ML20132E179

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Monthly Operating Rept for Apr 1985
ML20132E179
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/30/1985
From: Dean C, Graves R
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8507170643
Download: ML20132E179 (10)
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!~ ' CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT i

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' MONTHLY OPERATING REPORT NO.'85 _

FOR THE MONTH OF-APRIL 1985 ..

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PLANT OPERATIONS On April 13, 1985, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant commenced a scheduled load reduction to 50 percent power to repair the "B" condensate pump motor. At 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />, the plant reached 50 percent and made necessary repairs. The unit commenced a load increase on April 14, 1985, at 0329 hours0.00381 days <br />0.0914 hours <br />5.439815e-4 weeks <br />1.251845e-4 months <br />, holding at 65 percent power to conduct a routine turbine control valve test. The plant reached full power at 1053 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.006665e-4 months <br />.

The plant reduced load to 97 percent power on April 22, 1985, for a short period of time to work on a feedwater regulating valve.

On April 28, 1985, at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />, a broken air line on a component cooling temperature control valve caused the valve to close. This resulted in heatup of the letdown system causing a release of boron from the demineralizer. Plant load temporarily decreased to approximately 598 Mwe due to the increase in boron concentration. The unit returned to 100 percent power at 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on April 28, 1985.

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E M CE CORRECTIVE ACTIOi4 SPECIAL PRECAUTIOL SYSTEM EFFECT ON APRIL MALFUNCTION 1985 TAKEN TO PREVENT TAKEN TO PROVIDE OR SAFE COMPONENT CAUSE RESULT OPERATION REPETITION FOR REACTOR SAFETY DURING REPAIR .

P-9-1B Boric Acid Worn fitting on Leakage Possible loss of Replaced worn parts NONE Pump CY-85-0229 equalizing boric acid pump line F-17-1 Car Fan Misalignment liigh Possible bearing / Realigned fan to motor NONE CY-65-02231 equipment coupling failure vibration

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l CONNE_CI.ICU_T_Y_ANMEE REACTOR COOLANT DATA MONTH: APRIL 1985 l

REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM l .....................................................................

PH G 25 DEGREES C  : 6.46E+00 : 6.66E+00 : 6.87E+00 :

CONDUCTIVITY (UNHOS/CM)  : 9.50E+00 : 1.31E+01 : 1.69E+01 :

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

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

BORON (PPM)  : 5.09E+02 5.61E+02 : 6.13E+02 :

LITHIUM (PPM)  : 9.03E-01 : 1.21E+00 : 1.45E+00 :

z TOTAL GAMMA ACT. (UC/ML)  : 2.23E-01 6.67E-01 : 1.17E+00 :

4 IODINE-131 ACT. (UC/HL)  : 2.01E-03  : 2.96E-03  : 4.32E-03  :

1-131/I-133 RATIO  ! 8.87E-01 : 1.29E+00 1.80E+00 :

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

DELTlUMEC2ML)  ; :L.38gt00 : 2._02E+00 ! 3.19E+00 :

HYDROGEN (CC/KG)  : 2.74E+01 : 2.88Ef01 3.12E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):-- 5.20E+03 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 0.00E-01.

AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE)! 3.35E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER HINUTE):- -0.00E+00

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE April 1985 COMPLETED BY C. B. Dean l

TELEPHONE (203) 267-2556 MONTH: APRIL l

l l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net) (ML-Net) l 1 583 17 ss?

2 583 18 582 3 583 19 582 4 583 20 582 5 584 l 21 582 1

6 583 581 22 7

583 582 23 1 8 583 24 582 l

9 583 25 582 10 26 581 11 583 27 581 12 583 28 581 13 291 29 581 14 506 30 581 15 582 31 ---

582 16 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)

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

UNIT NAME Conn. Yankee 1 April 1985 DA 1.

COMPLETED BY C. B. Dean REPORT MONTH APRIL 1985 TELEPHONE (203)267-2556 1

% e i ou n u l

No. Date g e

fj N, .o $ g LER 4 E 4 Cause & Corrective i uo o ,8 $ $ RPT. O oo Action to l

h 0:0 E U0 e Prevent Recurrence l 0" N ]U,Ek2

    • M NO O I

l 85-03 04-13-85 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> S B N/A 1 HH MOTORX Reduce power to 50 per-l 53 minutes cent to repair "B" i.

condensate pump motor l

l

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

REFUELING INFORMATION REQUEST'

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

January 4, 1986

3. Scheduled date for restart following refueling.

M rch 1, 1986

4. (a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

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

N/A (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?

N/A

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

N/A

6. Icportant licensing considerations associated with refueling, e.g., new or different fuel d: sign 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 cesemblies.

1168 I

9. The projected date of the last refueling that can be discharged to the spent fuel pool '

c:suming the present licensed capacity. I l

1994 to 1995 l

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  • O CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT RR # 1 BOX 127E. EAST H AMPTON. CONN. 06424 May 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 Monthly Operating Report 85-04, covering operations for the period April 1, 1985 to April 30, 1985 is hereby forwarded.

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

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