ML20024H061

Monthly Operating Rept for Apr 1991 for Connecticut Yankee Haddam Neck Plant

ML20024H061
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/30/1991
From:	Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9105210021
Download: ML20024H061 (10)

Text

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ONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR*1

• BOX 127E

• EAST HAMPTON, CT OC424 9341 May 15,1991 Re: Technical Specification 6.9.1.8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 i

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Dear Sir:

l In accordance with reporung requirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddarn Neck Plant Monthly Operating Report 04-91 covenng operations for the period April 1,1991 to April 30,1991 is hereby forwarded.

Very truly yours, kk John P. Stetz Station Director JPS/va ec:

(1)

Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2)

John T. Shedlosky Sr. Resident inspector Connecticut Yankee

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Lonnecticut Yankee Atomic Power Company lladdam Neck Plant Haddam, Connecticut Monthly Operating Repo:t No. 04 91 For The Month of April, 1991

e Plant Operations Summarv - April 1991 The following is a summary of Plant Operations for April 1991.

On April 1st at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was operating at 100% power.

On April 14th at 0014 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />, a power reduction was initiated for the turbine stop and control valve test. - At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the plant was at 65% power. At 0311 hours0.0036 days <br />0.0864 hours <br />5.142196e-4 weeks <br />1.183355e-4 months <br /> the test was successfully completed.

At 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />, with all systems normalized a power ascension was commenced.

By 0837 hours0.00969 days <br />0.233 hours <br />0.00138 weeks <br />3.184785e-4 months <br />, the plant was operating at 100% power.

The plant continued to operate at 100% power for the remainder of the month.

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AVER AGE DA;LY UNIT POWER LEVEL Docket No: 50-213 Unit:

Connecticut Yankee Haddam Neck Date:

May 15,1991 Completed By: K. C. Emmons Month: April. 1991 Telephone: (203) 267 3654 DAY AVERAGE POWER LEVEL DAY AVERAGE POWER I.EVEL (MWe-Net)

(MWe Net) 1 1E2 17 18 2

1El 18 181 3

182 19 18.2 4

182 20 181 5

18.1 21 181 6

138 22 1El 7

181 23 1E2 8

184 24 131 9.

181 25 131 l

10 181 26 181 11 18f 27 18f 12 184 28 181 13 181 29 1.81 l

14 14._1 30 181 15 181 31 al_a i

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1Nic OPERAflWG STATUS REPORT Maddam he5k

1. Docket: 50 213

2. Reporting Period: 04/91 Outsee

• On line Hours:

0.0 + 719.0

• 719.0

3. Utility contact: J. Stanford (203) 267 3635

4. Licensed Thernet Power (wt): 1825

5. Nameplete noting (Gross w e): 667 x 0.9

• 600.3

-6. Design Electrical telltg (Net we): 582

7. Maxisam Dependable Capselty (Gross we): 591.8

8. Maximum Dependable Cerecity (Net We): 565

9. If changes occur above since test report, reasons are: NONE

10. Power levet to elch *estricted, if any (het We): N/A

11. Reasons for rest:IctIcni, If any: N/A i

l MON 1 H YEAk 70-DATE CUMULAt!VE

' 12. Report period hours:

719.0 2,879.9 204,503.0

13. Heurs reactor critical 719.0 2,597.8 165,671.3

14. Reactor reserve shutdown hours:

0.0 0.C 1,285.3

15. hours e merator on lines 719.0 2,581.2 157,258.8

16. Unit reserve shutdout hours:

0.0 0.0 398.0 l

1Y. Jross thernet energy generated ( w tM):

1,307,387.0 4,604,13h.0 271,277,151.0 *

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18. Gross electrical energy generated (WeM):

440,435.0 1, % 2,3 74.0 88,895,212.0 *

19. Net stectrical ene.gy generated ( WeH):

420,929.0

• 480,413.0 84,457,311.6 *

20. Unit sarvice factors-100.0 89.7 76.9

21. Unit eve;tability factur 100.0 89.7 7.1

22. Unit capacity f actor using MDC nett 103.6 91.0 75.1

23. Unit capack; f actor using DER nets

-100.6 88.4 71.0

24. Unit forced outage rate:

0.0 10.3 6.0

25. Fceced outage hovrs:

0.0 297.8 10,008.1

26. Shutdowns schee.sted over next 6 months (type,date, diration): REFUELING 10/19/91.

27. If currently shutdown, estimated startuo date: N/A 1

• Cumatet!ve values from the first cr!tlLallty (07/.'4/67). (The remaining cunutative values are from the f W,. date of comercial operation, C1/01/65).

M AINTEN ANCE System Malfunction Erfect on Corrective Action Special Precautions Taken -

or Safe Taken to Prevent To Provide for Reactor Safety Component

'Cause Result Operation Repetition During Repair i-There were Ic reportable ite us for Maintenana for the month of April 1991 l

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I&C

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System r1alfunction Effect on Corrective Action Special PrecautionsTaken or Safe Taken to Prevent To Provide for Reac'.or Safety Component Cause Result Operation Repetition During Repair There were n a reportable item s for I&C for the Month of April 1991 9

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Docket No.

50-213 UNIT SHUTD0lDNS ftND PotDER REDUCTIONS Unit Name:

Connecticut Ymkee Date:

May 15,199.

Report Month _Hpril 1991 Completed By: K C. Emmons Telephone 203-267-3654 No Date Type Duration Reason Method LER System Component Caase and Correcttve Action to Prevent Racurrence (nours) of Snutting Report '

Code Code Down paactor No REPO RTABLE5 iUTD0bNS OR POWEF REDUCTIO 15FOR / PRIL 1991 M

REASON METHOD SYSTEM & COMPONENT F Forced A Equioment Failure 1 Manual ExhlDit F & H - Instructtons S Scheduled B Maintenance or Test 2 Manual Scram for Preparation of C Refueling 3 Automatic Scram Dara Entry Sneets D Regulatory Restriction 4 Continueo Licensee Event Report (LER)

E Operator Traintrig & Ltcense Examination S Reduced Loa:1 File ;NUREC -0161)

F Administrative 9 Other G operator Error H Other (Explain)

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a CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: APRIL 1991

~ REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM

......s.....

PH 9.25 DEGREES C 6.58E+00 6 64E+00 6 75E+00 :

CONDUCTIVITY (UMHOS/Cli) 9 54E+00 1.25E+01 :

1.54E+01 :

3 CHLORIDES (PPM)

<5 00E-02 : <5.00E-02 : <5 00E-02 :

DISSOLVED OXYGEN (PPB)

<5.00E+00

<5.00E+00 : <5.00E+00 :

' BORON (PPM) 4.77E+02 :

5.21E+02 :

5.67E+02 :

LITHIUM ; PPM) 9.63E-01 :

1.10E+00 l-1.35E+00 1

' TOTAL GAMMA.ACT. (UC/ML) 6.31E-01 :

1.13E+00 1 2.62E+00 :

10 DINE-131 ACT. (UC/ML) 4.59E-03 :

5 96E-03 :

1.65E-02 :

1-131/I-133-RATIO 1.19E+00

1.53E+00 3.59E+00 :

CRUD (MG/ LITER).

<1 00E-02 1.00E-01 :

2.50E+00 :

TRITIUM.(UC/ML) _

1.12E+00 :

1.51E+00 :

1.86E+00 :

HYDROGEN'(CC/KG)-

2.66F.+01 :

2.99E+01 3.48E+01 :

AERATED LIQUID' WASTE PROCESSED (GALLONS):

1.61E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS)!

7.00E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

3.08E-01 L

PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

3.58E-03 I

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Refuelin e In form ation Reauest 1.

Name of facility lladdam Neck i

2.

Scheduled one for next refueling shutdown.

October 19,1991 3.

Scheduled date for restart following refueling.

December 14,1991 4.

(a)

Will refueling or resumption of operation ehercafter requit e a technical specification change or other

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license amendment?

Yes (b)

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

Revise Section 5 of Technical Specifications to allow ase of zirealoy clad fuel. Obts! i an exemption from 10CFR50 Appendix K Sections I.D.3,l.D.4 and I.D.5.

(c)

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 quesdons are associated with the core rebad?

(Ref.10 CFR section 50.59) n/a (d)

If no such review has taken place. v '.n is it scheduled?

n/a 5.

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

ne exemption request was submitted to the NRC in September 1990. De request for license amendment was submitted in March 1991.

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Imponant 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 pmcedures.

Conversion to zircaloy cladding.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel serage pool.

1 (a) 157 (b) 709 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.

1168 l

9.

He projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capxity.

19 %

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