ML20137U135

Monthly Operating Rept for Nov 1985

ML20137U135
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/30/1985
From:	Dean C, Graves R, Trejo R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
85-11, NUDOCS 8602190061
Download: ML20137U135 (10)

Text

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c e CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM UECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 85-11 FOR THE MONTH OF NOVEMBER 1985-8602190061 851130 PDR ADOCK 05000213 R PDR

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Li ~ ll PLANT OPERATIONS I The .following is a summary of plant operations for November,1985:

The unit commenced a load decrease to 73% power on November 8 at 0721. hours to reset reactor coolant flow trip setpointa. The unit returned to 100% power at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.

On November 10 at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, an automatic reactor and turbine trip occurred due

.to spurious steam line high 4 P signals.

The plant phased on line at 1927 hours0.0223 days <br />0.535 hours <br />0.00319 weeks <br />7.332235e-4 months <br /> on November 10. After chemistry holds at 5% and 25% power, the unit reached full power on November 11 at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br />.

On November.12 at 2359 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.975995e-4 months <br />, the unit reduced load approximately 10 MWe after receiving an alarm on #4 high steam flow AP. The unit returned to full power at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on November 13.

An automatic reactor and turbine trip occurred on November 21 at 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br /> during setpoint adjustment of the high steam flow trip. Since the unit is in a coastdown mode and steam flows are higher, interaction occurred bctween loops.

The interaction was due to the high steam flow signals being close to the trip point completing the 2/4 logic resulting in a reactor trip.

The plant phased on line on November 22 at 0147 tcurs. After chemistry holds, the plant started increasing load. The unit decreased load to 280 MWe on November 22 at 1352 hours0.0156 days <br />0.376 hours <br />0.00224 weeks <br />5.14436e-4 months <br /> due to steam generator feed pump vibration. At-1500 hours, the plant commenced a load increase.. The unit had to reduce load to 300-MWe at 1634 b2cause of problems with "A" steam generator-feed pump. The unit came off line on November 27 at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> to repair _the feed pump. The unit phased on line at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> on November 28, and after chemistry holds, reached full power at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on November 30.

INSTRUMENTATION AND CCNTROL

• NOVEMBER 1985 CORRECTIVE ACTION SPECIAL PRECAUTIONS SYSTEM EFFECT ON OR mal.Ft1NCT I ON SAFE TAKEN TO l'REVENT TAKEN TO Pit 0 VIDE CAUSE RESULT OPERATION REPETITION FOR REACTOR SAFETY COMPONENT DURING REPAIR Stt n line break Spurious noise Caused trip N/A Set trip points as far N/A p ro tective ' circuit and channel away from signal as interaction possible according to tech spec e

MAINTENANCE NOVEMBER 1985 '

'TVE ACTION SPECIALPRECAUh10N OR - mal.FilN CT I ON SAFE TAKEN TO PREVENT TAKEH TO PROVIDE COMPONENT CAUSE RESULT OPERATION REPETITION FOR REAGTOR SAFETY DURING REP,iiR There were no reportable items for the month of November .

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' AVERAGE DAILY. UNIT POWER'.LEVELE

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1 DOCKET NO. ~ 50-213' -

Conn. Yankee UNIT Haddam Neck

.DATE Dec. L15; 1985'

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COMPLETED: BY C. B'. : Dean .

i TELEPHONE (203):-2'67-2556-

' MONTH: , November 1985 I . DAY AVERAGE DAILY' POWER LEVEL DAY ~ AVERAGE DAILY POWER LEVEL'-

(MWe-Net) ,;(MWe-Ne t) -

-580 1 17 559 2 578 18; '560- _

3 576 19' 559 -

4 573 20j 559 i 5 574 211 333 6 573 -22 58

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7 572 23 i206 8 504 24 253 9 575 25 2'56 i

10 42 26 -264 l

.; 'll 256 27 14

! 12 505 28 19 '

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.13 560 -29 133 1

-560 14 30' 300:

15 561 31 16 561 1

. INSTRUCTIONS .

_ On this format, list the average daily . unit power level in MWe-Net Dfor: each day ,

in the reporting month._.-Complete.the nearest.whole. megawatt' Y

(9/77)'_

. - __-___ 2____. r ____._L L _ _._ - _:_.___-_n__- -__-__-___._._ __.- : -__._:-.-.. ._ -

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CONNECTICUT.Y NiiEE REACTOR COOLANT DATA MONTH: NOVEMBER 1985 ~

REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH G 25 DEGREES C  : 5.87E+00 : 7 07E+00 : 9.19E+00 :

CONDUCTIVITY (UNHOS/CM)  : 5.00E-01 : 2.09E+00 : 4.80E+00 :

CHLORIDES (PPM)  : <5.00E-02 : <5.00E-02 : <5.00E-02.

DISSOLVED OXYGEN (PPB)  : <5.00E+00 : <5.00E+00 : <5.00E+00 :

~~50RON (PPM)  : 1.50E-01 : 5.32E+01 : 2.17E+02 :

LITHIUM (PPM)  : 1.00E-02 : 1.19E-01 : 6.70E-01 :

TOTAL GAMMA ACT. (UC/ML)  : 2.89E _01 : 1.08E+00 : 1.65E+00 :

IODINE-131 ACT. (UC/ML)  : 4.21E 2.39E-02 : 1.72E-01 :

I-131/I-133 RATIO  : 1.41E+00 5.16E+00 2.59E+01 !

CRUD (MG/ LITER)

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<1.00E-02 : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML)  : 6.47E-01 : 7.02E-01 7.45E-01 :

HYDROGEN (CC/KG)  : 3.42E+01 3.70E+01 4.10E+01 :

AERATED LIGUID WASTE PROCESSED (GALLONS): 1.13E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 2.11E+05 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 5.98E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):' O.00E+00 L

NRC Opercting Stetua Rcpert Hnddem Neck 1.' Docket: 50-213

2. Reporting Period: !!/85 Outage + On-line Hours: 34.0 + 686.0 = 720.0

3. Utility

Contact:

J.P. Drago (203) 267-2556, ext.~ 452

4. Licensed Thereal Pcuer (MWt): 1825

5. Naseplate Rating (Gross MWe): 667 x 0.9 = 600.3 6.' Design Electrical Rating (Net MWe):. 582 7.' Manieue Eependable Capacity (6ross MWe): 595.8

8. Maxieue Deper.dable Capacity (Net MWel 569

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

10. Fewer level to which restricted, if any (Net MWel: N/A 11.' Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours: 720.0 8,016.0 157,056.0

13. Hours reactor critical: 696.6 7,938.4 135,655.4

14. Reactor reserve shutdown hours: 0.0 21.0 1,285.0

15. Hours generator on-line: 686.0 7,877.9 130,082.5

16. Unit reserve shutdeun hours: 0.0 24.3 398.0 17.' Gross thereal energy generated (MWtHl 962,315.0 13,684,030.0 225,871,200.0 8

18. Gross electrical energy generated (MWeH): 310,222.0 4,464,170.0 74,123,320.0 1 j 19. Net electrical energy generated (MWeH): 292,168.4 4,250,953.0 70,512,020.0 t

20. Unit service factor 95.3 92.3 82.0

21. Unit availability factor 95.3 98.6 83.1

22. Unit capacity factor using MCC net 71.3 93.2 82.5

23. Unit capacity factor using DER net: 69.7 91.1 77.2

24. Unit forced outage rate: 4.7 1.7 5.7

25. Forced outage hours: 34.0 138.0 7,844.1 ,

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26. Shutdowns scheduled over ne. 6 months (type,date, duration): REFUELING 01/04/96 !! MEEKS

27. If currently shutdoen, estimated startup date: N/A t Cueulative values free the first criticality (07/24/67). (The remaining cueulative values are free the first date of ;

consercial operation, 01/01/68).

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME conn. Yankee DATE Dec. 15, 1985 COMPLETED BY R. Trejo REPORT MONTil November 1985 TELEPil0NE (203)267-2556

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No. Date E9 N .o f; y LER 4 8e Cause & Corrective "o D$ $ ,g g RPT. U $'8 Action to

[ dS E yDhyy U$ O' Prevent Recurrence S E. fbAM NO O 85-09 11/10/85 F 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> A 3 85- IA INSTRU Erroneous steam flow 47 minutes 028-0( high AP signal (ESF) 85-10 11/21/85 F 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> A 3 85-25 minutes 028-0( IA INSTRU Erroneous steam flow high AP signal (ESF) 85-11 11/27/85 F 5 hou.s A 1 N/A Cll

• PUMPXX Generator taken off-line 30 minutes to repair steam generator feed pump vitsration 1 2 3 4 F Forced Reason: Hethod: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) II-Other(Explain 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licenset C-Refueling 3-Automatic Scram Event Report (I,ER) File D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 Same Sourro

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REFUELING INFORMATION REQUEST

-1. Name of facility Connecticut Yankec Atomic Power Company

2. Scheduled date for next refueling shutdown.

January 4, 1986

3. Scheduled'date for restart following refueling.

I March 19, 1986

4. (a) Will' refueling or resumption of operation thereafter require a technical speci-fication change or cther license amendment?

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

1. Revise the allowance factors in calculating core power peaking.

2. Revise the axial offset limits for 4 loop and 3 loop operation.

3. Revise the RCS mass flow specification due to anticipated S/G work.

(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 questions are associated with the core reload (Ref.10 CFR Section 50.59)?

Core reload design in progress.

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

January 1986

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

December 1985

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.

NO

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

(a) 157 (b) 545 '

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

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

1994 to 1995

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.s. s CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR # 1. BOX 127E. EAST H AMPTON, CONN. 06424 December 15, 1985 Docket No. 50-213 Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ,

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 85-11, covering operations for the period November 1, 1985 to November 30, 1985, is hereby forwarded.

Very truly yours, IldMa-Richard H. Graves Station Superintendent RHG/dfv Enclosures cc: (1) Director, Region I Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Asenue King of Prussia, PA 19406 (2) Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

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