ML20137B679

Monthly Operating Rept for Jan 1981

ML20137B679
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/31/1981
From:	Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20137B401	List: IA-85-723, Partial Response to FOIA Request for 23 Specified Monthly Operation Repts.Documents 12 & 14 Listed in App a Available at Pdr.Remaining Documents Encl ML20137B395 ML20137B416 ML20137B443 ML20137B468 ML20137B509 ML20137B545 ML20137B561 ML20137B587 ML20137B616 ML20137B626 ML20137B658 ML20137B679
References
FOIA-85-723 CYH-81-003, CYH-81-3, NUDOCS 8511260329
Download: ML20137B679 (10)

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 81-1 FOR THE MONTH OF JANUARY 1981

- 8511260329 851119

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

1/1/81 The plant was at full power (604 MWe) at the beginning < i this report period and remained at full power until 0905 hrs. on 1/2/81.

1/2/81 Commenced power reduction at 0905 hrs. Load at 400 MWe at 1021 hrs.

Shut down 'A' circulating water pump. Isolated and drained 'A' condenser waterbox for tube cleaning.

1/3/81 Returned ' A' circulating pump and waterbox to service at 1037 hrs.

Shut down 'D' circulating pump at 1047 hrs. Restarted 'A' circulat-ing pump and shut down 'B'cire. pump because of leakage indication in

'B' waterbox at 1201 hrs. Drained and isolated 'B' waterbox for cleaning and a leak check.

1/4/81 Reduced load from 400 MWe to 350 MWe and performed Turbine stop and control valve test at 0930 hrs. Completed test and returned load to 400 MWe at 1130 hrs. Plugged two tubes and rolled one tube in 'B' waterbox and started 'B' circulating pump at 1537 hrs. Shut down .

'C' circulating pump and isolated 'C' waterbox for leak check at 1538 hrs. Restarted 'C' circulating pump at 1816 hrs. Shut down

'D' circulating pump at 1830 hrs. for leak check of waterbox.

At 1847 hrs. operator tripped Reactor and Turbine manually. 'A' and

'B'. steam generator feed pumps tripped due to low suction pressure caused by cavitation of condensate pumps. Operator tripped the plant when two stean generator low level alarms were received.

Restarted #3 and #1 RCPs at 1902 hrs. Performed pre-critical checks and commenced critical approach at 2020 hrs. Peactor was critical at 2141 hrs. Backwashed all condenser waterboxes and rolled turbine at 2305 hrs.

1/5/81 Plant was on line at 0022 hrs. Manually tripped Turbine at 0058 hrs.

due to ficoding of 2B feed water heater. Closed six point heater stops and drained feed water heater. Realigned feed water system and rolled turbine at 0237 hrs.

Plant on line at 0250 hrs. Plant was loaded to 150 MWe and holding for S/G Chemistry at 0507 hrs. Commenced load increase at 0935 hrs, and reached full power at 1645 hrs. Plant remained at full power for the remainder of this report period.

1/8/81 Electric fire pump cut of service 1510 to 1630 hrs. for seismic support work on breaker. Halon system out of service several times this month for seismic support work. Fire watches established as nec-essary. At 1515 hrs. received pressurizer relief line flow alarm.

All conditions were normal and cause of alarm determined to be

, electrical interference. Alarm reset at 1936 hrs.

1/13/81 ' A' high pressure safety injection pump out of service at 1017 hrs.

for maintenance. Retested and returned to service at 1335 hrs.

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1/15/81 ' A' rod drive MG set out of service 0916 to 1400 hrs. for brush replacement.  !

1/16/81 'B' rod drive MC set out of service 0807 to 1518 hrs. for maintenance.

1 1/23/81 Received hi-pressure alarm on pressurizer relief tank due to failed light source.

1/29/81 Backwashed all condenser waterboxes.

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. bertUr SPECIAL PKLCAdr;ONS

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SYSTEM ON CORRECTIVE ACTION TAKEN TO PROV102

( OR MALFUNCTION SAFE TAKEN TO PREVENT FOR RCACTOR SATETY I COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR - -

!'Pr23:urizer capillary Crack in weld Leak high None' Welded 16 new piece of None required ey2 tera Reason unknown Airborne' air 1/8 tubing -

MA'1949 Lecko'en #2 feed line Gasket failure Feed water leak None Furmanited body of valve None required icolation valve Reason unknown b:nnst.

Lenk,on hinge pin Covar-trip valve MA.1961

, " " Waste, Gas Com '

Faulty flow switch No alarm protec- None Cleaned flow switch None required prestor (component cool- tion.on "Com-ing) Reason: dirt pressor "A" and sticky sub- trouble" stance found on switch mechanism *

"A" Wmate. Gas Com- Maladjusted oil - No alarm protec- None Adjusted oil level switch Non required prazcar level switch - tion on "Com-Reason unknown pressor "A" trouble" "A',' Waste Gas Com- Faulty relay - No alarm protec- None Replaced relay Non required

pressor Reason: open coil tion on "Com-pressor "A" trouble" l Erse:urizer relief Failed light No alana protec- None Replaced light source None req 61 red trnk pressure source in meter tion

-jindicator alarm unit relay circuit -

[ Reason unknown Circ.' water and gen- Faulty Rosemount Inaccurate temp- None Replaced power supply None required crator resistance power supply - erature readings tamp,erature detection Reason unknown system Steam line break Dirty or worn Loss of indica- None Replaced worn slidewires, None required

! temperature indicatort slidwires - tion only cleaned dirty slidewire

1 ,2,4 Reason

constant movement of I servo mechanism ii j,' I .

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CONNECTICUT YANKEE REACTOR C00 TANT-DATA-MONTH: JANUARY 1981 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXINUM PH @ 25 DEGREES C  : 5.90E+00  : 6.18Et00 : 6.48E+00 :

CONDUCTIVITY (UMHOS/CH)  : 7.90E+00  : 1.27E+01 : 1.94E+01 :

CHt0 RIDES- CPPM) . 44.00E"02 . ;4.00E=02 ; A.00E-02 ;

DISSOLVED OXYGEN (PPB)  : <5.00E+00  : <5.00E+00 : <5.00E+00 :

BORON (PPM)  : 6.53E+02  : 7.17E+02 : 9.09E+02 :

CITHIUM~(PPM)~  ;-6700E-01-:-1 ; 15E t 00 ; 1.-70Ef 00-TOTAL GAMMA ACT. (UC/ML)  : 1.50E+00  : 3.48E+00  : 4.23E+00  :

IODINE-131 ACT. (UC/HL)  : 1.41E-02  : 2.18E-02  : 2.78E-02  :

-Pt3tfPt33-RA f%  ; 7.2SE-01  : 0.06E 01  : ,7.4'E 01  :

CRUD (MG/ LITER) '

0.00E-01  : 0.00E-01  : 0.00E-01  :

TRITIUM (UC/ML)  : 3.27E+00  : 3.54E+00  : 3.00Ef00  :

f-tYDROGEN-CCC/KG)  ; -2720E'foi ; 2T56E+01 ; 3T00E+01 ;

AERATED LIQUID WASTE PROCESSED (GALLONS): 1.23E+05 ITab t. t IGUID~ PROCESSED-~THROUGH-DORON-RECOVERY (GAttONS-Ti--3T53E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 2.09E-01 PRIMARY TO SECONDARY LEAN RATE (GALLONS PER MINUTE): 0.00E+00

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AVERAGE DAILY UNIT POWER LEVEL 9

DOCKET NO. 50-213

, Conn. Yankee UNIT Haddam Neck DATE 2/12/81

. COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH. January 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 577 17 578 2 457 578 18 3 376 577 19 4 290 576 20 5 321 577 21 6 576 578 22 7 579 576 23 8 579 577 24 ,

9 578 577

.25 10 579 577 26 11 579 27 577 12 579 28 577 13 579 29 577 14 579 30 577 15 580 31 576 16 579 INSTRUCTIONS On this format, list the average daily unit power level in MWc-Net for each day in the reporting month. Complete the nearest whole megawatt.

i iTL Conden~Ser -Cleaning

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, (9/77)

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UNITSI Ull:0WNS AND h0WER REDUCTIONS DOCKET NO.

UNIT NA%IE u nn. Tarwe.

u t ering.

,, . HEl' ORT A10NTil Jan. 19'31 COMPLF.

DATE[2/"/01

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,$ ? 3 jE'5 1.scemee E.,, . E* , Cauw & (* nrestive No. DJIe H

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.d jsE  !!ven He;uns at 3,y us O 83 EU Assion su Pscsen Hecurrense s.~.ig;=t U 6 *

• 4 81-1 810102 S 0 N/A N/A zz zzzezz

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11 Reduced load to 65% power in order to clean Main Condensers 81-2 810104 F 5.6 11 1 N/A zz zzzzzz Reactor and t' urb'in'e trip due to low feed pump suction.

• J' 81-3 810105 F 1.9  !! 1 N/A zz zzzzzz Tripped turbine due to flo'oding in

,9 #2B feedwater heater. Reactor i

remained. critical..

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i I *2 1 4 L; , l' l.nced Iteamn: h*elliod: Eslobit G. Insionssiewis 5 5.ficJuic.l A I: inigunent Itaitnic ll.splain) 1. Manual for prepasati..n ..I Data fl MJilllCil3ticC til TC58

• 2 b!Jili4JI NClalls.

• I.I'* ) *ileccin 108 I 8 ten %ce I lielueling 1 Antennalle.krani. 1.e... Hepen s Il.1 H i I ile (Nill *!.C.

D Hcgulatin flesteistiins .

4-(lihes llimplain t 01(.11

, l t fresalna is. sui.ng A Iisenw l mantinalline . -

I binanisisalive  !  %

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• G IIpciational I sine ll'nplain)

' Isl. int! hai.h .%qu.c

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• • • • • LC ODEEATIN', STATUS rep 00T C0 Pct.ETED ET REACTOR EN0!NEERINGm**

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L' HIT NfM....C0ftl. T ANKEE AT0"IC POWER CD. I(GET NO. 50-213 *

-2. ' EEPOLTIMC PED!OD January 1981 DME 2/12/81

2. ?. . LICENiE9 THE*"SL P0kE9(*NT.'. . .1925 CO*LETED Rf Reactor Engineering i t', i mEPLME PST!wGt000iS PYE)... 400.3 '

TELEPPONE (203) 267-2556

,j '5. DE5!?'l ELECT 21CI-L 5**TINMET yug)...,5e9

s. 6. g FA4!PW 0frF$$4ftE CA54 CITY (CR05? MWE)... 577 L7. .MA!!M.9 LEPEND4LE CAPACITINT NE)... 555 . . . . .

8. , IF CPMCES OCC% IN CAPACITf EATINGS (ITEMS 3 THROUCH 7)SINCE LAST REPORT, CIVE REASONS .... NONE .

9. . P9 pro LEVEL 10 uMICH RESTRICTED. IF ANY(NET MWE).... NONE j FEAi0t! FOR PESTRICT10N. IF ANY .... NOT APPLICABLE s; ,10j .,

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• e THIS REPORTING PERIOD

. TR. TO DATE CUMLLATIVE TO DATE *

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• @ $5 IN FEp0; TING PERIOD 744.0 744.0 114720.0 + '

12. ' NUMEER OF HOURS THE REACTOR WAS CRITICAL 741.1 '741.1 99713.7 *

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. ~. 13. , PEACT04 SESE5VE SHUTD049 9)RS 4.6 ,. 4.6  !!69.0 +

• !4 KdSS GEP'EFATOR OH LINE 736.5 736.5 94157.5 +

15.~ UNIT PESERVE SHUTE 04N HOURS 0.0 - 0.0 373.7 m

!!. 0005? THEL *'AL ENERGY GENELATED (MWH) 1294197. 1294197. IUc45590.

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6505S ELECTRICAL ENERGT CENERATED (Miat) 42&B02. 428802. 5 ?5?Wo0.

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18. 'hET ELECTRICAL ENERGf CENERATED (MWH1 40B891. 406891. 50926499.

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!?.' ~ LHIT SEEVICE FACTOR 99.0 99.0 02.2 +

q 20. TWIT P/A! lap!LITY FACTOR 99.0 99.0 92.5 +

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21 _.ONIT CAEACITY FACTOR (USING MC NET) 99.0 99.0 B2.0

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, 22. .. LWIT CAPACITS PACTOR (USING DER NET) 94.0 94.8 75.8

• u 23. UNIT F0FCED OUTA?E FATE 1.0 1.0 e.8 +

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' 2 4. SHUTDOWNS SCHEDULE!) OVER NEXT 6 MONTHS (TTPE,DA1E AND DURATION OF EACH).... NONE

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[25'.~ IF SHUTDOWN AT END OF REPORTING PERIOD EST! MATED DATE AC STARTUP .... N/A I

, i.26.. ... LNITS IN TEST STATUSfPRIOR TO COMMERCIA. OPERATION)....NOT APPLICABLE _

18 I; +SINCE DATE 0F COM=ERCIAL OPERATION 1-1-68 h,

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.i:EFIG;i.I!;G I!!F012!.\Tl0:1 IEOUK!iT-1, pagio of . fpcJ lity Connecticut Yankee Atouic Power Company Scheduled date for next refueling shutdown. .

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' September / October 1981

3. Scheduled date for restart following refueling .

- Approximately six to eight weeks.

4. (a) Will refueling or resumption of operation thereaf ter 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 .cafety 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 100FR50.59 to determine if .'ny unreviewed safety ,

questions are ass'ociated with the Core reload.

(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 consideration associated with refueling, e.g., new or different fuel design er supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

Nonc .

7. The number of fuel assemblics (a) in the core .:nd (b) in the spent fuel ctorage pool. .

(a) 157 '(b) 38'9

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 assemblics.

1168

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,.. The projected date of the la: t refueling that can b.? discharged to the spent _ _ ~

__fuci pool ar.r.uming the present licensed "capac t ty.

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CONNECTICUT YANKEE ATO M IC P O V/ E R COMPANY j '

7 HADDAM NECK PLANT

\;. RR #1 BCX 127E. EAST HAMPTON CONN. 0J424 February 12, 1981 CYH 81-003 Docket No. 50-213 Director, Office.of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTENTION: Mr. Victor Stello

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Monthly Operating Report 81-1, covering operations for the period of January 1, 1981 to January 31, 1981 is hereby forwarded.

Very truly yours,

/[

Richard H. Graves Station Superintendent RHG:RPT/sb Enclosures cc: (1) Director, Region I Division of Inspection & Enforcement U. S. Nu'elear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2) Director, Office of Management

-Information and Program Ccntrol U. S. Nuclear Regulatory Commission Washington, D. C. 20555 O

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