ML20212C563

Monthly Operating Rept for Aug 1986

ML20212C563
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/31/1986
From:	Drago J, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8612310083
Download: ML20212C563 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY i

HADDAM NECK PLANT HADDAM, CONNECTICUT

/

MONTHLY OPERATING REPORT NO. 86-8 ,

/ l FOR THE MONTH OF k l

AUGUST 1986 \(k C612310083 860831 PDR ADOCK 05000213 R PDR

PLANT OPERATIONS The following is a summary of plant operations for August 1986:

Following completion of the steam generator outage, the unit was phased on line at 0204 hours0.00236 days <br />0.0567 hours <br />3.373016e-4 weeks <br />7.7622e-5 months <br /> on August 2. The plant reached 100 percent power on August 6 at 0442 hours0.00512 days <br />0.123 hours <br />7.308201e-4 weeks <br />1.68181e-4 months <br />.

On August'6 at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, the unit commenced a load reduction to 80 percent power to perform incore flux mapping and calibration of the excore detectors. The plant returned to 100 percent power on August 10 at 1108 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.21594e-4 months <br />.

The plant continued operating at full power until August 31 at 1929 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.339845e-4 months <br /> when the unit was manually tripped due to the failure of number one steam generator feed regulating valve. The valve failed open due to separation of the plug from the valve stem, causing full feed flow and low feed pump suction pressure.

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. , i INSTRUMENTATION & CONTROL EFFECT SPECIAL PRECAUTIONS SYSTEM AUGUST 1986 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION , REPETITION DURING REPAIR NIS (axial offset) Minor work on Abnormal varia- None A procedural change was Reduction in power fo e detectors and tion between made to notify Engineering below 80 percent. I cables caused the channels. when the detectors are detectors to be moved.

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. AVERAGE' DAILY UNIT POWER LEVEL 4

DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE Sept. 1986-  ;

. COMPLETED BY J.--P. Drago E

TELEPHONE (203) 267-2556

~ MONTH: August 1986 DAY' ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) l' 0 17 538-2 12 18 538 3 -33 19 537 4 '7I -

20 537

.5 168 21 538-6 457 22 _

538 7 426 23- 538 8 424 24 540 9 427 -25 542 f 10 513 26 541 1

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11 534 27 541 12 539 28 545 13 539 29 548 14 '540 30 440 15 539 31 0 16 538 .

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt.

(9/77)

i CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: AUGUST 1986 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM l ..............................................:......................

PH & 25 DEGREES C  : 6.10E+00 1 6.43E+00 : 6.62E+00 :

i CONDUCTIVITY (UMHOS/CH)  : 1.40E+01  : 1.93E+01 : 2.60E+01 :

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)  : 8.99E+02  : 1.03E+03 : 1.55E+03 :

LITHIUM (PPM)  : 1.11E+00  : 1.61E+00 : 1.95E+00 :

TOTAL GAMMA ACT. (UC/ML)  : 2.72E-02  : 3.68E-01 : 7.76E-01 :

IODINE-131 ACT. (UC/ML)  : 3.06E-04  : 5.45E-03 3.48E-02 :

I-131/I-133 RATIO  : 8.50E-01  : 2.26E+00 : 2.09E+01 :

CRUD (MG/ LITER)  : <1.00E-02  : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML)  : 2.95E-01  : 6.41E-01 : 1.09E+00 :

HYDROGEN (CC/KG)  : 4.41E+01 5.00E+01 5.74E+01 :

,. AERATED LIQUID WASTE PROCESSED (GALLONS): 7.93E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 5.79E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 6.43E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0.00E+00 I

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NRC' Oper ati n'g Statun Repor-t Haddam Neck k l. Docket: 50-213-

2. Reporting Period: 08/86 Outage + On-line Hours: 54.6 + 689.4 = 744.0

3. Utility

Contact:

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

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4. Licensed Thereal Power (Mt): 1825

5. Naseplate Ratir.g (6ross Me): 667 x 0.9 = 600.3

16. Design Electrical Rating (Net Me): 582

7. Maxinus Dependat,le Capacity (6ross Me): 595.8

8. Maxieus Dependable Capacity (Net Me): 569

9. If changes occur above since last report, reasons are: NONE 10.' Power level to which restricted, if any (Net Me): N/A 11.' Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE

- 12. Report period hours: 744.0 5,831.0 163,631.0

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13.' Hours reattor critical:- 710.0 2,342.9 138,742.3

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

' 15. Hours generator on-line: 689.4 2,108.0 132,909.8

16. Unit reserve shutdown hours: 0.0 0.0 398.0

17. 'Bross thereal energy generated (Mtil): 1,084,490.0 3,019,963.0 230,135,875.0

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18. Gross electrical energy generated (MeH): 335,718.0 935,979.0 75,466,846.0

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- 19. Net electrical energy generated (MWeH): 316,580.2 858,867.7 71,758,038.0

• l 20. Unit service factor 92.7 36.2 81.2

21. Unit availability factor: 92.7 36.2 81.5

22. Unit capacity factor using MDC nett 74.8 25.9 80.4-

. 23. Unit capacity factor using DER net 73.1 25.3 75.4 i 24.' Unit forced outage rate: 7.3 25.0 6.1 l 25. Forced outage' hours: 54.6 701.3 B,570.1 i

l 26. Shutdowns schedoled over next 6 sonths (type,date, duration): NDNE

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

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• Cumulative values from the first criticality (07/24/67). (The resaining cusulative values are fras the first date of cessercial operation, 01/01/68).

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213' UNIT NAME Haddam' Neck DATE Sept. 1986 COMPLETED BY J. P. Drago REPORT MONTH August 1986 TELEPHONE (203)267-2556

% e cm oM M U

No. Date o

og N yJ $ LER

<r ge Cause & Corrective u o o jj " RPT. $ o 13 Action to S

" US $ U$ OFu Prevent Recurrence 5" E ]$ jjmaM h@ NO O 86-07 8-1-86 F 26.07 A 1 36-035 SF HTEXCH Primary water stress (continued) corrosion cracking of steam generator tubes.

Plug affected tubes and evaluate steam generator chemistry.

86-08 8-6-86 F 49.30 F 5 36-038 IE INSTRU Due to work performed on the excore nuclear instru-mentation, the incore/ex-core axial offset correla-tion became invalid.

Initiated procedural change to ensure Reactor Engineer-ing is notified of work performed on NIS.

86-09 8-30-86 F 28.52 A 2 36-041 HH VALVEX Feedwater control valve failed open (plug separated from stem. Long term currecLive activu nut yel 1 2 3 estaglished.

F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) H-Other(Explain 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

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

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~. * * *' REFUELING INFORMATION REQUEST 1.- Name of facility Connecticut Ydnkee Atomic Power Company

2 Scheduled date for next refueling shutdown.

-July - 18, 1987 (last day - at full . power) i

'3. l Scheduled date for restart following refueling.

October 23, 1987-(first day at full power) 4.- (a). Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

NO (b) If answer-is yes, what, in general, will these be?

Not applicable.

-(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)?

Not applicable.

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

~

Not applicable.

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

Not' applicable.

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) 597

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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0 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1

• BOX 127E

• EAST HAMPTON, CONN. 06424 l

September 15, 1986 Docket No. 50-213 Director, Office of Resource Management l U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l 7 ear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 86-8, covering operations for the period August 1, 1986 to August 31, 1986, is hereby forwarded.

Very truly yours, Richard H. Graves Station Superintendent RHG/mdw

' Enclosures cc: (1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 fhbY f