ML20205D064

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jan 1987
ML20205D064
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 01/31/1987
From: Dean C, Miller D
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8703300326
Download: ML20205D064 (10)


Text

.

AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE February 15. 1987 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH: JANUARY 1987 1

DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 560 17 557 2 561 18 531 3 561 19 556 4 560 20 556 5 561 21 557 ,

6 560 22 560 7 560 23 560 8 560 24 559 9 560 25 560 10 26 560 561 560 11 561 27 561 12 560 . 28 561 13 561 29 561 14 560 30 562 15 560 31 16 360 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.

8703300326 070131 7 l l

'(9/77)

PDR ADOCK 05000213 R PDR

CONNECTICUT YANKEE REACTOR COOLANT DATA NONTH! JANUARY 1987 REACTOR COOLANT ANALYSIS HINIMUM AVERAGE MAXIMUM PH e 25 DEGREES C  ! 6.64E+00 : 6.71Ef00 t 6.83E+00  :

CONDUCTIVITY (UNHOS/CM)  ! 1.02E+01 ! 1.32Ef01 ! 1.80E+01  !

CHLORIDES (PPH) i <5.00E-02 ! <5.00E-02 ! <5.00E-02 i DISSOLVED OXYGEN (PPB)  : <5.00E+00 8 <5.00E+00 1 <5.00E+00  :

BORON (PPH)  : 4.94Ef02 ! 5.34E+02 5.88E+02  !

LITHIUM (PPM)  ! 8 76E-01 ! 1.11Ef00 ! 1.46E+00 i TOTAL GAMMA ACT. (UC/ML)  ! 3.79E-01 ! 9.43E-01 ! 1.27E+00  :

10 DINE-131 ACT. (UC/ML)  ! 3.16E-03 ! 4.80E-03 1 8.87E-03 I-131/I-133 RATIO  ! 9.00E-01 ! 1.53E+00 ! 2.49E+00  !

CRUD (NG/ LITER)  : <1.00E-02 ! <1.00E-02 <1.00E-02  !

TRITIUM (UC/HL) 1.11E+00 ! 1.54E+00 ! 1.95E+00  !

HYDROGEN (CC/KO)  ! 3.64E+01 ! 3.92E+01 ! 4.26E+01  !

AERATED LIQUID WASTE PROCESSED (GALLONS)! 1.36E+05 WASTE LIQUID PROCESSED THROUGH DORON RECOVERY (GALLONS): 0.00E-01 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE)! 2.49E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER HINUTE)! 0.00E+00

c ,

NRC Oparcting Ctatuo Rcprrt Haddam Neck

1. Docket: 50-213
2. Reporting Period: 01/07 Outage + On-line Hours: 0.0 + 744.0 = 744.0
3. Utility Cretact: J.P. Drago (203) 267-2556 est 452
4. Licensed Thereal Power (Mti: 1825
5. Naseplate Rating (Gross Me): - 667 x 0.9 = 600.3
6. Design Electrical Rating (Net Mel 582
7. Manteue Dependable Capacity (Gross Me): 595.8
8. Marisue Dependable Capacity (Net Me): 569
9. If changes occur above since last report, reasons are: NONE
10. Power level to which restricted, if any (Net Me): N/A
11. Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE
12. Report period hours: 744.0 744.0 167,304.0
13. Hours reactor critical: 744.0 744.0 142,204.2
14. Reactor reserve shutdoen hours: 0.0 0.0 1,285.0
15. Hours generator on-line: 744.0 744.0 136,231.6
16. Unit reserve shutdoen hours: 0.0 0.0 398.0
17. Gross thereal energy generated (MtHl 1,353,623.0 1,353,623.0 235,734,084.0 t
18. Gross electrical energy generated (MeHl: 436,185.0 436,185.0 77,249,107.0 8
19. Net elettrical energy generated (M eHl 415,862.9 415,862.9 73,447,350.9 8
20. Unit service f actor: 100.0 100.0 81.4
21. Unit availability factor: 100.0 100.0 81.7
22. Unit capacity factor using MDC net 98.2 98.2 80.4
23. Unit capacity factor using DER net 96.0 96.0 75.5
24. Unit forced outage rate: 0.0 0.0 6.1
25. Forced outage hours: 0.0 0.0 0,921.2
26. Shutdoens schedated over next 6 months (type,date, durationi REFUELING 07/18/8714 WED.S
27. Il currently shutdoen, estimated startup dates N/A i

8 Cueulative values free the first criticality (07/24/67). (The reeaining cueulative values are free the first date of coseercial operation, 01/01/68).

I SF SF N co hr .o ec de ud l

e d

2 D GFEDCBAR a

- - - - - - - e t OAORRMEa p dp eeaqs e emeg fiuo riruunin analetp  :

t it alem i sot ine ot ronan nr rgnt aaTy c ~

lt r eF i aR Evie oi a "Se rens rl u

r it o nr Tr r g i ee c s .

( &t t(

E i E 5OUoe x Lo x p

l in c

p l

"5$an R E

U N

a e a P I i n i O T n s n R

) e ) T 'S H

E H U x O T a N N D m 5EE T O i H H W N

n - S a O ]y,8a om . J t t ' A A i h N N

  • ,@g 5 a o e U D n r A

(

E

  • h R P x Mggg m Y O

-p W l

1 9

E a RL 8 R i PE 7 n .

TR - R

. E D

U C

T I

< 'O N

NU!.

S 3

EE 4321M

- - - - e OAMMt t uaah ht nno *.

eouud rmaa:

( all 508ey*

Et xiS p cc "8'e l r aSa icm nr

) a m P C C JfoN r a O aoro nr 'p eau vcs TM EP UO D

5 4 u u et e LL NC E ( EEfE at on ni EE IK x Nvnox rhwi to& PT TE h t etrh yeet n HE T i mnr i r R C ODDN b w ty P b 1m s et o N AAN i ri 9orh cor EB T M .O t -'RSet 8neu u r YEE 0 e hp 7t dt r e 1 1p eaG ' hudco r c 2 C F C 6oer - e t e o 5

S 1rt aI ot w n i 0 .

n 0-

) tstn fin c v 3 r

a ( fot is os n

s e e 2 6

- B

.b 1

n 2

1 3

Lonr D Y e ,5 a 7

S Er u -

o R oc 2 a n u ) Lft 2 n 1 k r i i 5 9 e .

c FcDo 6 8 e e iean t 7 i

l. m.at e- 10

m.

.?' l

REFUELINC INFORMATION REQUEST

' 1.-

Name of facility fConnecticut Yankee Atomic Power Company 1 2. -- . Scheduled'date for next refueling shutdown..

LJuly 17;.1987 (last day'at' full power)

' 3.1 ' Scheduled t date for restart following refueling.

October 23, 1987.(first day at full power) 4.- l(a) Will refueling orfresumption of operation thereafter require a technical speci-

'fication change or other license amendment?

-YES-(b) If~ answer is_yes, what, in-general, will these be?-

The following specifications 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 and core configuration been reviewed-by your Plant Safety Review Committee to determine whether any unreviewed safety

, questions are1 associated 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 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

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

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

  • EAST HAMPTON, CONN.06424 February 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 87-01, covering operations for the period January 1, 1987 to January 31, 1987, is hereby forwarded.

Very truly yours,

'/

7/ s Donald B. Miller, Jr.

Station Superintendent DBM/mdw Enclosures cc: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission 631 Pa'rk Avenue King of Prussia, PA 19406

///

f 629

i CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT 1

MONTMLY OPERATING REPORT NO. 87-01 FOR THE MONTH OF JANUARY 1997 c _ __ . _ _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _

PLANT OPERATIONS The following is a summary of plant operations for January 1987.

On January'14 at 0621 hours0.00719 days <br />0.173 hours <br />0.00103 weeks <br />2.362905e-4 months <br />, we reached the 77 billion kilowatt hour accumulated generation mark.

A routine turbine valve' test was conducted at 65% power on January 18 at 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />. The test was completed at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />. At 0642, the plant reached 100% power.

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

i.

I 4~

n e vg = .

E

]!!E 8

kEn

!i!"

l N E 3

'05 ll l

R l .

Il, j.

d s it mg 8 54 0 yyRE e 3 .8 t' N - ,!

,,,g, y SYSTEM MAIhTENANCE JANUARY 1987 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVEhT FOR REACTOR SAF,ETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPATR Thero are no ,

r; portable ite=s i fer the month of January 1987.

l T

l