ML20211H024

Monthly Operating Rept for Mar 1986

ML20211H024
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1986
From:	Dean C, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8606230008
Download: ML20211H024 (10)

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o-I CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RADDAM, CONNECTICUT t

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MONTHLY OPERATING REPORT NO. 86--3 '

FOR THE MONTH OF MARCH 1986 9

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PLANT OPERATIONS The plant continued with its 13th refueling and maintenance outage during the month of March.

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IBSTRUMENTATION & CONTROLS MARCll 1986 CORRECTIVE ACTION SPECIAI,PRECAbTIONS SYSTEM EFFECT ON OR MA1.FilNCr 10ii SAFE TAKEi4 TO PREVEsiT TAKEN TO PROVIDE CAUSE RESulil' OPERATION REPETITION FOR REACTOR SAEETY COMPONENT DURING REPAIR There were no reportable items for the month of March.

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MAINTENANCE MARCII 1986 .

CORRECTIVE ACTION SPECIAI, PRECAUTIONS SYSTEM EFFECT 0[4 OR mal.FilN('T I ON SAFE TAKEN TO PREVENT TAKEN TO PROVIDE CAUSE RESULT OPERATION REPETITION FOR REALTOR SAEETY COMPONENT DURING REl'sl R MSTV-1211-1,'2, 3, 4 Valve disc None--pins N/A Installed new hinge pins N/A hinge pins bent found bent during PM Reason--unknown inspection of valve Electric Driven Fire liigh vibration Pump in None Rebuilt pump and motor N/A -

Pump operation Reason--pump and motor bearings worn out

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AVERAGE DAILY' UNIT POWER LEVEL.

. DOCKET NO. 50-213 Conn. Yankee t UNIT Haddam Neck DATE April 15, 1986 COMPLETED BY C. B. Dean TELEPEONE (203) 267-2556 l M0?"nt: March 1986-i i '

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 .0 5 0 21 '0 6 0 22. 0 -

! 7 0 23 0 8 0 0' 24 0 0 9 25.

0' 0-

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11 0 27

.0' 12 0 28 0 13 0 29- 0

.14 0 30 0-15 0 31 0 16 0 l

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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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: MARCH 1986 MINIMUM AVERAGE MAXIMUM REACTOR COOLANT ANALYSIS PH G 25 DEGREES C  : 4.52E+00 : 4.58E+00 : 4.65E+00 :

CONDUCTIVITY (UMHOS/CM)  : 8.10E+00 9.03E+00 : 9.60E+00 :

CHLORIDES (PPM)  : <5.00E-02 3 <b.00E-OZ 3 (D.00E-UZ ;

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

BORON (PPM) 2.72E+03 : 2.84E+03 2.98E+03 :

0.00E-01 : 0.00E-01 3 0.00E-01 i JLITHIUM (PPM) 3.29E-03 :

TOTAL GAMMA ACT. (UC/ML)  : 1.62E-04 : 1.35E-03  :

IODINE-131 ACT. (UC/ML)  : 0.00E-01 : 0.00E-01  : 0.00E-01 :

1-131/I-133 RATIO  : 0 00E-01 : 0.00E-01 i 0.00E-01 i CRUD (MG/ LITER)  : 1.00E-03 2.21E-01 3.80E+00 :

TRITIUM (UC/ML)  : 5.34E-02 : 6.08E-02 6.62E-02

- -'" H Y D R O G E N (CC/KG)  : 0.00E-01 : 0.00E-01 3 0.0DE-01 i AERATED LIQUID WASTE PROCESSED (GALLONS): 5.60E+05 WAbit LIQUID FMUGLb5EU IHKUUUH UUKUN MLUUVtKTL6ALLONb); 2.56E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 0.00E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER HINUTE): 0.00E+00 CNot done plant in Refueling Mode.

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NRC Opcrating Stotun Ropor-t Haddam Neck

1. Docket: 50-213 2, Reporting Period: 03/86 Outage + On-line Hours: 744.0 + 0.0 = 744.0

3. Utility

Contact:

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

4. Licensed Thernal Power (Mt): 1825

5. Naseplate Rating (6ross Me): 667 0.9 = 600.3

6. Design Electrical Rating (Net Me): 582

7. Maxinus Dependable Capacity (6ross M e): 595.8

8. Maxinus Dependable Capacity (Net Me): 569

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

10. Power level to which restricttd, 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 2,160.0 159,960.0

13. Hours reactor critical: 0.0 86.8 136,486.1

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

15. Hours generator on-line: 0.0 76.2 130,877.9

16. Unit reserve shutdown hours: 0.0 0.0 398.0

17. Gross thermal energy generated (MtH): 0.0 117,556.0 227,233,468.0 *

18. Gross electrical energy generated (MeH): 0.0 38,277.0 74,569,144.0 e

19. Net elettrical energy generated (MeH): -2,631.8 27,591.5 70,926,761.7 *

20. Unit service factor: 0.0 3.5 81.8

21. Unit availability factor: 0.0 3.5 82.1

22. Unit capacity factor using MDC net: 0.0 2.2 81.4

23. Unit capacity factor using DER net: 0.0 2.2 76.2

24. Unit forced outage rate: 0.0 0.0 5.7

25. Forced outage hours: 0.0 0.0 7,868.8

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

27. If currently shutdown, estimated startup date: 04/20/86

• Cuaulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of coseercial operation, 01/01/68).

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME IInddam Neck.

DATE April 15, 1986 COMPLETED BY C. B. Dean REPORT MONTil March 1986 TELEPil0NE (203)267-2556 a

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No. Date E9 N

.o $ g 1.ER 4 0e Cause & Corrective "o d$ $ ,8 0 0 RPT. 0 $'E Action to

[ 0:$ $ U$ O' Prevent Recurrence t0" 5 ]g,@fg

• • M m0 0 86-01 3/1/86 S 744 C 1 N/A RC Fuel XX Continuation of Core 13-14 Refueling I 2 3 4 F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (ExpInin) 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 (14ER) FiIe D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5

] C-Operational Error (Explain) Exhibit 1 Same Sourro

REFUELING INFORMATION REQUEST

1. Name of facility Connecticut Yankee Atomic Power Company

2. Scheduled date for nexc refueling shutdown.

July 4, 1987

3. Scheduled date for restart following refueling. ,

4 April 23, 1986 4.- (a) Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

J YES l (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 I 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?

April 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 i

fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

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

i (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

O sh CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR # 1. BOX 127E. EAST HAMPTON, CONN. 06424 April 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 86-3, covering operations for the period March 1, 1986 to March 31, 1986, is hereby forwarded.

Very truly yours, b WW Richard H. Graves Station Superintendent RHG/dfv -*

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 Y' > ,

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