ML19256F289
| ML19256F289 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/12/1979 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19256F286 | List: |
| References | |
| NUDOCS 7912180441 | |
| Download: ML19256F289 (8) | |
Text
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CONNECTICUT YANKEE ATOMIC P0k'ER CO>D'ANY IIADDAM NECK PLANT llADDAM, CONNECTICUT MONTilLY OPERATING REPORT NO. 79-11 FOR Tile MONTH OF NOVEMBER, 1979 1608 321 7 912180 f
PIANT OPERATIONS The following is a chronological description.of plant operations for the month of November, 1979.
At the beginning of this report period the plant was at 100% power, 607 FMe.
On 11/11/79 the load was reduced to 400 FMe in order to perform a turbine stop trip valve test.
The plant was returned to 100% power the same day.
On 11/16/79 the load was reduced to 486 FMe for repair of a feedwater regulator valve. The plant was returned to 100% power 36 minutes later.
On 11/17/79 the load was reduced to 471 FMe to prevent overloading an auto transformer at !!ontville. The plant was returned to 100% power three hours later.
On 11/10/79 the circulating water varming line was opened.
Several tie-ins were made to the fire protection system during this period.
All periodic tests were performed as scheduled.
1608 322
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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: NOVEMBER l'779 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH @ 25 DEGREES C 6.10E+00 :
6.57E+00 ;
6.89E+00 :
CONDUCTIVITY (UMHOS/CM) 8.30E+00 :
1.68E+01 :
2.25E+01 :
- <4.00E-02 : <4 00E-02 : <4.00E-02 :
DISSOLVED OXYGEN (PPD)
- <5.00E+00 : <5.00E+00 : <S.00Ef00 :
4.42E+02 :
4.88E+02 :
1.66E+00
" 00E+00 :
TOTAL GAMMA ACT. (UC/ML) 6.36E+00 :
8.03E+00 :
1.02E+01 :
IODINE-131 ACT. (UC/ML) 4.10E-02 4.65E-02 :
5.13E-02 :
I-131/I-133 RATIO 6.70E-01 :
8.41E-01 :
1.02E+00 :
CRUD (MG/ LITER) 8.00E-02 :
1.30E-01 :
1.50E-01 :
TRITIUM (UC/ML) 2.23E+00 :
2.56E+00 :
2.96E+00 :
HYDROGEN (CC/KG) 2.20E+01 :
2.67E+01 :
3.00E+01 :
AERATED LIQUID UASTE PROCESSED (GALLONS)!
1.50E+05 WASTE LIQUID PROCESSED THROUGH DORON RECOVERY (GALLONS):
3.67E+04 4.18 E-02 AVERAGE PRIMARY LEAK RATE (GALLONS PER HINUTE);
PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
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- 1608 324
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- NRC OPERATitG STATUS REP 0ftT CDt?LETED BY REACTOR E' Git:EERINGe****
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-,_ 1 UNIT t;A*tE....CDt4'J. YAtJKEE ATDMIC P3fER (D.
DOCKET ID.
50-213 2.
REPORTil:G PEaIUD.... November, 1979 DATE Deccect 12. 1979 3.
LICEleEd ThE,t!*AL PG!ER(filT)... 1825 CDlPLETED CY Reactor Ertgineering t.*44EPLATE RATl!GCGCSS ;1;E)....GC0.3 TELEPtot;E (203) 267-2556 5.-
LEslG:4 ELECTRICAL RATitiG(: JET lt!E)... 5 75 6.
l'.*XlP.Jt DEPD.0AULE CAPACITY (GR035 ti.;E)... 577 7.
I' Mil'd4 vEPDUACLE CAPACITY (f.ET lt E)...
550 a.- IF GiAthES OCCGI IN CAPACITY etATl!GS(ITEMS 3 THROUGi-7)SINCE LAST REFORT,-GIVE-REASONS..;.None-
- ~~ "
9.
Pu..in LENEL TO Wilot REST tlCTED.
IF ANY(NET tt:E).... None 10.--IIAS33 FOR RESTRICTION.
IF ANY....Not -applicable s
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THIS REPORTiliG PERIOD YR. TO DATE Cu4)LATIVE TD DATE 11.
10Ud5 IN RER)RTit1G PERIOD 720.0 301G.0 104443.0
- 12.
tutBER OF FOGIS TiiE REACTOR WAS CllTICAL
-720.0 6797.2
--- 90452.7
- 13.
REACTOR RESERVE SIUTDalN 100RS 0.0 254.5 1152.6
- l4.
10URS GENERATOR ON LINE 720. 0 GG33.6 8G196.2 *
- 15. -- UhlT.tESERVE SIUTUOLJ:41100tS 0.0 233.5 369.9 15.
GOSS TilD?tAL EtJERGY GENERATED (MJII) 1310339.
11345955.
143735033.
I7.
GOM ELECTRICAL ENERGY GENERATED (tMI)
- 435535, 33712G2.
48303G7G.
18.
f.ET ELECTRICAL ErJERGY GD4ERATED (!4.11) 41G309.
3685594.
--- 4652f.018 19.
UtilT SD1VICE FACTOR 100.0 83.4 82.5
- 20.
UtilT AVAILABILITY FACTOR 100.0 SG.3 82.9
- 21.
UNIT CAPACITY FACTOR (US!!G LUC IJET)
-- - -- 10 5.1 - --
83.G -
82.4
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& 22.
UtilT CAPACITY FACTOR (U$ltG DER NET) 100.G
, 80.0 76.6
- a y 23.
UNIT FORCED OUTAGE RATE 0.0 0.4 7.4
- I 2*.
SIUTDGt:4S SCHEDUALED OVER f4 EXT 6 f 0r4THS(TYPE,DATE A?O DURATION OF EACH).... Refueling,-May-1980. approxiraately 8 to 12 weeks - - -- ---
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IF SHUTDGIN AT E!D CF REPORTl!G PERIOD, ESTIMATED DATE-OF-STARTUP.--.No-4PPlicable 25.
UNITS IN TEST STATUS (Pal 0R TD Cott.:ERCI AL OPERATION).... TDT APPLICABLE
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yankee UNIT lladdam Neck DATE December 12, 1979 COMPLETED BY Reactor Engineering TELEP110NE (203) 267-2556 MONTil: November, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PO'..'ER LEVEL (MWe-Net)
(MWe-Net) 1 583 17 579 2
583 18 582 3
582 19 583 4
582 20 583 5
582 21 583 6
583 22 583 7
583 23 583 8
583 24 582 9
584 25 583 10 583 26 581 11 549 27 582 12 583 28 582 13 584 29 582 14 584 30 582 15 583 31 16 583 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.
1608 :26 (9/77)
50-213 UNITSI'U1 DOWNS AND POWER FED *Js"TIONS DOCKET NO.
UNIT NAME C un. Yan,cee DATF.
December 12 1979-CO. fPLETED ity jeac t6r' EnnIIbering
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REFUELING INFORMATION REQUEST 1.
Name of 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 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 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 wit!
(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 ar.d 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 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 aasemblics.
1168 9.
The projected date of the last refueling that can be discharged tr the spent fuel pool assuming the present licensed capacity.
1994 to 1995 1608 328