ML19312D386

Monthly Operating Rept for Feb 1980

ML19312D386
Person / Time
Site:	Crane
Issue date:	03/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19312D384	List: ML19312D383 ML19312D386
References
NUDOCS 8003240314
Download: ML19312D386 (6)

Text

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OPERATING

SUMMARY

" The unit;was shutdown for the entire month by order of the NRC.

MAJOR SAFETY RELATED MAINTENANCE

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'. Decay ~ Heat-Valves DH-V20A and DH-V21 (Decay Heat-System to Borated Water

' Storage Tank Recirc.' Isolation Valves):had.been found to be leaking through and were ' replaced. The existing valves were. disassembled, a blue check was performed on. the,discito seat surface and the decision made to replace the

. valves. The.new. valves were. installed, blue' checked satisfactorily, reas-

.s'embled and a ' flush and operational: inservice > test was performed with satis-

~ factory results.

Three repairs were performed on previously reported intergranular stress Lcorrosion cracking indications in. thel Decay Heat. System to Building Spray Systemicross connect piping. (indications 0-178, 180 & 182). Repair consisted

'of.. replacing.the affected section of piping and included X-ray examinations

-of the welds and flush and ' operational in-service test. Tests were performed with satisfactory results.

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OPERATI!iG DATA REPORT.

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50-289 4

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Dats __ 3/15_/80 D. G. Mitens11 Comp 1sttd By OPERATING STATI,

Telephone (215) 021-6970 1.

Unit Name: Three-Mile Island Nuclear Stalion

2.. Reporting Period:

February 1980 3. Licensed Thermal. Power (!Nt):

2535

k. - Nameplate Rating (Gress We):

871 5

Design Electrical Rating (Net !Ne):

819

6. -Max. Dependable Capacity (Gross !Ne): 8ho

7. ' Max. Dependable Capacity (Net IWe):

776

8. If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:-

9.; sier Level to which Restricted. If Any (Net !We):

- 10.

Reasons for Restrictions If Any:

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Month Yr. to date Cumulative 696.

1140.

48169.. r-

.11.

Hours in Reporting Period 12.

No. of Hours' Reactor was Critical 0.0 0.0 31731.8 0.0 0.0 839.5 13.'

Reactor Reserve Shutdovn Hours J14.

Hours Generator On-Line 0.0 0.0 31180 9 15 Unit Reserve Shutdown Hours 0.0 0.0 o,0 16.

Gross Thermal Energy Generated (MWH)

O.

O.

76531071.

17 Gross Elect. Energy Generated-(MWH)

O.

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2548h330.

18. Net Electrical Energy Generated (!GH) 0.

O.

23840053.

19 Unit Service Factor 0.0 0.0 64.7

20. ' Unit Availability Factor 0.0

0. 0_

64.7

. 21.

Unit Capacity Factor (Using MDC Net) 0.0 0.0 62.8

' 22.. Unit Capacity Factor (Using DER Net) n.o 0.0 60.4.

23. ~ Unit Forced Outage Rate _

100.0 100.0 23.5~

2h. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

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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 IHITIAL ELECTRICITY Co mERCIAL OPERATION e

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M ', b, AVERAGE DAILY UITIT POWER LEVEL 1-Docket No.

hD-289

- Unit

-1 Date -

3/15/80 Completed By D. G. Mitchell i.

~ Telephone (015) 9211879

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February 1980-DAY AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL

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, I ' 1[ NIT SHUTDOWNS AND POWER $ REDUCTIONS

. Dock-A No.

50-289

~ REPORT MohTil February 1980 3/15/80 Date T.

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Completed.By D. O_ Mie.,haii'

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h Telephone (215) 921-6579

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1 Regulatory Restraint Order

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" Exhibit G - Instructions

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1-3.fethod I: Forced 2 ecson:

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1 f r Preparation of Data c

S: Scheduled A-Equipment Failure (Explain]

14fanual t'.

B-Maintenance or Test Entry Sheets for Licensee

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Event Report (LER) File C-Refueling 3-Automatic Scram.

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i.4 D-Regulatory Restriction h-Other (Explain) f!

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E-Operator Training & Licensee Examination 4

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F-Administ.rative 3 Exhibit 1 -- Same Source I,T G-Operational Error (Explain)

H-Other (Explain)

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REFUELING INFOM4ATION REQUEST

- 1.. Name of Facility:-

4-

. Three Mile Island Nuclear Station, Unit-1

2.. Scheduled date for. next refueling shutdmu:

Unknown

' 3 Scheduled date for restart following refueling:

~ Unknown h.- Wil'1 refueMug 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 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 i-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 d

.'T. IThe' number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 1TT (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 or 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

1986 is.the'last refueling discharge which allows full core off-load

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l capacity (177(fuel assemblies).

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