ML19332A735

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Monthly Operating Rept for Aug 1980
ML19332A735
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 09/10/1980
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19332A732 List:
References
NUDOCS 8009180180
Download: ML19332A735 (9)
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' CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT l

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MONTHLY OPERATING REPORT NO. 80-8 i-FOR THE MONTH OF AUGUST, 1980 i

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r PLANT OPERATION 3 i

The following<is a chronological description of plant-operations for the month of August, 1980.

1 At the beginning of this report period the plant.

~8/1/80 was operating on three-loops at 65% full power (365 MWe).

8/2/80 Turbine Trip-Reactor Trip @ 0200 hrs.

First out on turbine was loss of auto stop oil-mechanical overspeed initiated trip.

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8/2/80 Commenced critical approach at 0415 hrs. and attained critically at 0455 hrs. Rolled turbine i

and phased unit to the line @ 2030 after several I

rolls and turbine trips to set overspeed mechanical trip.

8/3/80 Load @ 25% full power (150 MWe) and holding for stm./ gen, Chem. @ 0150 hrs.

8/3/80 At 0252 hrs. started "B" stm. gen. feed pump

.and shutdown "A" pump due to' failed outboard seal.

8/4/80 Commenced' load increase at 0305 hrs. and reached 65% full power (full load for three loops) @ 0530 hrs.

8/4/80 "B" Aux. stm./ gen. feed pp out of service 2008

. hrs, to 2225 hrs. for repair of drain line leak.

8/5/80 Started #2 RCP and commenced heatup of #2 loop at 0616 hrs.

8/5/80 Commenced load reduction to take unit off line to place #2' loop inservice. Unit off line @ 2209 hrs.

  1. 2 RCP shutdown @2302, reactor shutdown @ 2400 hrs.

8/6/80 Unisolated loop 2 at 0015 hrs. and started #2 RCP

@ 0138 hrs.

Commenced critical approach @ 0210 and reactor was critical @ 0300 hrs.

Stm. was taken out

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of secondary. plant for work.

H.P. turbine gland sta supply line leak @ 0310.

.8/6/80 iCommenced warming stm. line @ 0925 hrs. and phased unit to line 0 1259 hrs.

Increased load to 150 MWe and holding for Chem.'@ 1635 hrs.

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PLANT OPERATIONS (Cont'.) -

8/7/80 Commenced load increase @ 0410 hrs. and attained 65%: fu11 power at '0640--continuing load increase

! @ 18 MWe an hour--reached full load (562 MWe)

@'1738 hrs.

8/12/80

  1. 1' containment recirculation fan removed from service for cable replacement @ 1453 hrs.

8/14/80 At-1730 hrs..found #3 turbine control valve to be not operating properly. Reduced load to 550 MWe @ 1757 hrs. to work on #3 turbine E

' control: valve.

8/15/80' closed #3 turbine control valve and opened #4

@ 2045 hrs.

8/16/80

  1. 1 containment recirculation-fan returned to service

@ 0145 hrs. Opened #3 turbine control' valve with test motor stiglitly to maintain full load, 1015 hrs.

8/20/80 Charging flow control valve (FCV-110) failed open and was isolated @ 1905 hrs.

8/21/60 CH-FCV-110 returned to service following solenoid -

replacement.

8/25/80 EG-2A out of service for cooler cleaning @ 0700 hrs.

-8/27/80

  1. 3 containment recirculation fan out of service for maintenance @ 1005 hrs, and returned to service

@ 1320 hrs.

8/27/80 EG-2A tested and returned to service 1950 hrs.

8/28/80 EG-2B out of service for cooler cleaning @ 0655 hrs.

8/29/80 EG-2B tested and returned to service @ 2015 hrs.

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EFFECT SPECIAL PRECAUTIO.NS

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SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDi:

OR MALFUHCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY CAUSE RESULT OPERATION REPETITION DURING PEPA!R COMPONENT l

Rod Pzzition Increase in plant Rods 7 & 8 read None Adjusted span of Rods 7 & 8 None Indic' tion fcr Tavg affected higher than rest to agree with remainder of Rod #7 & #8 span setting of the bank of bank C:nteinmt,t aump Broken drive belt Chart failed to None Feplaced broken belt MCB indicator in service laval recorder drive while repairs in progress to monitor sump level FCV-110 Failed solenoid FCV-110 failed None Replaced failed solenoid Backup valve FCV-110A was open in service Pow:r Range 34 Not enough gain Power level could None Rebalanced A & B detector Load run back jumper out of full power not be set closed currents to allow higher installed in charnel 34 amplifier to trip point output from full power during work. Other 3 channels operating as amplifier called for by Tech. Specs.

F-17-1 Containment Improper Grounded cable 1 of 4. fans Replaced cable None - fan out of service Recire Fan installation out of less than 7 days MA-llc 9 service

  1. 2 Reactor Coolant Faulty Seals Inproper seal None Replaced seals None - pump not run with Pump leakage bad seal 4

r CONNECTICUT YANKEE REACTOR-COOLANT-DATA MONTH: AUGUST 1980 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH 0 25 DEGREES C 5.60Ef00 :

5.98E+00 :

6.65E+00 :

CONDUCTIVITY (UNHOS/CM) 5 05E+00 :

1.20E+01 :

2.30E+01 :

THEORI DES-( PPM )

<4TOOE-02-:-<4TOOE --44TOOE DISSOLVED OXYGEN (PPB)
<5.00E+00 : <5.00E+00 : <5.00E+00 :

BORON (PPM) 1.10E+03 :

1.20E+03 :

1.47E+03 :

-idTHIUM-( PPM) 5 00E-01-1-1 r20E+00--

2r10E+00-TOTAL GAMMA ACT. (UC/ML) 5.89E-01 3.21E+00 5.32E+00 :

10 DINE-131 ACT. (UC/ML) 7.43E-03 :

1.89E-02 :

2.46E-02 :

-I-1-31/I-1-33-R AT-I O

.42E 7r93E 1rOOE400-:

CRUD (MG/ LITER) 1.30E-03 1.14E-02 :

3.00E-02 :

TRITIUM (UC/ML) 1.05E-01 :

1.01E+00 :

1.72E+00 :

4tYDROGEN-(CC/KG0 2710E+01-F--2T83E+01 ;

3v-75E+01-!

AERATED LIQUID WASTE PROCESSED (GALLONS):

1.34E+05

-4d ASrTE-L-I OU I D-P R O C ES S E D -THROUG H-B O R O N -R ECOV ER Yf 0 A LLON SH 1.54E404 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE)*

2.36E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00

AVERAGE DAILY UNIT' POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE 9/10/80 COMPLETED BY Reactor Engineering -

TELEPHONE (203) 267-2556 MONTH:

August 1980 DAY AVERAGE DAILY POUER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 553 1

342 17 2

31 18 552 3

129 19 555 4

298 20 556 5

292 21 558 6

49 22 560 7

390 23 558 8

537 24 558 9

541 25 556 10 542 26 555 11 543 27 552 12 546 28 550 13 548 29 5,51 14 546 30 551 15 535 31 548 t

16 549 INSTRUCTIONS On this format, list the average' daily unit power leyc1 in MWe-Net for cach day in the reporting month.

Complete the nearest whole megawatt.

(9/77)

o DOCKET N3. 50-213' UNIT S!!Ull;0WNS AND POWER REDUCTIONS UNIT NAME Connecticut Yankee DATE 9 /10/80 COMPLETED ItY Rn'arne v ~tanaring n

HEPORT AIONTil August 1980 1ELLPil0NE (20D 267 ?ss6 v.

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& g) 80-4 800802 F.

18.5 G

3 Reactor & Turbine trip due to F

turbine bverspeed.

Overspeed* trip g

setting improperly adjusted.

b 80-5 800805 S

14.8 F

1 Shut'down i,n order to tie in Loop 2 after RCP #2 repair.

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4' l' l~.need Iteamn:

h*ethod:

lialnhis G. Instinstions 5 5.lieduled A l:.piipinent I.ninic ll.aplain) 1 Mannal for Pieparainin il Data ll Maintenance.n Test J. Manual Seram.

I:nii) Slice:S 1.n I nesisce

(' ltelneling 1 Antomatic Scram.

1 sens l<ep.nt li.I lu life (Nil:tt.';.

1) Ite;;nlat.ny itesteistion 8 Othe llinplain)

Ulbli I opes.ii.n li.nnmg.*< licenw l xaminallon I binnmsti.iti.c i

G Upesaininal I isos ll:nplat.i)

I sinIn: I. Sanis.%.no.c.

l'8/ FI) tillihes il splaml

o:***NRC UPERATitG STATUS REPORT COMPLETED BY REACTOR EtGINEERl!G>xm 1.

(filT ftAoE.... Cut 4. YANKEE ATOMIC VnlER CO.

DOCKET fiO.

50-213 Q

2.

REPutTitG l'ERIOD.... August 1980 DATE 9/10/80 3.

LICEt45ED TIEfttAL ICER04dT)...1825 C01PLETED BYReactor Engineering h

4.

t!/.tPLATE RATl!G(UtuSS ILE)... 600.3 TELEPIONE (203) 267-2556 5.

DESI ci ELECTRICAL ltATitG(t4ET ME)... 580 C

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iMins t UEPENDALLE CAPACITY (GROSS 14E)... 577 7.

IMIMJ:1 DEPEr43ABLE CAPACITY (NET ltE)... 550 6.

IF Cll/ skies OCCUR lia CAPACITY RATitGS(ITEMS 3 Ti!ROUGli 7)SINCE LAST REPORT, GIVE REAS0tlS....N/A h

9.

M;ER LEVEL TO LAllCH RESTRICTED.

I F #1Y (flET ltE )....None

10. REASul FOR RESTRICTlot4.

IF ANY....N/A C

CCC THIS REPORTitlG PERIOD YR. TD DATE CO ULATIVE TO DATE W}

11.

FOURS It4 REPORTitG PERIOD 744.0 5855.0 111047.0

  • 12.

NO13ER OF IOURS TIE REACTOR tlAS CRITICAL 737.5 3858.8 95055.6

  • 13.

REACTOR RESERVE SHUTIxA#1 H00tS 15.6 27.0 1179.6 *

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14 IOURS LENERATOR Ori LINE 710.7 3767.6 90707.8

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VillT RESERVE SIUTUULN 10URS 0.0 0.0 369.9 16.

UUSS THEHMAL Et:ERGY GENERATED (t441) 1185534.

6382816 156523965.

17.

GROSS ELECTRICAL Et4ERGY GENERATED 04M) 371992.

' 2096613.

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51451079.

18.

i4ET ELECTRICAL ENERGY GENERATED (nA1) 352974.

1987720.

48942483.

19.

ullT SERVICE FACTUR 95.5 64.3 14.7

  • 20 ullT AVAILABILITY FACTOR 95.5 64.3 82.3
  • 41.

tritT CAPACITY FACTOR (USifG t1DC NET) 86.3 61.7 81.5

  • 22.

ullT CAPACITY FACTOR (USING DER NET) 81.8 58.5 75.2

  • 23.

ullT F0rtCED OUTAGE RATE 2.5 0.8 7.0

  • 24.

SHUTD0ti4S SOEDULED OVER FIEXT 6 tD4THS(TYPE,0 ATE N4D DURATION OF EAO{).... Turbine balance and maintenance. Sept. 26. 1980, approx. 3 days v

45.

IF SIUTDGil AT END OF REPORTitG PERIOD, ESTIMATED DATE OF STNITUP....N/A 26.

ullTS !!4 TEST STATUS (PRIOR TD COMERCIAL OPERATI0ti)....N0T APPLICABLE

  • alNCE DATE OF Cot 41ERCI AL OPERATION 1-1-63 V

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REFUELING INFORMATION REQUEST

  • 1.'

Nam ef facility Connecticut Yankee Atomic Power Company 2.

. Scheduled date for next refueling shutdown.

September / October 1981 3.

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

4.

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

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No technical specification changes are anticipated at this time.

(b)

If answer is yes, what, in ger.:ral, will these be?

N/A (c)

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Saf ety Review Committee to determine whether any unreviewed safety questions are associated with.the core reload (Ref. 10 CFR Section 50.59)?

When the above stated documents are received from the fuel vendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety q'uestions are associated with the Core reload.

(d)

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

N/A -

S.

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,

uethods, 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) 389-8.

The present licensed spent feel pool storage capacity and the size of any increase-in licensed storage 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 prc'sent licensed capacity.

1994 to 1995 e

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