ML19256E978

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Monthly Operating Rept for Oct 1979
ML19256E978
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 11/09/1979
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19256E977 List:
References
NUDOCS 7911160308
Download: ML19256E978 (8)
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{{#Wiki_filter:. CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT i MONTHLY OPERATING REPORT No. 79-10 FOR THE MONTH OF OCTOBER, 1979 g40458

    • 3,0~3 1341 002 79 t

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PLANT OPERATIONS The following is a chronological description of plant operations for the month of October, 1979. At the beginning of this report period the plant was in cold shut down for inspection of the feed line nozzles at 'the steam generators and inspections to satisfy other bulletins. During this outage the seal for the #2 RCP was repaired. Also many inservice procedures for valves were completed, and repairs were made to pressurizer code safety valve #584. The manway and hand hole gaskets of #4 steam generator were replaced. The reactor coolant system was hydrotested on 10/7/79 and heatup was commenced. The reactor was critical at 1728 on 10/8/79 and generator was phased to the grid at 2136 on 10/8/79 and loaded to 150 MWe for a chemistry hold. A load increase was commenced at 1430 on 10/9/79 and 100% power was reached at 0330 on 10/10/79. The plant remained at 100% power for the remainder of this reporting period. The auxiliary boilers were placed in wet lay up on 10/17/79. On 10/20/79 it was determined that there was a slight leak through the pressurizer code safety valve #584. All periodic tests were performed as scheduled. 7 8 fl 7_b h 1 c.s ,m 1341 003

EFFECT SPECIAL PRECAUTIONS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR M.S.P.I.C.V.-1206B Wear on seat Leakage None 2ebuilt by Atlantic Valve None required - plant "B" Aux. Feed and plug shutdown Control Valve MA 0644 No. 2 RCP Seal Unknown Leakage None Replace #1 seal runner and None required - plant }UL 0646 "O" rings shutdown

  1. 2 Feed Reg. Valve Bad gasket Leakage None Replaced bottom gaskets None required - plant IDL 0659 shutdown EG-2B cooler Tube leaks Leaka'ge into None Plugged two (2) tubes EG2A available MA 0676 comp. cool.

water Cont. recire, fan Bearings worn - liigh vibration None Replaced two (2) pillow Three (3) other fans F-17-1 age block bearings available MA 0687 EG-2A Cooler Tube leaks Leakage into None Cleaned, plugged three (3) EG2B available MA 0693 comp. cool, tubes dye checked tube water sheet Pressurizer Spray Broken feedback Valve would not None Repaired feedback linkage None required - plant Valve - 574 linkage modulate shutdown Incore flux thimbles Buildup of Unusuable, None Cleaned all fission None required - plant lubricant fission chamber chamber paths shutdown psth

  1. 2 S.G. Level Faulty input Channel None -

Replaced transmitter Mone required - plant shutdown Transmitter capacitor drifting and plant spiking shutdown s k /d E# _n> egg s. C2 ct, b c: bp an CD i

.e CONNECTICUT YANKEE -UNIT 1-REACTOR COOLANT DATA MONTH: OCT 1979 t -REACTOR - COOL ANT - ANALYSIS MINIMUM ^VERAGE MAXIMUM-PH O 25 DEGREES C 4.48E+00 : 5.46E+00 : 6.54E+00 : ---CONDUCTIVITY --( UMHOS/CM )

3. 90 E+00- * - 8.19 E+ 0 0-;-1-.-95 E+ 01--:-

CHLORIDES (PPM)

<4.00E-02 : <4.00E-02 : <4.00E-02 :

r DISSOLVED OXYGEN (PPB)

<5.00E+00 : <5.00E+00 : <5.00E+00 :

-DORON -( PPM ) - 4. 92 E+ 02- -:--1.-2 S E+ 03 - : 1,83E+03-: LITHIUM (PPM) 6.00E-01 : 1.13E+00 : 1.85E+00 : TOTAL GAMMA ACT. (UC/ML) 4.47E-01 : 5.02E+00 8.85E+00 : -IODINE-131--ACT.- ( UC/MLJ 1-8 3 E - 0 3 ! 3.-14 E -0 2-:--- 4-. 86 E-02 -: I-131/I-133 RATIO 6.20E-01 : 7.78E-01 : 9.83E-01 : CRUD (MG/ LITER) 4.00E-02 : 1.45E-01 : 2,50E-01 : -TRI-TIUM -( UC/ML-) -- --

-4. 80E-01 --:-1.-04E+00
----1 84E+00 : -

HYDROGEN (CC/NG) 4.50E+00 : 1.88E+01 3.15E+01 : AERATED LIOUID WASTE-PROCESSED (GALLONS) 4-8.-64E+04 - WASTE LIOUID PROCESSED THROUGH DORON RECOVERY (GALLONS): 6.02E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 9.55E-02 PRIM ARY-- TO -SECOND AR-Y-LE AK-R ATE-( G ALLONS-PER--MINUTE 4-:-----O. 00E-00 e m. - we N 1,74_1 0_0_5 e e 646 the

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.e ene eer nem em o one eh e m meme. eme,.e.ema e ee-any m i emme e e .m. e. . ems.

4 CONNECTICUT YANKEE UNIT 41 -- REACTOR COOLANT DATA MONTH: OCT 1979 -REACTOR-COOL ANT-ANALYSIS MINIMUM AVERAGE MAXIMUM-- PH G 25 DEGREES C 4.40E+00 : 5.46E+00 : 6.54E+00 i .--CONDUCTIVITY -( UMHOS/CM ) 3.-9 0 E + 0 0 * - 0.19E+00'-: 95E+01. :- CHLORIDES (PPM)

<4.00E-02 : <4.00E-02 : <4.00E-02 :

DISSOLVED OXYGEN (PPD)

<5.00E+00 : <5.00E+00 : <5.00E+00

-BORON -(PPM ) - A. 92E+ 0 2 - ---1.-2 G E+ 0 3 - :---1.-8 3 E + 0 3-LITHIUM (PPM) 6.00E-01 : 1.13E+00 : 1.05E+00 : TOTAL GAMMA ACT. (UC/ML) 4.47E-01 : 5.02E+00 : 8.85E+00 : --IODINE-131 - ACT.-- ( UC/liLJ 1-.83E-03 : 3.14E :--- 4-. 06E-02 :- I-131/I-133 RATIO 6.20E-01 7.78E-01 : 9.83E-01 : CRUD (MG/ LITER) 4.00E-02 : 1.45E-01 : 2.50E-01 ---TRI-TIUM--( UC/ML ) --

-4. 80E-01 -:-1-,04E+00 -:

1. 04 E+00 :-

HYDROGEN (CC/KG) 4.50E+00 : 1.88E+01 ! 3.15E+01 : AERATED -LIGUID WASTE-PROCESSED (GALLONS.) *-_8.44E+04 --- WASTE LIQUID PROCESSED THROUGH DORON RECOVERY (GALLONS): 6.02E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 9.55E-02 PR I M A RY-- TO --SECO N D AR-Y-L-E AK-R ATE < G ALLO NS-PER--M I NUTE-)-: ---0. 00E-00 1341 006

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          • !1RC OPERATING STATUS REPORT CCMPLETED SY REACTOR DiGiliEERING*****

( 1. Ut;IT i;ArtE.... Cut #1, YAtJKEE ATot4tC PGIER Q). @ CKET to. 50-213

1; _.

-.j 2. REPORTil:G PERIOD.... october.1979 DATC November 9.1979 3._. LICEt;SEJ TitEiW.L PGJER(ItJT)...1325 CDitPLETED BY Reactor Engineering 4 f.mEPLATE HATir4G(GIUSS ti1E)....t,00.3 TELER07:E (203) 267-2556 5. LESIGri ELECTRICAL RATitJG(! ET tt E)... 575 6._. t'AXI!-turt OEPElic/4LE CAPACITY (GHOSS file)... 577 - 7. IMXilial DEFDiUABLE CAPACITY (tJET !!!E)... 550 h. IF CitAtCES OCCUR IfJ CAPACITY HATitiCS(ITEi4S 3 TilROUGli 7)SilJCE LAST REPORT, GIVE REAS0tlS....Not Applicable .._....__J 9. fu.ER LEVEL 10 utlO! RESTRICTED. IF AtlYttJET 11WE)....None

10. DEA 50tJ Fut HESTRICTIOrd.

IF A!4Y....Not Applicable L -Tills REPORTifG PERIOD YR. TO DATE CulULATIVE TO DATE -"- -- 11. Holm lli REPORTitG PERIOD 745.0 729G.0 103728.0 * - - t 12. IAJrluER OF 10Vd5 Tile REACTOR llAS CRITICAL 559.5 6077.2 89732.7

  • 13.

REACTOR RESERVE StiUTDoutl IDUlts 185.5 75b.5 1152.6 e 14.--- LOWS GEtoERATOR Ort LiliE 555.4 59G3.6 -- 85476.2 *- 15. UtilT RESERVE SilUTDouti IDURS 189.G 233.5 3G9.9 ... _.. _.... J 16. GOSS THER4AL E!JERGY GE!1ERATED OFH) 983G72. 10535116. 147474199. 17. GiOSS ELECTRICAL EtiERGY GE!!ERATED GIAl) 32G080 3435727. 48468141. - - -3 18. f.ET ELECTRICAL EtJERGY GDIERATED 0831) 310169. 32G9285. 4G107709. 19. UtilT SERVICE FACTUR 74.6 81.7 82.4 a 20.__. Utit T AVAI LABI LITY FACTOR.. - - 100.0 84.9 - 82.8

  • t 21.

UralT CAPACITY FACTOR (USING 11DC liET) 75.7 81.5 82.3

  • i 22.

UtilT CAPACITY FACTOR (USilG DER fiET) 72.4 77.9 76.4

  • 23.

UtilT FORCED OUTAGE RATE

0. 0 ------ - -

-0.5- - 7. 4 * - 1 24. SHUTUUWits SCllEDUALED OVER HEXT S flutiTHS(TYPE,DATE AIO DURATI0l' 0F EAOI).... Refueling, May 1980, approximate duration 8-12 weeks l 25. IF SHUTDLAdre AT Ett0 OF ltEFORTl!!G PDtl00, ESTir4ATED DATE OF STARTUP....Not Applicable O c---) 26. UtilTS Iti TEST STATUS (Pal 0R T0 0)lt;ERCIAL OPERAT10ft)....fDT APPLICABLE N I - - ~ ~ - - - - - - - - '

  • SitiCE DATE OF C0rit<RCIAL OPERAT10t1 1-1-68

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AVERACE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE Nov. 9, 1979 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH: October, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 17 581 18 581 2 582 3 19 20 581 4 581 5 21 6 22 579 7 23 579 8 24 580 9 225 25 579 10 575 26 580 11 581 27 582 12 580 28 582 13 582 29 583 14 532 30 583 15 582 31 583 16 581 I!4STRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt. (9/77)

DOCKETNO. 50-213 UNITSI:Ull:0WNS AND POWER REDUCTIONS Conn. Yankee UNIT NA.'.f E DATE Nov. 9, 1979 CO.4fPLETED isy R,,eactor Encineering ItEPORT AIONTil October, 1979 1El.I.I'llONE (203)._ 267-2556 c .f. 3 h ICelisce h*t, 'u ('ause & (*estectlitt N.e. Date i 3$ 2 5 cE livens F? 9E Atison in

e. 5 F Repsial 8r

$' O D Pacvessi Itcsusicist;c H $3 g2 [. o 2 v d Scheduled shutdown in compliance 10 79-10-01 with NRC Bulletins 79-02, 79-13, to S 189.6 D 1 79-10-08 79-14, 79-17. Started 79-09-29 at:.d carried on into October 1979. s ~ t l l i .1 4 I' l n.cd Reauvi: h*cil;ial: Estuhit G. insisussions 5 S.I.cJnicil A D uipinent Failuieliarlain) 141anual fin Prepaeaisi.n nl Data l (fa ll4taintenance.n lesl .!41 ann.it Scrain. l.nis) Slaccl> le.s. nsemcc .y:: (*.iteluelnig 1 Antoniatie Si, tant. l sent Itepin e II.I It I I ale INilRI.G.

1) llegni.ai.9) Hesisistion

. l Otlicillimplaisil ultill I i1 pes.iin: I's.unnig A iiccuse l maininalien g I %.Insisihi J i lV.* t g G tIpcsational I inis 11 spl.iiii) eq ' gr i slutus ! h sne S.un.ss llill Il titlics 'l splaini Q e s j' 3, s I iI

9 REFUELINC INFORMATION REOUEST 1. Name of facility Connecticut Yankee Atomic Power Company a 2. Scheduled date for next refueling shutdown. Fby, 1980 i 3. Scheduled date for restar following rafueling. Approximately eight to 12 weeks from shutdown date, i 4. (a) Will refueling or resumption of operation thareafter require a e 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 CFR Section 50.59)? When the above stated document are received from the fuel vendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety questions are associated with (d) If no such review has taken place, when is it scheduled? the core reload. 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 methods, significant changes in fuel des!.gn, 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) 340 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 assemblies. 1168 9. The pro'jected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1994 to 1995 1341 010

REFUELINC INFORE\\ TION REQUEST 1. Name cf facility Connecticut Yankee Atomic Power Company 2. Scheduled date for next refueling shutdown. May, 1980 3. Scheduled date for restart following refueling. Approximately eight to 12 weeks from shutdown date. 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 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 CFR Section 50.59)? When the above stated document are received from the fuel vendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety questions are associated with (d) If no such review has taken place, when is it scheduled? the core reload. 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 methods, 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 storsge pool. (a) 157 (b. 340 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 assemblies. 1168 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 1341 011 = me}}

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