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Monthly Operating Rept for Oct 1981
	ML20042B349
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/08/1981
From:	Donna Anderson; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
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ML20042B346	List: ML20042B345; ML20042B349;
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	NUDOCS 8203250236
	Download: ML20042B349 (10)
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i CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT 1

4 MONTHLY OPERATING REPORT NO. 81-10 FOR THE MONTH OF OCTOBER 1981 f

i 8203250236 811108 PDR ADOCK 05000213 R

PDR

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PLANT OPERATIONS The following is a summary of plant operations for the month of October, 1981:

The unit was shut down the entire month for a refueling and maintenance outage.

Fuel shuffle commenced at 1816 hours0.021 days 0.504 hours 0.003 weeks 6.90988e-4 months on October 9 and was completed at 1310 hours0.0152 days 0.364 hours 0.00217 weeks 4.98455e-4 months on October 15, 1981.

A speci,a1 procedure on Recovery from Station Blackout to Outside Power was successfully completed on October 29, 1981, at 1455.

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EttECT

$PECIAL PRECAUTIOi<

SYSTEM Page 1 of 2 ON CORRECTIVE ACTION TAKEN TO PRCVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFET1 COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPA1R

. Control Rod Drive Damaged coupling Could not engage None Installed new coupling None Required Shaft H6.

drive shaft Drive shaft Reason: Possible was damaged misalignment during when installing refueling.

drive shaft.

Demineralized Cracked welds at Tank leaked None Repaired welds and installed None Required Mater Storage Tank syphon heater adaquate pipe supports, inlet and outlet pipe connections.

Reason: Pipe support unable to adaquately restrain constant hanmering from

. syphon heater.

Loop #1 Main Steam Damaged valve Valves would None Repaired Valves Isolated Loop '

Safety Valves internals.

hold required pressure Reason: Water hammer

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2 Reactor Coolant Oil soaked Insulation None Insulation removed, piping None Required Pump insulation.

started smoking and pump volute cleaned and during Loop new insulation installed.

Reason: Possible heat-up, oil spill during oil charge.

"B" Emergency Leaking heat Service water None Installed new heat None Required Diesel

. exchanger, leakage into exchanger.

diesel coolant t

g system.

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LweECT SPECIAL PRECAUTIO!

SYSTEM Page 2 of 2 ON CORRECTIVE ACTION TAKEN TO PRCVIDE OR HALFUNCTION S/JE TALEN TO PREVENT FOR REACTCR CAFET COMPONENT CAUSE RESULT OPERATION REi3ETITION DURIEG LEPAIk Loop #14 Fill Motor Packing to Valve motor Ilone Adjusted packing and None Required Operator Valve tight.

operator tripped retested satisfactorily

(#508).

out on torque svii,ch.

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l CONNECTICUT YANKEE REACTOR COOLANT DATA MnNTMt nrT 19R1 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH 9 9M DFRRFFA E f

4.06E+00 4.47E+00 :

4.75E+00 :

CONDUCTIVITY (UMHOS/CM) 4.25E+00 :

6'.19E+00 :

7.95E+00 :

CHLORIDES (PPM)

<5.00E-02 : <5.00E-02 :

1.00E-01 :

niceniorn nvvnru rppn3 t

t.

t i

BORON (PPM) 2.04E+03 :

3.11E+03 2.33E+04 :

LITHIUM (PPM)

TnTAI RAMMA APT. (llr/MI i 1.AOE-03 !

5.20E-02 ! '5.41E-01 !

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

4.65E-04 :

2.77E-03 :

I-131/I-133 RATIO PRi f n (Mn/lTTrD)

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TRITIUM (UC/ML) 1.39E-01 :

1.61E-01 :

1.91E-01 :

HYDROGEN (CC/KG)

Not done - refueling AERATED LIQUID WASTE PROCESSED (GALLONS):

4.28E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

2.18E+04 AUFRAGF PRTMARY IFAK RATE (GALLONS PER MINUTE)*

0.00E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00 M

9 a

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE October 8,1981 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556

. MONTH:

October 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEk LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

'18 0

3 0

19 0

4 0

20 0

0 5

'O 21 0

6 0

'22 0

7 0

23 0

8 0

s?4 9

0

~25' 0

26 10 s

0 11 0

27 0

12 28 13 O

29 0

' 14 30 0

0

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15 31 0

0 16 INSTRUCTIONS s

On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatti

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET No.

50-213 UNIT NAMEConn. Yankee A DATE Oct. 8, 1981 COMPLETED BY D. Anderson REPORT MONT11 October 1981 TELEPl!ONE (203)267-255T mo

% wt E

em u

00 E

ode Licensee 6,2 E*o Cause & Corrective No.

Date NS E

.0 N "

Event U$

8. 3 Action to Eml Report #

NO Prevent Recurrence U.S j6 rE U

a g

81-13 811001 to

'S 745.0 C

1 N/A ZZ ZZZZZZ Continuation of Core 1031 10-11, Refueling Shutdown.

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1 2

3 4

Method:

Exhibit C-Instructions F Forced Reason:

S Scheduled A-Equipment Failure (Explain)

H-Other(Explain) 1-Manual for Preparation of Daca B-Haintenance or. Test 2-Manual Scram Eatry Sheets for License C-Refueling 3-Automatic Scrnm.

Event Report (LER) File

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D-Regulatory Restriction 4-Other(Explair (NUREC-0161)

E-Operator Training & License Examination ~

F-Administrative 5

Exhibit 1 Same Source G-Operational.-Error (Explain

n tf un+NRC OFERATING STATUS REFORT COMPLETZ5 3T REACTOR ENGINEEAI'.Gneu

' r-j 1.

DOCVE T....*;0-213 0PERATINC STATUS onunnpen.ennu

-2.-- PEPORTIN3 FEP100...petober 1981 OUTAGE + CN-LINE HR... 745.0 r o.0 =-745.0

- - - - - e (C*NECTICUT TAWT.E * -

7' 3.

UT ILI T T CONT ACT.............. DON ANDERSON ( 203) 267-2556 EX 258 s HADZAM NECK FLAC

- - - - +++

4 LICEN?ED THES.NAL P0kER(MWT)............................... 1825 L.5. -- NsMEPL ATE c.ATING(GcCSS lake)................. 667 1 0.9 = 600.3 6.

DESIGN ELECTRICA*_ cATING(NET MWE)........

.................!E0 7.

MAX IMUM Z EF ENDA3LE C APACI TT (CROSS MWE).................... 532

-9 ;-- MAllMUM DEF ENDA9tE CAPACIT T (NET NWE h ;..... r..... ;...... e.555 1.

IF CHANGES OCCUR ABCE SINCE LAST REP' ORT: GIVE REASONS.... None

-10.- POWER LEVEL TO WHICH RESTPICTED.

!$ ANT (NET fflEl...

.....None- - - - - - - - - - - - - - - - - - -

11. REA30t4 FOR RESTRICTIGN.

IF ANT...........................None

.i MONTH TR. TO DATE CUMULATIVE TO CATE 12.

HOU23 IN REFORT!!;G PERIOD 745.0 7296.0 12!270.0

f I 13.

NUMEER OF HOURS THE REACTOR WAS CRITICAL 0.0 6364.9 104337.6

l 14.-- -- PEACTCR FESERVE SHUTDOWN H)URS -

-0.0------------

9.1 1192.5 e 15.

HOURS GEt,ERATOR ON LINE 0.0 6321.7 97382.7 *

]

6 UNIT RE3ERVE SHTPOWN HOUR 3 0.0 0.0 373.7 L

c 11214337.

172345720.

17- -CROSS THE0 MAL ENERCT GENEPATED (MWH1-

-~---0.

18.

GPOS3 ELECTRICAL ENERGT CENERiTED NWH) 0.

3670415.

56775o13.

I NET ELECTRICAL ENERGT CENERATED (MWH)

-2195.

3476442.

54016050.

l 19.

L20. -- UNIT SERVICE FACTOR

-- - 0.0 - - - - - - -

85.6 92.3

21.

UNIT AVAILABILITY FACTOR 0.0 86.6 82.6

l 22.

UNIT CAPACITT FACTOR (USING MDC tET) 0.0 86.4 82.2

J

'23. - - UNIT CAF ACITT FACTOR (USING DER NET) - - -- - ---- 0.0 ------ -- ---- -

82.7 - -- ?

73.1 e 24 UNIT FORCED OUTAGE RATE 0.0 1.8 6.6 +

, 25.

l' NIT FORCED OUTAIE HOURS 0.0 110.7 7036.0 +

f L26.---SHUTDOWNS SCHEDULED OVER NEIT 6 MONTHS (TTPE,DATE AND DURATION OF EACH).... Continuation of Core 10-11 refueling, started September 26, 1981, 2

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approximately 5 to 7 weeks.

-27.

IF CURRENTLY SHUTDOWN r ESTIMATED STARTUP - DATE............................. November-11 --1981--- -- - -- - - - - - -

-3

SINCE DATE OF COMMERCIAL OPERATION 1-1-68

s

"uNRC OPERATING STATU3 LEFORT C0tTt.ETED BY REACTOR ENGINEERINGun p.-

w____.

r 1.

00CKET... 50-213 0 PEP.AT!NG STATU3

- 2 6-REFORTING FERIOD.... September 1981 OUTAGE + ON-LINE HR....IE6.7 + 593.3 = 720.0

---

C N ECTICUT YP*EE '

+ FEAM NEM FLui

e 3.

UTILITY CONTACT.............. DON ANDERSON (203) 267-2556 Et 53 4

LICENSED THEM AL P0WED.(MWT)................................!?l5 Revision 1.

This revision

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5.-- N4f EF L ATE F AT ING 'CP.033 MWE)................. 667 1 0.9 = 600.3 - -

L 6.

LE31GN ELECTRIC AL FATING (NET NE)......................... 530 corrects the September gross 7.

r.AXIMUM DEFENDA3LE Ce'PACITT(CROSS FWE).................... 532 MWE generating incorrectly entered as 337133 in original'~~~ ~7 pr--MAi! MUM DEFENDA3tE CAPACITY (NET MWEl.;nin.r....;r..rrn. 555

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Septen.ber report.

L.

If CHANGE 3 CCCUR ABOVE, SINCE LAST REPORT, GIVE REASONS...None

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7 10.-POWER LEVEL TO WHICH RESTRICTED. -IF ANY (NET MWE) Tc...... None - --

11. REASON FOR RESTRICTION.

IF ANY...................~.......None I

CUMUL'TIVE 10 DATE

- 5 A

MONTH YR. TO DATE

{

12.

HOURS IN RE?ORTINO PERIOD 720.0 6551.0 120527.0

__y 13.

NUMBER 3F HOUP3 THE REACTOR WAS CRITICAL 608.1 6364.7 104337.6 *

-147-REACT 00 RESE0VE SHUTDOWN HOURS

- 0.0 --

9.1---

1192.5 e 15.

HOUR 3 GENERATOR CN LIFE 593.3 6321.7 99342.7 +

4 16.

UNIT RESERVE STJ1DOWN HOURS 0.0 0.0 373.7 i

?

-!!294397. -- -

172S45780.

-17.---GROS 3 THEPMAL ENE RGY GENEPATED (MWH) -- - -1051704. -

18.

GR033 ELECTRICAL ENERGY CENEPATED (MWH1 337113.

?672415.

56775613.

.______.___q 19.

NET ELECTRICAL ENERGY CENERATED (MWH) 320227.

3500637.

540182t5.

t I

'20. - -- UNIT SERVICE FACTOR

- e2. 4 - --

- - -- ----- -- - 9 6. 5 82.9 e 82.4 96.5 83.1

21.

UNIT AVAILA31LITY FACTOR 22.

UNIT CATACITY FACTOR (USING MDC NET) 80.1 96.3 82.7

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L. - UNIT CAPACITY FACTOR (USING DER NET) - ---76.7 - -------

92.1

---~

7e.5 +

Z3 24 UNIT FORCED OUTAGE RATE 1.7 1.8 6.6

25.

UNIT F0E.CED OUTAGE HOUR 3 10.1 112.7 7026.0 +

SHUTDOWN 3 SCHEDU.ED OVER NEXT 6 MONTHS (TYPE,DATE AND DURATION OF EACHl.... Core 10-11 refueling, Septer bir-October 1981, 5 to 6 weeks.

-26.

3

-27s

-9F-CURRENTLY-SHUTDOWNr ESTIMATE 11 STARTUP DATErn a rr.n n a.;..n.c..... r.a November 3; 1981--------

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3INCE DATE OF COMMERCIAL OPEP8 TION 1-1-68 m

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REFUELING If.TORMATION RE0_UEST

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1.

Name of facility Connecticut Yankee Atomic Power Company

'2.

Scheduled date for next refueling shutdown.

Februar 1983 3.

Scheduled date for restart following refueling.

Mid March 1983

'4.

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

No. technical specification changes are anticipated at this time.

(b'),

If answer is yes, what, in general, will these be?

N/A (c)

If answe'r is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co=mittee to determine whether any unreviewed safety questions are associated with the *

. core reload (Ref.10 CFR Section 50.59)? When documents are received from vendor they are reviewed in accordance with 10CFR 50.59 to determinc if unreviewed safety questions are core reload associated.

(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.

There are no scheduled dates because of (4) above.

6.

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

None 7.

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

(A) 157 (B) 441 The presen. licensed spent fuel pool storage capacity and the size 8.

e of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

1168

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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 I

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ML20042B349

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