ML20214L723

Monthly Operating Rept for June 1986

ML20214L723
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1986
From:	Dean C, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8609100341
Download: ML20214L723 (10)

Text

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. CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT-l MONTHLY OPERATING REPORT NO. 86-6 FOR THE MONTH OF JUNE 1986 8609100341 860630 PDR ADOCK 050002 3 R P

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

On June 2 at 1358 hours0.0157 days <br />0.377 hours <br />0.00225 weeks <br />5.16719e-4 months <br />, NIS channel 33 generated a load runback-signal. The load limiting device on the turbine did not function properly and a manual load reduction was initiated to adjust the load limiting device. The plant returned to 100 percent power at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.

On June 4 at 1917 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.294185e-4 months <br />, the plant was manually tripped after receiving indication of loss of a main feedwater pump, due to failure of the heater drains tank level control valve.

After repairing the valve, the unit phased on line on June 5 at 0658 hours0.00762 days <br />0.183 hours <br />0.00109 weeks <br />2.50369e-4 months <br />. After chemistry holds at 5 percent and 25 percent power, the plant held at 65 percent power to repair NIS channel 34 due to setpoint drift. The unit reached 100 percent power on June 9 at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.

On June 9 at 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />, a load runback occurred caused by a spurious dropped rod stop alarm. The load runback was terminated.

On June 17 at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, the unit commenced a load reduction after receiving a low steam generator feed pump suction pressure alarm. The reactor coolant system pressure continitd to increase and the plant was manually tripped. The feedwater Scs:er drains tank level control valve had failed. The valve was repatted and tested. The reactor achieved criticality on June 17 at Ibe5 hours.

On June 19 at 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, the reactor tripped. The power supply on NIS channel 34 had failed possibly due to a loss of control board ventilation.

The unit phased on line at 1754 hours0.0203 days <br />0.487 hours <br />0.0029 weeks <br />6.67397e-4 months <br /> on June 21, and held at 5 percent for steam generator chemistry.

On June 22 at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br />, a reactor and turbine trip occurred due to debris between two open contacts on the reactor coolant system, low flow trip relays. On June 23 at 1931 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.347455e-4 months <br />, the plant phased on line and remained at 5 percent power for steam generator chemistry.

On June 24 at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />, the unit went to three-loop operation to prepare for loop flow testing. The unit commenced a load increase, holding at 25 percent power for axial offset. The plant reached 65 percent power and successfully completed loop flow testing.

On June 25 at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, the unit commenced a load reduction to return loop 3 to service. At 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />, the plant started a load increase and reached 100 percent power on June 26 at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />.

INSTRUMENTATION & CONTROL EFFECT SPECIAL PRECAUTIONS JUNE 1986 ON CORRECTIVE ACTION TAKEN TO PROVIDE, SYSTDI OR MALFUNCTIOM SAFE TAKEN TO PREVENT FOR REACTOR SAFETY CAUS2 RESULT OPERATION REPETITION DURING REPAIR COMPONENT .

i, NIS Channel 34 Spurious Signal Turbine load None Replace power range channele N/A runback. with state of the art equip-ment (long term).

NIS Channel 34 Failed power Reactor Trip None Replace power range channels N/A supply. (Possibly with state of the art equip-due to high ment.(long term).

temperature in Administrative controls l main control will be implemented for room.) plant operation at elevated temperatures.

Reactor Protection Loop 1 reactor Reactor Trip None Cleaned all relays. Long N/A System coolant low flow term corrective action is trip actuation. to protect relays from l Found foreign intrusion of foreign material in low materials, flow relay.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE July 15, 1986 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH: June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 539 17 244 2 493 18 0 3 541 19 0 4 432 20 0 5 1 21 0 6 23 22 0 122 15 7 23 8

223 118 24 543 174 9 25 546 528 10 26 y3 547 541 27 549 540 12 28 13 29 550 30 15 31 --

546 .

16 a 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)

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1 CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: JUNE 1986 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH 9 25 DEGREES C  ! 6.OAE400 1 A.97F400 2 A.49F400 t l CONDUCTIVITY (UMHOS/CM)  : 1.35E+01 ! 1.72E+01 : 2.00E+01 :

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

,__ DIS.SDLVED_0XY. GEN _(EEB )  : 35.00E+00_ 3 5.00E100_!_<5.00E+00_:

-BORON (PPM)  ! 9.79E+02 : 1.19E+03 : 2.36E+03 :

LITHIUM (PPM)  ! 1.23E+00 : 1.67E+00 : 1 94E+00 :

TOTAL GAMMA ACT. (UC/ML)  ! 1.37E-01 ! 5.22E-01 ! 8.75E-01 !

10 DINE-131 ACT. (UC/ML)  ! 9.60E-04 : 7.08E-03 : 2.56E-02 :

I-131/I-133 RATIO  ! 1.27E+00 : 1.05E+01 : 6.64E+01 :

___CR.UD__(MOZLITER) 31.00E-02_ 3 1_.00ErO2_ 3 1.00E 02._ _

TRITIUM (UC/ML)  : 8.54E-01 : 1.13E+00 : 1.54E+00 :

HYDROGEN (CC/KG)  : 4.34E+01 : 4.55E+01 : 4.04E+01 :

AERATED LIGUID WASTE PROCESSED (GALLONS): 3.15E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 1.36E+07 AVERAGE PRIMARY LEAK RATE (QALLONS PER MINUIE.)! 6269E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 2.16E-02 L

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NRC.Opcrating Stotuc Rapcrt Heddoo Nock

1. Docket: 50-213

2. Reporting Period: 06/96 Outage + On-line Hours: 148.9 + 571.1 = 720.0 3, Utility contact: J.P. Drago (203) 247-2556 ext 452

- 4. Licensed Thereal Power (MWt): 1825 .

5, Naseplate Rating (Gross MWe): 667 x 0.9 = 600.3

6. Design Electrical Rating (Net MWe): 582

7. Maxieue Dependable Capacity (6ross PWe): 595.8

9. Maxieue Dependable Capacity (Net MWe): 569

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

10. Power level to which restricted, if any (Net MWe): N/A

!!. Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours: 720.0 4,343.0 162,143.0

13. Hours reactor critical: 690.4 .

1,333.7 137,783.0

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

13. Hours generator on-line 571.1 1,172.4 131,974.1

16. Unit reserve shutdown hours: 0.0 0.0 398.0

17. Gross thereal energy generated (MWtHl 823,856.0 1,489,989.0 228,605,901.0 t

18. Gross electrical energy generated (MWeH): 254,617.0 462,653.0 74,993,520.0 t

19. Net electrical energy generated (MWeH): 237,017.7 414,960.1 71,314,130.4 8

20. Unit service factor 79.3 27.0 81.4

21. Unit availability fa: tor 79.3 27.0 $1.6

22. Unit capacity factor using MDC net 57.9 16.8 30.7

23. Unit capacity facter using DER net: 56.6 1a.4 75.6

24. Unit forced outage rate: 20.7  !!.3 5.7

25. Forced outage hours: 148.9 148.9 3,017.8

26. Shutdowns scheduled over next 6 sonths (type,date, duration):'NONE ,

27. If currently shutdown, estiested startup dates N/A 8 Cuaulative values 'ros the first criticality (07/24/67), (The reeaining cueulative values are free the first date of 1 cassercial cperation, 01/01/68).

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 '.

UNIT NAME Haddam Neck DATE July 15,'1986 COMPLETED BY C. B. Dean REPORT MONTH June 1986 TELEPHONE 203-267-2556 7

m No. Date Ecn ow n c g LER y

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.e 4 eo Cause & Corrective

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Eom E j$ 0 RPT. S S*8 Action to h g S Prevent Recurrence 86-04 6-4-86 F 11 hrs. A 2 36-027- HH VALVEX Low SC/FP suction pressur a 41 mins. 00 alarn - manual trip.

Repaired valve.

86-05 6-17-86 F 102 hrs. A 2 36-027- HH VALVEX Low SC/FP suction pressur e 39 mins. 00 alarm - manual trip.

Repaired valve.

• 86-05 6-19-86 F A 3 36-025- IA INSTRU Reactor Trip while 00 trouble shooting NI-34 86-06 6-22-86 F 34 hrs. H 3 36-026- IA ZZZZZZ A piece of foreign material 35 mins. 00 (ceiling tile) fell between 2 open contacts.

• The Unit was not phased on line at this tirie , there ' ore this trip : s considered part of tim 6-17-86 shu tdown.

1 2 3 4 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) j E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 Same Source

e REFUELING INFORMATION REQUEST-

1. ~Name of facility Connecticut Yankee Atomic Power Company a 2 Scheduled date for next refueling shutdown.

EJune 13, 1987 (last day at full power)

3. . Scheduled date for restart following refueling.

September 24, 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)?

I 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.

s

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant i 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.

l i (n) 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.

j 1168 I 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 1  !

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O CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1 e BOX 127E

• EAST HAMPTON CONN.06424 July 15, 1986 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 86-6, covering operations for the period June 1, 1986 to June 30, 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 (2) Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

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