Text

Monthly Operating Rept for Mar 1981
	ML20003F761
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/12/1981
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
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ML20003F758	List: ML20003F757; ML20003F761;
References
	NUDOCS 8104230536
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i CONNECTICUT YANKEE ATOMIC PCWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT.

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J MONTHLY OPERATING REPORT NO. 81-3 FOR THE MONTE OF MARCH 1981 j

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PLANT OPERATIONS The following is a chronological description of plant operations, for the month of March 1981:

3/1/81 The plant was operating at 100 percent full power (604 MWe) at the beginning of this report period and remained at full power until load was reduced for condenser leak check on March 9, 1981.

3/3/81 Backwashed C & D condenser waterboxes 3/4/81 Made air charge to containment 1315 to 1420 3/6/81 Passed 54 billion KW mark on gross generation at 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months .

3ackwashed all condenser waterboxes 3/7/81

3 RCP seal water return flow indicator failed low at 0358 hours0.00414 days 0.0994 hours 5.919312e-4 weeks 1.36219e-4 months .

I & C replaced power supply and returned #3 RCP seal water return indication to service at 0653 hours0.00756 days 0.181 hours 0.00108 weeks 2.484665e-4 months .

3/9/81 Commenced load reduction for condenser leak check at 0958 hours0.0111 days 0.266 hours 0.00158 weeks 3.64519e-4 months .

load at 400.% and shut down "3" circulating pump at 1123 hours0.013 days 0.312 hours 0.00186 weeks 4.273015e-4 months .

Received report of fire in Pri=ary Auxiliary Building at 1132 hours0.0131 days 0.314 hours 0.00187 weeks 4.30726e-4 months . Firs in roof above boric acid storage room extinguished with water Restar*.ed "3" circulating pu=p - no leaks in 3 vaterbox at 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months . Shut down "C" circulating pump at 1340 hours0.0155 days 0.372 hours 0.00222 weeks 5.0987e-4 months . Plugged one tube in C waterbox. Restarted "C" circulating pu=p at 1546 hours0.0179 days 0.429 hours 0.00256 weeks 5.88253e-4 months . Shut down "D" circulating pu=p at 1602 hours0.0185 days 0.445 hours 0.00265 weeks 6.09561e-4 months - no leaks.

Restarted "D" circulating pump at 1755 hours0.0203 days 0.488 hours 0.0029 weeks 6.677775e-4 months . Backwashed "A" condenser at 1810 hours0.0209 days 0.503 hours 0.00299 weeks 6.88705e-4 months . Reduced load to 350 MWe for turbine stop and control valve test at 1839 hours0.0213 days 0.511 hours 0.00304 weeks 6.997395e-4 months . Ccmoleted valve test and commenced load increase at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months . Plant was at full load at 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months and remained at full power for the remainder of this report period.

3/19/81 Divers cleaned screenhouse trash racks 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months to 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months .

l 3/23/81 I & C vented reference leg on channel 3 pressurizer level. Level l

indication from 53.8 to 51 percent.

3/25/31 Backwashed A & 3 condensers i

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EFFECT SN!? Al IIUW U'O ON CORRECTIVE ACTION TAKEN TO PI(O'.*lf F.

11ALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPOSENT CAUSE RESULT OPERATION REPETITION DURI::C R pal!!

Pressurizer Pressure Loose cor nector Loss of channel Norm.: Pressur-Connector taped to control-Use of portions of Channel on Pic 401-1 control on PORV.

izer pressure.

ler.

Checked all other SUR 5.2-4.

Pic - 401-1 (controller for Opened PORV 570 decreased connectors for tir,htness.

Redundant indication PORV) and 110V 569 N25-30 PSIG of pressurizer pressure Reason for loose were available.

connector was possibly jarring 4

I of itCB by workmen.

"B" service water Erroded elbow Service water None Replaced elbow None required filter backwash line Reason: age leak elbow Cable vault Main Main CO2 system Automatie initia-None Disassembled and cleared None required Co, system.

bank time delay tion of CO2 systen time delay. Replaced SUR 5.5-20 did not function inoperative.

fan dampner shaft se't Reason: unknown screws. Retested system Fan dampners did not Close.

Reason: Loose shaft set screws.

4 Switch gear Automatic initia-Automatic initia-None Installed 3 Varistor in None required a

llalon system tion of llalon tion of Halon circuit.

SUR 5.5-23 system failed.

system inopera-Retested system Reason:

inte r fer-tive, 4

ence between horn T

circuit and sol-Q enoid initiating circuit.

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CONNECTICUT YANKEE REACTOR COOLANT DATA HONTH. nARCH 1 51 l

REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM

+

o+A/cTvu ;

o.46E+00 ;

6 72E+00 :

rn C 25 DEGREE 5 C CONDUCTIVITY (UMHOS/CM) 8.30E+00 :

1.34E+01 :

1 80E+01 :

CHLORIDES (PPM)

<4.00E-02 : <4.00E-02 : <4.00E-02 :

LISSCLVEL CxiCEN (FIS)

';5.00E!GG ; ~;5.00EiOO ; ;5.00EiOO ;

BORON (PPM) 4.71E+02 :

5.18E+02 :

5.64E+02 :

LITHIUM (PPM) 9.00E-01 1.53E+00 :

2.00E+00 :

Nt--GAMMA ACT. (UCiHL) 1.6tE+00 ;

3.66E+00 ;

5.36E+00 ;

IODINE-131 ACT. (UC/ML) 1.75E-02 :

2.04E-02 :

2.37E-02 :

I-131/I-133 RATIO 6.84E-01 :

7.82E-01 :

8.80E-01 :

CRCL (i'G<

ITER; 0.00E 01 ;

0.00E 01 ;

TRITIUM (UC/ML) 3.07E+00 :

3.43E+00 :

3.82E+00 :

HYDROGEN (CC/KG) 2.04E+01 :

2.22E+01 :

2.63E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):

8.97E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

0.00E-01 AVERAGE F RIMARY LEfitt-RATE-tGAtt2MS-PEfi HINUTE).

2.34E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00 PODR OR GINAL i,-e,-----

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

..e.,--. - - - - -..,,

3y----,--,-v--+-, - -,

.,___,------.r--

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE April 12, 1931 Reactor Engineering C(MPLETED BY TELEPHONE (203) 267-2556 March 1981 MONTH.

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 576 580 t

17 577 580 2

18 577 579 3

gg 579 577 20 4

577 580 5

21 577 580 6

22 578 579 7

23 578 579 8

24 480 580 9

25 578 580 10 26 580 580 g

27 580 12 580 28 581 580 13 29 580 580 14 30 580 579 15 31 580 16 P00R ORIGINAL INSTRUCTIONS On this format, list the average daily unit power icvel in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt.

(9/77)

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.aKR;ELING I'J0lO!A-~"? EEOUG

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Connecticut Yankee Atomic Power Company Scheduled date for next refueling shutdown.

s

.Septei.er/ October 1981 3.

Scheduled date for restart following refueling Approximately six to eight weeks.

2 I

4.

(a) Will refueling or resu=ption of operation thereafter require a technical specification change or other license a=endment?

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 Cc=mittee to determine whether any unreviewed.=afety questions are associated with the core reload

-(Ref. 10 CFR Section 50.59)?

When the above stated docu=ents are received from the fuel vendor they will be rGviewed in accordance with 10CFR50.59 to determine if any unreviewed safety

. questions are associated with the Core reload.

(d)

If no such review has taken place, when is it scheduled?

N/t. '

5.

Scheduled date(s) for submitting proposed licensing action and supporting information.

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

6.

Important licensing consideration 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.

N:ne 7.

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

(c) 157 (b) 38'9 8.

He present licensed spent fuel pool storage capacity and the size of any dncrease in licensed storage capacity that has been requested or is planned.

in number of fuci assc=bli.es.

P00R BRIGINM m.

The projected date of the last refueling that can br. discharged to the spent fuci pool assuming the present licensed capacity.

1994 to 1995

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ML20003F761

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