ML20212P898

Monthly Operating Rept for Dec 1986

ML20212P898
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1986
From:	Dean C, Miller D CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8703160322
Download: ML20212P898 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT I

MONTHLY OPERATING REPORT NO. 86-12 FOR THE MONTH OF DECEMBER 1986 h, 31 { kh13 een

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

On December 5 at-1433 hours, the reactor achieved criticality

following the completion of maintenance on the number three steam generator. feed water regulating valve.

On December 6 at 0252 hours0.00292 days <br />0.07 hours <br />4.166667e-4 weeks <br />9.5886e-5 months <br />, the unit phased on line and at 1952 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.42736e-4 months <br />, the plant was at 25% power holding for chemistry clearance.

The plant decreased load and came off line at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br /> to repair a loose baffle plate on the "B" moisture separator reheater.

On December 11 at 0239 hours0.00277 days <br />0.0664 hours <br />3.95172e-4 weeks <br />9.09395e-5 months <br /> following completion of the maintenance on the moisture separator reheater, the unit phased on line and reached 16% power at 1250 holding there until December 19.

On December 19 at 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br />, the plant was taken off line and commenced a cool down in order to conduct a Residual Heat Removal (RHR) flow test.

On December 24 at 0618 hours0.00715 days <br />0.172 hours <br />0.00102 weeks <br />2.35149e-4 months <br />, the unit commenced a load increase and at 0706 hours0.00817 days <br />0.196 hours <br />0.00117 weeks <br />2.68633e-4 months <br />, the unit reached 16% power for another chemistry hold.

At 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br />, the plant resumed the load increase.

On December 25 at 0428 hours0.00495 days <br />0.119 hours <br />7.07672e-4 weeks <br />1.62854e-4 months <br />, the unit stopped the load increase at 84% power to evaluate a potential quadrant power tilt question. At 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />, the unit resumed the load increase. At 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />, the unit reached-100% power.

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

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SYSTEM MAINTENANCE DECEMBER 1986 ON. CORRECTIVE ACTION TAKEN TO PROVIDE- 'I OR MALFUNCTION SAFE TAKEN TO PREVElff FOR REACTOR SAFETY .;

COMPONENT CAUSE . RESULT OPERATION REPETITION DURTNG REPAIR: ..

There are no . , j reportalbe items  !

-for the month 1 of December. .

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213~

Conn. Yankee UNIT Haddam Neck DATE January 15. 1987 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH: DECEMBER 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 54 2 0 18 54 3 0 19 37 4 0 20 0 5 0 21 0 6 21 22 0 7 0 23 0 8 0 24 65 9 0 502 25 10 0 359 26 11 26 27 560 12 51 28 560 13 49 29 560 14 49 30 560 15 51 31 561 16 51 INSTRUCTIONS On this format, list the average daily unit power icvel in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt.

(9/77)

CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: DECEMBER 1986 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH e 25 DEGREES C  : 5.99E+00  : 6.36E+00 6.65E+00 :

CONDUCTIVITY (UMHOS/CM)  : 8.10E+00  : 1.27Ef01 : 1.72E+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)  : 5.87E+02  : 1.00E+03 : 1.46E+03 :

LITHIUM (PPM)  : 5.93E-01  : 1.12E+00 : 1.37E+00 :

TOTAL GAMMA ACT. (UC/ML)  : 3.52E-02  : 2.87E-01 : .9.53E-01 :

10 DINE-131 ACT. (UC/ML)  : 3.63E-04  : 1.03E-02 : 8.10E-02 :

I-131/I-133 RATIO  : 8.00E-01  ! 3.06E+01 : 1.98E+02 :

CRUD (MG/ LITER)  : <1.00E-02  : 1.00E-01 : 1.60E+00 :

TRITIUM (UC/ML)  : 8.31E-01  : 1.43E+00 2.13E+00 :

HYDROGEN (CC/KG)  : 1.68E+01  : 3.35E+01 : 4.27E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS): 1.84E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 1.24E+05 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 2.77E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0.00E+00 l

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NRC Oparating Status Roport Haddcm Nock

1. Docket: 50-213

2. Reporting Period: 12/86 Outage + On-line Hours: 320.4 + 423.6 = 744.0

3. Utility

Contact:

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

4. Licensed Thernal Power (MWt): 1825

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

6. Design Electrical Rating (Net MWe): 582

7. Maxisco Dependable Ca;acity (Gross MWe): 515.8

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8. Maximus 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: 744.0 8,760.0 166,560.0

13. Hours reactor critical: 540.5 5,060.8 141,460.2

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

15. Hours generator on-line 423.6 4,685.9' 135,487.6

16. Unit reserve shutdown hours: 0.0 0.0 398.0

17. Gross thereal energy generated (MWtH): 380,276.0 7,264,549.0 234,380,461.0 8

18. Gross electrical energy generated (MWeH):  !!5,061.0 2,282,055.0 76,812,922.0 8

19. Net electrical energy generated (MWeH): 100,891.8 2,132,317.8 73,031,488.0 8

20. Unit service factor 56.9 53.5 81.3

21. Unit availability factor 56.9 53.5 81.6

22. Unit capacity factor using MDC net: 23.8 42.8 80.3

23. Unit capacity factor using DER net: 23.3 41.8 75.4

24. Unit forced outage rate: 43.1 18.3 6.2

25. Forced outage hours: 320.4 1,052.4 8,921.2

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

27. If currently shutdown, estimated startup date: N/A 8 Ceaulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of consercial operation, 01/01/68).

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

UNIT NAMEConn. Yankee DATE Januarv 15 'l'987 COMPLETED BY C. B. Dean REPORT MONTH DECEMBER 1986 TELEPHONE (203) 267-255b u e

~ ow m No. Date $9 N .o $ g LER e "E e Cause & Corrective "o U$ $ ,8 g tj RPT. S SI Action to S E. S E U.g g. o Prevent Recurrence 5" N ]g,ghg**M NO O 86-11 12-1-86 F 122.87 A , 3 86-044 - CJ VALVEX While shutdown, the loop (continuatit n) 00 1 T.C. valve stem leak off pipe / check-valve corrosien was discovered +

and repaired.

86-12 12-6-86 F 99.95 A 1 HJ HTEXCH Load decrease to repair s "B" MSR modified MSR 4

-~ design.

86-13 12-19-86 F 97.58 D 1 86-04F- SF n/a During ECCS review, the 00 . licensee discovered that the fail-safe positi6n of a RHR valve may not provide core protectico *,, .,

1 in a postulated medium j .

break LOCA. A flow test j was performed while shut down to est3blish

correct valve position.

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i 1 2 3 4 F Forced Reason: .

Method: ~

Exhibit G-Instructime;

S scheduled A-Equipeent Failure (Explain)' H-Other(Explain 1-Manual for Preparation of D 4 i B-Maintenadce.or Test '

2-Manual Scram Entry S?.eets for Li. *

• I C-Refueling j

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3-Autor.atic Scr i Event Report (LER) Fi1 D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

E-Operator Training h License Exanination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 Some Source m, i

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, . . 1 yp + r 1[ , , REFUELING INFORMATION REQUEST

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1. Name of facil'tf- i

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Connecticut Yankee Atomic Power Company

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p 2. Scheduled date for next refueling shutdown.

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July 17, 1987'(last day at full power) 3, . - c3cheduled date for rescart following refueling.

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October 21,l1987 (first day at full power) 4 (a) Will rt; fueling ore resumption of operation thereafter require a technical speci-fication chang.e or other license amendment?

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

, The following spec 1fications will be revised for 4 loop and 3 loop operation:

RCS flowrate, safety limit curves and axial offset limits.

(c) If answer is no, has the reload fuel design nd core configuration been reviewed by your Plant Safety Revicw Committee to determine whether any unreviewed safety questions are asscciated 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.

6/1/87

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6 Important licensing considerations associated with refueling, e.g., new or different fuci design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

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7. 'the ni.mbtr of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 557 (b) 397 8; Thr present licensed spent fac1 pool storage capacity and the size of any increase in liccesed storage capacity that has been requested or is planned, in number of fuel annomblies.

1168

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

1991'to 1995

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1

• BOX 127E

• EAST HAMPTON, CONN.06424 January 15, 1987 Docket No. 50-213 Director, Office of Resource Management 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,86-12, covering operations for the period December 1, 1986 to December 31, 1986, is hereby forwarded.

Very truly yours, Donald B. Miller, Jr.

Station Superintendent DBM/mdw l Enclosures cc: (1) Regional Administrator, Regica 1 l U. S. Nuclear Regulatory Commission l 631 Park Avenue King of Prussia, PA 19406 I

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