Text

Monthly Operating Rept for Dec 1981
	ML20054B705
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/12/1982
From:	Donna Anderson; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20054B704	List: ML20054B703; ML20054B705;
References
	NUDOCS 8204190107
	Download: ML20054B705 (10)
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CO:l:lECTICUT YANFEE ATOMIC POWER COMPANY HADDAM IIECK PLANT HADDAM, CONNECTICUT o

4 MONTHLY OPERATING REPORT I10. 81-12 FOR THE MONTH OF DECEMBER 1981 8204190107 820112 PDR ADOCK 05000 R

PLAlff OPERATIOIIS:

The following is a summary of operations for the month of December 1981:

The plant operated at full power until December 10, when a load reduction van commenced to plug leaking waterbox tubes.

On December 11, at 17h8 hours the unit emme off line for a scheduled outage to replace the turbine governor oil impeller. The plant was phased on line at 1220 on December 15, and reached full power at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months the next day.

On December 22 at 0302 hours0.0035 days 0.0839 hours 4.993386e-4 weeks 1.14911e-4 months , the plant tripped from reactor coolant system high pressure mismatch between the primary and secondary systems.

The mismatch was due to a failure of a control air line fitting on the heater drains tank high level dump valve, c-After repairing the fitting the unit was phased on line on December 22 at 1503 hours0.0174 days 0.418 hours 0.00249 weeks 5.718915e-4 months .

At 1705 hours0.0197 days 0.474 hours 0.00282 weeks 6.487525e-4 months a leak was discovered on reheater steam supply valve MS-MOV-36.

A load reduction was commenced and the unit was taken off line at 1831 to repatch the valve. The plant was phased on line at 2350 on December 22.

The unit reached full power on December 23 at 1122 hours0.013 days 0.312 hours 0.00186 weeks 4.26921e-4 months and remained there for the rest of the month.

l

Dece-ber 1981 G[h CORRECTIVE ACTION kAKEh h0 b bVkbb SYSTC{

I' 0 '

2 OR MALFUNCTIO3 SAFE TAKEN TO PREVENT FOR REACTOR SA:iETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR "A" Auxil ary

'hter accu-lation Increrative air

' ion e Replaced Pegulator Proved "B" Auxiliary Feel Piano in rerulator.

regulator to Feed Pump operable Oxidizine air stem control prior to removing "A" reculator sprine.

valve.

from service.

.e e

e O

e s

sm.

Ma2ntenance SYSTEM O!!

CORRECTIVE ACTION TAKEli TO PROVICE OR MALFUNCTION S/JE TAKEN TO F.GVENT F02 RE!.0 TOR SAFETY COMPOSENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Ecric acid system Section of heat Hone None Replaced defective N/A heat trace circuit.

trace inoperable Normal circuit portion of heat trace.

6 (reserve).

vorking.

O l

t 0

?

O e

M

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9 Page 2 of 2 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-213 UNIT NAME Conn. Yankee DATE l-14-01 COMPLETED BY D. Anderson REPORT MONTil December 1981 TELEPHONE (203)267-255o,

no Y ud U

en N

00 E

oME Licensee

@o Cause & Corrective No.

Date E.

NE E

.S U #

Event U$

S.3 Action to N

$5 U.S$

Report #

NO Prevent Recurrence u

o Emg Heater drains tank high level dump valve failure due to failed fitting on control air system.

81-19 12-23-81 F

5.3 A

1

.U/A ZZ ZZZZZZ Turbine generator off line to repair steam leak on MOV 36.

l I

s l

i 1

2 3

4 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(E. plain (NUREG-0161)

E-Operator Training & License Examination I

F-Administrative 5

l' C-Operational. Error (Explain Exhibit 1 Same Source

o Pace 1 of 2 UNIT SilUTDOWNS /ED POWER REDUCTIONS DOCKET NO.

50-213 UNIT NAME Conn. Yankee DATE l-1h-01 C0>1PLETED BY D. Anderson December 1981 TELEP110NE (203)267-2556 REPORT MONTll l

MO 44 u

u d^

N o te U r.

30 8,

m35 Licensee 04 E *o Cause & Corrective No.

Date E

NS j$ "

Event M$

l'8 Action to N

$E5 I

E U.S S Report #

$?O Prevent Recurrence j

xmg o

u I

81-16 12-11-31 S

82.1 A

h N/A ZZ ZZZZZZ Reduced power to I

to plug "B" vaterbox 12-15-81 condenser tubes.

While reducing power for scheduled turbine.

I maintenance, erratic operation of Turbine ;

Control Valves caused turbine overspeed trip.

81-17 12-15-81 s

1.6 B

1 N/A ZZ ZZZZZZ Turbine off line to check overspeed trip 1 set point.

l I

51-18 12-22-81 F

12.0 A

3 N/A ZZ ZZZZZZ Rx and turbine trip l l

l from high pressure.

~

j (Con't) 1 2

3 4

F Forced Reason:

Method:

Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain)

Il-Other(Explain) 1-Manual for Preparation of Da:a 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 (NUREC-0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain Exhibit 1 Same Source

AVERAGE DAILY UNIT POWER LEVEL DOCKET No.

50-213 Conn. Yankee UNIT Haddam Neck DATE l-12-81 C051PLETED BY D. Anderson TELEPHONE (203) 267-2556

>!ONTH:

December 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEtt LEVEL

' ~

(BMe-Ne t)

(bee-Net) l 576 17 581 e

2 578 18 581 19 583 3

577 4

574 20 581 5

577 21 580 6

578 22 78 7

577 23 446 8

577 24 580 0

577 25 582 10 544 26 582 l

11 112 27 581 582 12 0

28 581 i

13 0

29 580 14 0

30 579 89 31 f

15 428 l

16 INSTRUCTIONS 1

[

Oa this format, li it the avera;;c daily unit power icvel in FNe-Net for each day in the reportir.g uonth.

Complete the nearest whole nej;awatt.

(9/77)

--._- - ~ _..

-. - ~

COi4NEC l ICU1 inNNEE REAC~ LOR Cf KiL 6NT DAT A

' ~~~

MUDiH; DttLhBEk 1YU.I' ~ ~ ~~

~ ~ ~ ~ ~ ~~~~ ~ ~ ~ ~ ~ ~

'~~~~~~~ ~ ~ ~ ~'-

- ~ ~ ~ ~ '

~

REAC10P COUL AllT ANALYSIS MINIliUri AVERAGE tiAXTMUM (PTF ?G~~IiEGREEGT-~~

~~~-~ ! '- T.30E ! 0 0 ~ ! ' ~5. 51 E4 00 ~ ~I ~5. 75El 00-' ~!

CONuucrIU11Y ( UMilOS/CM )

1.09FiO1 :

1.71E401 :

2.J5EiO1 :

CHLORIDES (PPhi)

?5.00E-02 3.OUE-02 ;

3.00E-02 :

lil SSUL VED OXYbEN (PPU)

3.oOE400 : /S. oOE+0v ':7'STOUETOD~f

, BORON (PPM) 1.04E+03 :

1.14E403 1.43E403 :

, LITH 1UM (PPil) 1.00EiOO :

1.4vE400 :

2.00E+00

idiAL b A rilih ACI. (UL7IIL )

o. 6 A-02 :

t. 36Ef00T ~6. 4SE4 00 :

1 U D I N E -- 131 nCl. (UC/ML) 2.78E-03 :

14.11E-02 :

5.18E-02 :

! -131/1-133 RollO 3.43E-01 8.60F-01 :

1.G4EIOO :

1 LWU U ( h u / L J l f.R )

.1. o u E - 0 2

.1 00E-Of :

1.voE-02 i

IRIflUM (UC/ML) 1.82E400 2.07E400 1 2.36E400

ilYDRUGEM (CC/hG) 2.DDE+01 :

3.09E+01 6.06E101 :

1 AERATED L10U1D UASTE PROCESSEU(GALLONS):

6 79E104 0.OOE-01 WAS fE l.10 U 11 PRUCESSED THROUGH BORON RECUVERY(GolLONS):~~f 22L OI e M i m b!-

l'k 1 h Ak i LEAh RAfL7UAlLUNS PER rjlfiUfE):

-~

~

Pk1NnRY TO SECOi!DARY LFAN kolE(GALLONS l'ER hlllUTE):

0.00EiOO p.=e.--a.-

- - = -

-.._4__-

~

s,.

...w__.-

=, - =. -. -

e-_=.-=i=%m.ee--

w=_

,, -._.,.. _ _ _. _,,. ~. _..__

.m_. - -. _.-.

N wii mMe-i.Dw.e-W-

=.---ees.

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.we

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m p

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_.W-.-. * *

..===

N6h-

....a-.,.-6

&+-.we.il-

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.e-i.---.e-.o.-

m4.We-

w-g

.-.,w-e.-

y.m-w

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w-

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,,,-e--_-.

-,,w,w

-w_----__y_-

,.,,,%.-,-q.,y y

REFUELING INFORMATION REQUEST A.

Name of facility Connecticut Yankee Atomic Power Company i

2.

Scheduled date for next refueling shutdown.

February 1983 3.

Scheduled date for restart following refueling Mid March 1983' 4.

(a) Will refuelic.g 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 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 rFR Section 50.59)?

When documents are received from vendor they are reviewed in accordance with 10CFR 50.59 to' determine if unreviewed safety questions are core reload associated.

(d)

If no nuch review har. 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 (h) above.

6.

Important licensing considerations associated with refueling, e.g., new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant chang:s in fuel design, new operating procedures.

None 7.

The number of fuel asse.nblics (a) in the core and (b) in the spent fuel l

storage pool.

j (A) 157 (B) hk1 i

8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed ntorage capacity that has been requesced or is planned, in number of fuel assemblics.

1168 9.

The projected date of the last refueling that can be discharged to the spent fuel pool cssuming the present licensed capacity.

199h to 1995

~. - -. _ _ _.

p O

- - - - NRC OPERATING STATUS REPORT CCr.FLETED BY REACTCR ENCINEERIhG*"e*

._____.__.]

O 7 -

00* ET... 5& :13 0~ ERA': N0 3iATUB 1

j I

CESPTI!:G PE:!)).... December 1981. CUTAGE - 0* -LINE HR....!01.3 + (42.7 = 744.0

+ C W4ECT! CUT IfM EE

1 O 2

[3 tT ILIT r ;cnTA.T............. 201 A'Mo 30:4 Q 31 117-;556 EK52

+ HAD:'M KECK FLMT *... _ _ _ _

i 2

LICEN3E3.Taf P4L c WE2'?Wi!.................

........... ?:3

- - - - ++++++++++******

^

5.

APE:_ ATE :AT:*_;-;:015 *4E:...................'.? t 0.7 = 50C..

i. _ CE3:GM ELECT:'; AL F A~;MC !!:ET ~~1E1..........................!!!

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

7.

mat I*U* LE:E1~ A2_E CG ACITY !05033 PLE).....

j e

y 3.

MA t **J" CED E*0A3'.E Cfr ACITi t*4ET PWE)...................... 555 1__ IF_ C.HA* ICE 1 CCO'JR. A33'S SINCE LAST ?IPORi o GIVE REASCH3....None. _.

10. POWER LEVEL TO WICW FE?TRICTED.

IF At MET r".:E1.........None

..11.__REA374 F00 FISTEIOT 3N.

IF rd Y........................... None MONTH i

_ _ _. ~ _ _..... _ _ _ _ _

~ _. _ _ _. _ _ _ _. _ _.. _..

._YR. TO DATE....

_ _ _ _CU*VLATIVE TO DATE I

12.

HOUP3 IN PEPORTING FERIOD 744.0 8740.0 122736.0

6 13-NL7.3E0 CF H3'JR3 TPE REACTOR WA3 CRITICAL

_.740.5

.. 7576.7 _

105551.5.t 14 REACTGR FE3 EWE 3 HUT 00'W HGUR3 0.0 9.1 1192.5 e

~

r 15.

H3UR3 GENERATCR Oti LtNE 640.7 7332.0 100903.0

l 4

[

di t 4!LRESER'/E 3HUTDC'4*4 H0)R3______

_ _. 0.0__

___ _ 0.0 373.7 1

17.

GD033 THE:"AL ENEFCY GENE:ATED (MdH1 105:543.

13097363.

174647256.

(.

t

...C8033 ELECTPICAL U4ERGY CENERATED (MWH)_.362978._. _ _

_ _ _ _ _ _. _..4270279.. _. _

57373477._ _ -

18.

l J7-NET ELE;TBICAL.ENER3T.CENE:ATED E WH1 344354..

4062844.

54580452.

20.

UNIT SERVICE FACTCR 86.4 84.3 82.1

21.

UNIT AVAILA3tLITY FACTOR 86.4 84.3 82.5

22-UNIT CAPACIII FAC10RJU31NG P3CJiET) 83.4 63.6 80.0 3

.J l

23.

UNIT CAPACITY FACTOR (U3ING LER TET) 79.5 79.7 75.7

24 UNIT FORCED OUTAGE RATE 2.6 1.8 6.5 *

.25 -

UNIT FORCED OUTAGE HOUR 3 17.3

.135.0 _ ___....___ _.._

7058.3.*

t 26.

3 HUT 30'a3 3CHEDULED OVEF NEXT 4 MONTH 3(TYPEeDATE AND DURATION OF EACH)....None 27.

IF CURRENTLT'SHUTCOWNe ESTIMA1ED STARTUp DATE............................ 5/A

~

3INCE DATE OF CC?rE2.CIAL GFEFATICH 1-1-62 C

a

_ ~. _ _

+

ML20054B705

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