84-2145 Office of Management Information and P.

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 May Monthly Operating Report Enclosed please find two (2) copies of the May Operating Report for Three Mile Island Nuclear Station Unit.l.

Since: ely, H. D. Hukill, Director, TMI-i

. HDHamle Attachments cc:

V. Stello Dr. E. T. Murley 8

g31G'A 4

Cedifi"a $7 y6 I

\\

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

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