ML20066F284

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Monthly Operating Rept for TMI-1 for Dec 1990
ML20066F284
Person / Time
Site: Crane Constellation icon.png
Issue date: 12/31/1990
From: Broughton T, Heysek W
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2001, NUDOCS 9101230187
Download: ML20066F284 (6)


Text

.x-GPU Nuclear Corporation

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Post Office Box 480 f',ute 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

January 14, 1991 C311-91-2001 U. S. Nuclear Regulatory Commission Attna Document Control Desk Washington, D.C.

20555 Gentlemen:

Subject:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report December 1990 Enclosed are two copies of the December, 1990 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, T.

G.

Dro ghton l

Vice President & Director, THI-l TGB/WGH cca Administrator, Region I THI Senior' Resident Inspector Attachments t

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9101230187 901231 PDR ADOCK 05000289

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l GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation

OPERATIONS

SUMMARY

DECEMBER 1990 The unit entered the month operating at 75% power producing 600 MWe.

A reduced power level was maintained to of feet repaire to the "10B" low pressure: feedwater heater as a result of tube leakage. On December 3,1990 the "B" low preedure and high pressure feedwater heater strings were returned to service following the repairs. Plant power was raised to 95%. The plant continued power operation at

=95% until December 23, 1990.

As a result of a Minimum Emergency Generation order, TMI-l was regus. red to reduce power to 89%.

Following a return to 94%

power THI-l was again rediced to 84% power for a period of four hours before being returned to 94% power. The unit closed the month operating at a 94% power level limited by high OTSG 1evels on the "B"

side.

MAJOR SAFETY RE1.ATED MAINTENANCE During December, the following major safety related maintenance hetivity was performed:

Control Buildino Chiller "B"

(AH-C-4D)

The Control Building Chiller "B"

(AH-C-48) was taken out of service to perform the annual inspection of the unit and normal monthly inspection items.

In addition, & Hot Gas Bypase Valve Kit was installed as a modification to the unit to eliminate short cycling of the chiller during low-load operatione.

The chiller was r0 turned to service after satisfactory operation at low-load (to verify proper operation of the modification) and normal conditions.

Control Rod Drive Breaker #11 Control Rod Drive Breaker #11 was replaced with a new breaker because of a noisy undervoltage device. Ef forts to determine the cause of the undervoltage device noise in the removed breaker wi'.1 continue into January 1991.

2

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' OPERATING DATA REPORT DOCKET NO.

50-289 DATE 01/15/91 COMPLETED' BY-W. G. Heysek TELEPHONE (717) 948-8191

,r OPERATING-STATUS I NOTES I

1.-UNIT NAME:

THREE' MILE ISLAND UNIT 1 1

-1

-2.-REPORTING PERIOD:

DECEMBER,1990. I I

3; LICENSED'THERNAL POWER (MWT):

2568. I l

4.. NAMEPLATE RATING'(GROSS MWE)~:

871. I i

5.: DESIGN ELECTRICAL-RATING (NET MWE)2 819 I

i=

6.xMAXIMUM, DEPENDABLE CAPACITY (GROSS MWE):

856.

I-l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

808. 1 I

i

-l 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:

'THIS~ MONTH YR-TO-DATE CUMMULATIVE

11. HOURS :IN REPORTING PERIOD -

744 8760.

143161.-

12.; NUMBER OF-HOURS REACTOR WAS CRITICAL-744.0-7165.6 69164.2 113.JREACTOR RESERVE SHUTDOWN' HOURS.

0.0 242.8

,2245.6

14. HOURS GENERATOR ON-LINE-744.0 7123.6~

G8119.7 E.15. UNIT' RESERVE SHUTDOWN' HOURS:

0.0 0.0

'O.O

+

n 16. GROSS ~ THERMAL: ENERGY GENERATED (MWH) 1755896.

16898878.

166470772.

L17; GROSS ELECTRICAL ENERGY GENERATED (MWH) 594700.

5654235.-

55960904.

E'.B.

NET ELECTRICAL = ENERGY: GENERATED-(MWH) 559582.

5302931.--

52489420.

P 19.-UNIT SERVICE FACTOR 100.0 81.3

~47.6 D20.xUNIT AVAILABILITY FACTOR'

-100.0 81.3 47.6 L21.! UNIT CAPACITY FACTOR (USINGLMDC NET)

-93.1 74.9 46.7

[23.;UNITFORCEDl OUTAGE' RATE 2t; UNIT CAPACITY FACTOR (USING DER. NET) 91.8 73.9 44.8-O.0 3.2 47.1

[24.?SHUTDOWNSfSCHEDULED OVER NEXT-6 MONTHS _(TYPE,'DATE,'AND' DURATION OF EACH ll h :25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

L L

l:

AVERAGE DAILY UNIT-POWER LEVEL i

DOCKET NO.

50-289 UNIT TMI DATE ~ 01,'15 / 91 --

COMPLETED BY W. G, Heysek TELEPHONE (717) 948-8191-MONTH:

DECEMPER l)

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

(MWE-NET) j)

1 555.

17 774.

-2 556.

18 771.

3 57.1.

19

.770..

.i 4.

770.

12 0 772.

i 5.

779.

21 772.

6 777.-

22 768.

7 778.

23 749.-

l 8

778.

24 770.

775.

25

-776 19

+

10 774.

26

'/ 75.

11

-778.

27 774.

12 777.

28 772.

13

-773.

29 770.

'14

778.

30 767.

i:

15.

-776.

31 769.

g 16=

772.

I i

e i

k 4

+-

4 i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No.

50-289 UNIT NAME TMI-l REPORT MONTH December 1990 DATE 01/15/91 COMPLETED BY W. G. Heysek TFTEPHONE (717) 948-8191 Method of Licensee System :m ponent cause & Corrective I

2 Wo-Date Type Duration Reason Shutting Event Code Code Action to (Hours)

Down Report #

Prevent Recurrence Reactor 90-12/01/90 F

72 B

4 NA SD HTEXCH High feedwater level in the 10B feedwater 05 heater initiated a power reduction to stabi-lize heater level, maintain condensate flow and powdex parameters within specifications.

The "B" side high/ low pressure feedwater strings were isolated to perform repairs. 18 tubes were identified as damaged and 13 of these tubes were found to be complete breaks.

12/23/90 S

2.08 H

4 NA Minumum Generation Dnergency declared by 90-06 Reading Dispa M er 12/23/90 S

4.08 H

4 NA Minumum Generation Emergency declared by 90-07 Reading Dispatcher 1

2 3

4 I Forced Reason Method Exhibit G - Instructions for S Scheduled A-Equipment Failure (Explain) 1-Manual preparation of Data Entry Sheets 8-Maintenance or Test 2-Manual Scrain for Licensee Event Report (LER)

C-Refueling 3-Automatic Scrarn File (rJREG-0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & Licensing Examination 5 Exhibit 1 same sou :e F-Adninistrative G-Operational Error (Explain) 6 Actuelty used exhibits F & II NURcG 0161 N-Other (Explain) 5

,t REFUELING INFORMATION REOUEST

11. Name of Facility:

Three Mile Island Nuclear Station, Unit 1 3

2 '. Scheduled date for next refueling shutdown:

October 4, 1991 (9R) 3.

Scheduled date for restart following current refueling NA

4. Will refueling or res; tion of operation thereafter require a technical specification change or other license amendment?

No.

If answer is yes, in general, what will these.be?

If answer is no, has the reload fuel design and core coafiguration been reviewed by your Plant Safety Review Committee te, determine whether any unreviewed safety questions are asscatated with the core reload (Ref. 10 CFR Section 50.59)?

No.

If no such review has taken place, when is it scheduled? 6/1/91.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: None planned.

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 -

OPU Nuclear intends to install four Westinghouse Lead Test Assemblies during the reload of the TNI-1 core for cycle 9 operation.

Westinghouse fuel technology will be utilized to the extent possible.

7.

The number of fuel desemblies (a) in the core, and (b) in the opent fuel storage pools (a) 177 (b) 441

8. The present licensed spent fuel pool storage capacity and the sir.e of any increase in-licersed storage capacity that-has been requested or is planned, in: number cf fuel assemblies:

The present 11consed capacity is 752.

Planning to increase licensed capacity through fuel pool raracking is in progress.

9. The projected dt4te of the last' refueling that can be discharged to the spent-fuel pool assuming the present licensed capacity:

1991 is the last refueling. discharge which allows full core off-load capacity (l"7 fuel assemblies).

6

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