ML20203E114

Monthly Operating Rept for Jan 1986

ML20203E114
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/31/1986
From:	Dean C, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC
References
NUDOCS 8604240110
Download: ML20203E114 (10)

Text

_- _ . _ . _ . _ . . _ _ _. . _ . _ __ _ _

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.~ 50-213 Conn. Yankee UNIT Haddam Neck- ,

1 DATE Feb. 15, 1986 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH: JANUARY 1986 r

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

! '(MWe-Net) (MWe-Net) 1 492 17 0 l t

] 2 490 18 0

.I

l 3 488 '19 0  ;

! 4 21- 20 0 5 0 21 0 6 0 22 0 7 0 0 23 8 0 0 24 9

0 0 i 25 '

10 0 0 26 11 0 27 0 12 0 28 0 -

13 0 29 0 14 ,

0 30 0-

15 0 31. 0 16 0 b

! INSTRUCTIONS 1

l On this format, list the average daily unit power level.in MWe-Net for each. day g 2 in the reporting month. Complete the nearest whole megawatt.

2 B604240110 860131?

PDR R

ADOCK 05000213 PDRc (9/77) f[l 1

_ , _ . . _ , . . _ . _ _ . _ . ~ . . . - - . . . .. ___

- - - ~ _ -_ ..m.~.. . .- m - - - - - - , . - _ - . - . -- ---- . - - . -. . ~_ - .- - .-_ _ . . -.._-.---. _.w CONNECIlCLLT_ YANKEE REACTOR COOLANT DATA MONTH: JANUARY 1986 REACTOR COOLANT ANALYSls MINIMUM AVERAGE MAXIMUM PH 0 25 DEGREES C  : 4.43E+00 : 5.06E+00 : 7.95E+00  :

__ CONDUCTIVITY _(UMHOS/CM) . .: 9.10E-01__ .7.84E+00 1.30E+01  :

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

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

._ILORON (PPM)  : 1.00E-01

• 2.30E+03

• 2.84E+03  :

LITHIUM (PPM)

• 2.50E-02 : 3.13E-02

• 3.50E-02  :

TOTAL GAMMA ACT. (UC/ML)  : 1.02E-02 : 2.16E-01 : 1.04E+00  :

_ IODINE-131.ACT.-(UC/ML)- _ _ _ *

- 3.05E-04.:_.1,55E-02_:. ._ _1. 51 E-01_ :.. _ ___ _ _ _ _._._ _

I-131/I-133 F;ATIO  : 1.07E+00 : 1.20E+00 : 1.39E+00 : l CRUD (MG/ LITER)  : <1.00E-02 : <1.00E-02 : <1.00E-02

• TRTTTtlM (llc,'Ml-)  : 1 t0f,E-01 : 2.60E-01 4.81E-01 :

HYDROGEN (CC/KG)  : 5.50E-01

• 2.12E+01 2 3.33E+01 :

AERATED LI_(lUIIL__WASIE PROCESSED (G AL,L_ ORS)

• 5.03E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 6.84E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 4.25E-01

_---_. PRIMARY __TO SECONDARY LEAK RATE (GALLONS _PER. MINUTE):. ._0 . 0.0 E + 0.0. _ _

00* P1 nn t- chiit AnmJnniinp ygMgggg N

1

%_...a4- -- - _ . - . - - .- - ~. - e+ -,- . --. -..  %- - - , - - -.m --.----.w.-#,sa----- - - -m-~+--. i. , - ------e*

we--< ,-

-,s---w4<,--,-.-,w- ' *_ - - . . - - + _ _ - - - - _ _ --- 4 _. - - - - - ~ ----_.--.--=-,--.-w -

.._-_m,ae-g---..ew--4.-.-wa -_m=.i- a

. NRC Operating Status Report Haddam Neck

1. Ecchet: 50-213

2. Kepcrting Period: 01/86 Outage + On-line Hours: 667.8 + 76.2 = 744.0

3. Utility

Contact:

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

4. Licensed Thermal Foner (MWtle 1825

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

6. Cesign Electrical Rating (Net MWe): 582 .

7. Marinus Eepentable Capacity (Eross MWe): 595.8

8. Manaua Dependable Capacity (Net MWe): 569

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

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

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

12. Eeport period hours: 744.0 744.0 158,544.0

13. Hours reactor critical: 86.8 86.8 136,486.1 14.'Reactcr reserve shutdcen hours: 0.0 0.0 1,285.0

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

16. Unit raserve shutdown hours: 0.0 0.0 398.0

17. Gross thereal energy generated (MWtH): 117,556.0  !!7,556.0 227,233,468.0 t

18. Gross electrical energy generated (MWeH): 38,277.0 38,277.0 74,569,144.0 t

19. Net electrical energy generated (MWeH): 32,794.6 32,794.6 70,931,964.8 8

20. Unit service factor: 10.2 10.2 82.5

21. Unit availability factor: 10.2 10.2 82.8 I 22. Unit capacity fatter using MDC net: 7.7 7.7 82.2

23. Unit capacity factor using DER net: 7.1 7.6 76.9

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 aanths (type,date, duration): NONE +

27. If currently shutdown, estiaated startup date: April 5,1986 8 Cuaulative values froa the first criticality (07/24/67). (The remaining cueulative values are froa the first date of coseercial operation, 01/01/68).

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

UNIT NAME IIaddam Neck DATE Feb. 15, 1986 COMPLETED BY C. B. Dean REPORT MONTil JANUARY 1986 TELEPilONE 267-2556 u o ow m "

No. Date g N

.o f) y I,ER -s Cause & Corrective e uo o jd y RPT. U oo Action to h Nl0 $ g U$ fi U Prevent Recurrence 5~ s5 ]$*OM j tn 0 0 .

86-01 1-4-86 S 668 hrs. C 1 N/A RC Fuel XX Core XIII - XIV Refueling 1 2 3 4 F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) II-Other(Explain 1-Manual for Preparation of Data B-Mainter.ance or Test 2-Manual Scram Entry Sheets for Licensec C-Refueling 3-Automatic Scram Event Report (I.ER) I'll e D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

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

l 4

REFUELING INFORMATION RFQUEST ,

i

1. Name of facility

Connecticut Yankee Atomic Power Company 1

l

2. Scheduled date for next refueling shutdown.

July 4, 1987

3. Scheduled date for restart following refueling.

April 5, 1986  !

f 4. (a) Will refueling or resumption of operation thereafter require a technical speci-i fication change or other license amendment?

i YES (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.

4 i (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)?

l 2

Core reload design in progress. .

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

i j February 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

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 1

i 3

8. The present licensed spent fuel pool storage capacity and the size of any increase in j licensed storage capacity that has been requested or is planned, in number of fuel l 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 1

. I 1

8 -

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

Very truly yours, 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 ,

'l t i

o CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 86-1 FOR THE MONTH OF i l

JANUARY 1986 l 1

D PLANT OPERATIONS The plant operated in a coastdown mode until January 4 at 0003 when a load reduction commenced for refueling. At 0410, the plant was off line to start the 13th refueling and maintenance outage. The outage continued for the renth of January 1986.

l i INSTRUMENTATION AND CONTROL ,

j SYSTFJi JANUARY 1986 EFFECT ON ':0HitECTIVE ACTION SPECIAl, PRECAUTIONS on M Al.FilNCT I ON SAFE TAKEN TO Pl! EVENT TAKEN TO PROVIDE COMPONENT CAUSF. RESUI.T OPEtlATION REPETITION Folt REAGl'OR SAFF.TY DitRING REP.i1R i

h There were na f reportable items for f the month of January, d

r SYSTFJi MAINTENANCE JANUARY 1986 EFFECT ON ColtRECTIVE ACTION SI'ECI AI, PitECAUTIONS ,

01, M AI,FilNCT I ON SAFE TAKEN TO PitEVENT TAKEN TO Pl!OVIDli C0tlPONENT CAUSE  !!ESUI.T OPERATION REPETITION FOR REAGTOR SAFETY DUltING ltEPalR Main Steam Safety SV-13 failed Set pressure None--plant shut down Valve sent to factory and N/A Valve to open during of valve tested okay. Cause of "as found" could not be problem was determined to test determined be a disconnected fitting on test device i

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