ML20128H613

Monthly Operating Rept for Jan 1993 for Haddam Neck Plant.W/

ML20128H613
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/31/1993
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9302170101
Download: ML20128H613 (10)

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• CONNECTICUT YANKEE ATOMIC POWER COMPANY

[f HADDAM f1ECK PLAfiT j aca muu nonow noAo . EAST HAMMON CT OG4244U)

February 15,1993 Re: Technical Specification 6.9.1.8 Ik>cket No. 50 213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Dear Sir:

In accordance with reponing requirements of Technical Specification 6.9.1.8, .he Connecticut Yankee lladdam Neck Plant Monthly Operating Repott 93-02 covering operations for the period January 1,1993 to Janury 31,1993 is hereby forwarded.

Very truly yours, k/

John P. Stetz Vice President lladdam Neck Station JPS/va ec: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2) William Rayimnd Sr. Resident inspector Connecticut Yankee 170029

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ADOCK 05000213 PDR l}

Connecticut Yankee Atomic Power Company lladdam Neck Plant

-Iladdam, Connecticut l t

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Monthly Operating Report No. 93-02' '

- For The - Month of

l. January 1993

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CONNECTICUT YANKEE ATOMIC POWER COMPANY ,

HADDAM NECK PLANT 1 RR81

• BOX 127E

• EAST HAMPTON, CT 06424 9341 1

4 February 1,1993_

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The following is the Summary of Plant Operations for January 1992:  ?

The plant was operated at 100% power until January 17th at 0025 houn. A power reduction to 65% was performed to conduct a routine turbine stop valve stroke test. The test was successfully completed at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />. A power increase was initiated and the plant was returned to 100% power at 0650 houts, The plant was operated at 100% power for the remainder of the month of January.

l W83 REV,1487

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• CONNECTICUT YANKEE  :

1(P.ACIOR CCX)LANT DATA  !

. MONTil: January 1993 i i

REAC10R COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM

_ p1i G 25' C 6 $9 6.77 6.01 CONDI)C11VITY 4tmtm/cm) 10.67 12.05 15.97 Chlorides (ppm) <0 050 <0.0$0 <0.0$0 ,,

Diwilved Oxygen (ppb) <5 <5 <$ _

ikvon (ptwn) 208 338 384 1.ithium (ppm) 0.719 0.90R 1.125 Totat Ac t. (pri/ml) 0.260 0.174 0.419 l Ratio 0.67 0.72 0.97 l 1131 (pri/ml) 1.74 E-03 1.R9E.03 2.34 ti-03 Cru<l(mr/1) <1 <1 <1 ,

TRITillM (pri/mt.) 2.66 3.50 4.23 1Iyilroren (cc/Ky) 24.40 26.18 27.70 Aerated Liquid Waste Processed (Gallons): 1.48EdiO3 Waste I.lquid Processed through 11oron Recovery (Gallons): 5.20Ed104 Aventge Primary Leak Rate (Gallons per Minute): .368 Primary to Secondary leah Rate (Gallons per Minute): 5.92E413

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MAINTENANCE DEPARTMENT Report Afonth January 1993 MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide System Safe Taken to Prevent For Reactor Safety During Repair or Component Cause Result Operation Repetition i

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There were no rcportable ite ns for the Maintenance Department for January 1993 i.

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I&C DEPARTMENT

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Repon Month: January 1993 System MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition There were no re aortable iteris for the I&C Department for the mont: i of January 1993 i-

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~ UNIT SHUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee Da te: F-bruary 15. 1993

,- Report Month: _ January 1993 Completed By: K. W. Emmons

- TeIephone: (203) 267-3654

'I I No. Date Type Duration Reason Method of - LER. System Component

[ (Hours) ' Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence dowi Reactor #

4 There were no reportable shutdowns. ar power re luction in January 1993 i'

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IXZE REASON METHOD - SYSTFM & COMPONENT

. F. Forced . . A Equipment' Failure - 1 Manual - Exhibit F & H - Instructions for Preparation of 12 Manual Scram Data Entry Sheets

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- S : Scheduled B ' Maintenance or Test-1C Refueling 3. Automatic Scram . Licensee Event Report (LER)

- D Regulatory Restriction :4 Continued -

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File (NUREG-0161)

E Operator' Training > 5 Reduced ' Load 4

F Administrative - 9 Other l .. .

. G Operator Error H ' Other (Explain) l

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e AE C OFE R A1.lk0 $1 A TUS EEF-ORT N6dJun Neck

1. Occhet: 50+213

2. Reporting Feriod: 01/93 Out age + on-line b our s: 0.0 + 744.0 = 744.0

3. Utitity (cntect: M. P. tain (203) 267 3635

4. L icensed 1hernal Fower (Mst): 1825

5. Nameplate Rating (Gross MJe): 667 x 0.9 - 600.3

6. Desisn Electricot Stating (Net MWe): 5S2

7. Maxirun Depervdable Capacity (Cross Mwe): 5B6.9

8. Maainsn Dependable Capacity (Net Mse): 500.1

9. If 5cnges occur obove since test rep;rt, reasons ere: NONE

10. tower levet to which restricted, if eny (het Pue): N/A

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11. Reasons f or r est riction, if any: N/A MCNfP T(AR 10 CATC Cun,nAtivt 1?. Report period hours: 744.0 744.0 219,912.0

13. Hours reactor critical: 744 .0 744.0 175,550.4

14. Reurter reserve shutdown bours x 0.0 0.0 1,2B5.0

15. Haur s gereret or on* L ir>e: 744.0 744.0 167,031.2

16. Unit reserve shutdown hcurst 0.0 0.0 398.0 17 Cross thernal energy generated (MWtH): 1,347,687.0 1,347,687.0 292,260,459.0 *

18. Gross electrical energy generated (MWeH): 451,327.0 451,327.0 95 5 909.0 *

19. Net electrical energy generated (MWeH) 431,095.0 431,075.0 90,992,296.6 *

20. Unit service factor: 100.0 103.0 76.9

21. Unit availability factor: 100.u 100.0 77.0 22, Unit capacity f actor using MDC net: 103.5 103.5 75.1

23. Unit capacity f actor using DER net: 99.6 97.6 71.1

24. Unit forced outage rate: 0.0 0.0 5.6

25. forced cutage hours: 0.0 0.0 10,073.5

26. Shutdawns scheduled over next 6 nonths (type,date, duration): $/15/93 7/27/93 Refucting

27. If currently shutdown, estimated startup date: N/A

• Cumulative values f rom the first criticality (07/24/67). (The rcmaining cumulative values are f rom the first date of concercial operation, 01/01/65),

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Refuellne Infanguttion Reauest ,

1. Name of facility t

llaklam Neck .;

2. Scheduled date for next refueling shutdown.

May 15,1993 ]

3. Scleduled date for restart following refueling.  ;

July 27,1993 .

4. (a) Will refueling or resumption of opeintion thacafter requisc a technical specification change or ot!ct license amendment?  ;

Yes r

(b) If answer is yes, what,in general, will these be?

Technical Specification change to remove three kxp rpecifications and failed fuel rtxi limit o specification.

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety i (c)

Review Committee to Jetennine whether any 'inreviewed safety questions are associated with the core rekuf?

r rVa i

(d) If no such revicw has taken place, when is it scheduled?  ;

n/a

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

March 1993

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier. .

unreviewed design or perfora'ance analysis methods, significant changes in fuel design, new operuting ~

pmcodures.

n/a

7. - De number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool. .

3 (a)~ 157 (b) 757 1

8. The present licensed spent fuel pool storage capacity and the size of any increase in lleensed storage capa 'ity _

that has been sequested or is planned, in number of fuel assemblies.

1168:

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9. %c projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. .

1998' t

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