ML20129G389

Monthly Operating Rept for Mar 1985

ML20129G389
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1985
From:	Dean C, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8506070248
Download: ML20129G389 (10)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck' DATE MARCH 1985 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH:

MARCH 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 583 31 17 2

583 18 327 3

583 19 362 4

583 20 581 5

583 21 583 6

583-22 583 7

582 23 583 8

582 24 583 9

582 25 583 10 555 26 583 11 581 27 583 12 202 28 583 13 0

29 583 14 151 30 583 15 281 31 582 16 470 DR A

13 INSTRUCTIONS R

PDR 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.

1. v (9/77)

l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME. Haddam Neck DATE March 1985 I

1 COMPI,ETED BY C. B. Dean REPORT MONTH MARCH 1985 TELEPHONE (203)267-2556 m

Cm O M O No.

Date 3g

.o S LER 4

Cause & Corrective N

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85-01 03-12-85 F

23 hrs.

A 3

B5-007 CH PIPEXX High RCS pressure due 33 mins.

to loss of main feed-water. Failure of air control line to recir-culation valve.

85-02 03-16-85 F

12 hrs.

A 1

35-006 CH PIPEXX Manual trip - large leak 48 mins.

in piping between IB feedwater heater normal level control valve and its downstream isolation valve.

1 2

3 4

F Forced Reason:

Method:

Exhibit G-Instructions S Scheduled A-Equipmeat Failure (Explain)

H-Other(Explain 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License @

C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other(Explain)

(NUREG-0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 Same Source

r..

-s-

. REFUELING INFORMATION REQUEST y.

' '1.! ' Name of fetcility; Connecticut Yankee Atomic Power Company

'82.

! Scheduled date for next refueling shutdown.

..J. nuary. 4,.1986 3.?' Scheduled date for: restart-following refueling.-

Msrch 1, 1986 74.'J(a) Will refueling'or resumption of operation thereafter require a technical' specification change or other license amendment?

'NO

. b)-' If answer is yes, what, in general, will these be?

l

(

f N/A L

'.(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)?

Core' reload design in progress.

(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.

N/A 6.

Important licensing-considerations associated with refueling, e.g., new or different fuel d2cign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

NO 7.

Th2 number of fuel assemblies-(a) in the core and (b)-in the spent fuel storage pool.

s (a) '157 (b)- 545 E8.

Th3 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. 'Th3 projected date of the last refueling that can be discharged to the spent fuel pool azguming the present licensed capac!ty.

~

1994 to 1995

[

CONNECTICUT YANKEE ATCMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 85-03 FOR THE MONTH OF MARCH 1985

.i

SPLANT OPERATIONS-

'On March'10,-1985, at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the unit commenced a' load reduction to 400 Mwe to conduct a routine turbine control valve test. The test was completed at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> and the plant returned to full power at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />.

On March 12, 1985, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, the switchgear room halon system discharged.

This was caused by overheating of the resistor bank for the "B" condensate pump'.(there was no smoke or fire). At 0320 hdurs the unit started a load reduction to 50 percent power due to a ground in the motor stator. At 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />, the plant tripped off line on high reactor coolant system pressure as load was being reduced to compensate for a broken air line on the. feed pump recirculation control valve.

On March 13, 1985, at 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br />, the unit started a critical approach. The reactor went critical at 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br />, and at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> the unit was holding at 50 percent power for return to service of "B" condensate pump. On March 15, 1985, at 2255 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.580275e-4 months <br />, the plant commenced a load increase.

The unit reached full power on March 16, 1985, at 0410 hours0.00475 days <br />0.114 hours <br />6.779101e-4 weeks <br />1.56005e-4 months <br />. A manual: plant trip was initiated-at 2008 hours0.0232 days <br />0.558 hours <br />0.00332 weeks <br />7.64044e-4 months <br /> due to a large leak in the piping between the 1B feedwater heater normal level control valve and its downstream isolation valve.

On March 16, 1985, at 2238 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.51559e-4 months <br />, the unit commenced a critical approach which was suspended due to rod control malfunction. The master cycler was replaced and at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br /> the plant recommenced a critical approach.

The plant phased on line on March 17, 1985, at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br />. After two chemistry holds at 5 percent and 25 percent, the unit commenced load increase to full power on March 18, 1985, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />. At 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br />, the load increase was stopped because of a problem with low pressure steam dump relays. At 0819 hours0.00948 days <br />0.228 hours <br />0.00135 weeks <br />3.116295e-4 months <br />, the plant started reducing load to work on the OPC relay. At 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />, a load increase commenced to 100 percent power. Load increase was stopped at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br />'and the unit reduced load to 50 percent power to fix the "B" main feed pump casing gasket. On March 19,1985, at 1316 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.00738e-4 months <br />, a load in:rease commenced and the plant reached full power at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> on March 20, 1985.

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CONNECTICUT YANKEE REACTOR COULANT DATA MONTH: MARCH 1985 REACTUR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM 00...................................................................

PH @ 25 DEGREES C 6.08E+00 :

6.40E+00 6.7PE+00 :

CONDUCTIVITY (UNHOS/CM) 6.45E+00 :

1 13E+01 :

1.80Ef01 :

CHLORIDES (PPM)

<5.00E-02 : <5.00E-02 : <5.00E-02 :

DISSOLVED OXYGEN (PPD)

<5.00E+00 : <5.00E+00 : <5.00E+00 :

BORON (PPM) 6.13E+02 6.83E+02 :

9.17Ef02 :

LITHIUM (PPM) 5.73E-01 :

9.73E-01 :

1 68E+00 :

TOTAL GAMMA ACT. (UC/ML) 3.43E-01 !

6.74E-01 !

1.00E+00 10 DINE-131 ACT. (UC/ML) 1.60E-03 :

6.17E-03 :

3.71E-02 :

1-131/I-133 RATIO 3.60E-01 :

1.76E400 9.97EiOO :

CRUD (MG/ LITER)

<1.00E-02 : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML) 1.91E+00 :

3.49E400 :

4.95E400 :

HYDROGEN (CC/KG) 3.37Ef01 3.54E+01 :

3 66E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):

1.35E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

1.56E+05 AVERAGE PRIMARY LEAK RATF(GALLONS PER MINUTE) 2.60E-01 PRIMARY TO SECONDARY LEAN RATE (GALLONS PER MINUTE):

0.00Ef00 l

e 48s068* el aPL RATi% ST ATUS AtPdRT LOMPLE TEd JV REACTUA ENGI' FEER!rG

• • • c0**

1.

DuC K E T.... 53- ? t 3 0P F R A TINC STA T tl 5 2.

AcedkII.6 Pctido..."AdCet 19d5 uuTAGF. ONLitat H0JPS... b4

+ 707.0

= 744 3.

ti t I L I l v C tra i t C T................ J. P. OmAGn (2033 267-25*m tai 452 4.

LICtNsfu Tita1AL P0.La...................................

1 25

• CundrCTICOT YANnEL o 5.

r4AMc PL A T E F A T I% 5 0na SS Nat i................ 66 7 a 0.9 = 000.3

• HADJAM f4ECK PL AN T c 6.

DESIS. tLECitICAL %AilMG (NET M.EE........................

$d2 7.

Maul"J" OE*t1JASLL LAPACITY 86RJSS Mdet.................

595.8 8.

P t y 1NM Dept'au A;,LE L AP 4Clif I:4E T Mdtl....................

569 9

IF CNA%E S OC.JR AtuWe SI.40 E LaST RLPORI, et A50:45 A RE......N/ A

10. POwc4 LEvil TO.+41CH dE5fdICTsD. IF ANf INET *WEl..........f4/A

11. R E a Sta t ad ME s Tk f C TI O% IF A?tv............................

1/A M O.NT H VR. TO DATE CUMtJL A T IVE TO DATE

12. HJJn S I Ps RE PlH T !*1a PEMIOD F44 0 2150.0 15120J.O *

13. Nc*oE k of 190045 TttF *tACf01 WAS CRITICAL 723.9 2139.1 129897.0 *

14. PLACTOR R CSEh E Sttui3Odr4 H)o*S 0.3 0.0 1264 0 *

15. HOURS Gt4L4ATOR 0.NL11L 70 T.6 2123 6 1243?d.1

• N traf f REsEMVE SHJTUO.1 H0tidS 0.0 0.0 373.7 *

17. GidSS T 'e E R*t AL Er4 racy t,CM k ATED (Mecil 1152097.0 3725474.0 2159129 7.0

18. G4055 ELECTdfCAL tNc4GV GEMcRATED fHWHI 333999.0 124365T.0 7093?bl5 0

19. ?;ET FLELTRICai E*sERGY GEMt4ATtD IMdHI 36462).J 1185645.9 67446711 0 2C. tp4ti SERVICt F ACTbt 95.1 9d. S S2.2 *

21. U.fi vAILAo!LETY FACTOR 95 1 96.5 92.5 *

22. U4tf CAPECITf FACIOd (185110 t'DC NE T I 86.1

%. 5 62 1 *

23. U'.! T C AP ACl if FACTOR tus!'45 DER

'4 E T s 84.2 94.3 Ti. i

• 2*. UwtT F3xCED JaTAG: unTE 4.9 1.7 5.9

• l

25. (A4IT fonCE3 JJTAG: H ba5 h4 h4 7F42.5 *

• SI*tCf COMMEdCIAL OPEPATION 1/1/69 StiliDL,415 SCt4EOULL O avC R r4E AT S ix MJ4THS (TYPE, DATC AND OtJRATION 1F EACH3.............

N/A TF cud *EMILi SituTCOW 4, L5!!MAiro STA1TU7 0 ATE....................

i4/A l

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%e CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT RR 31. BOX 127E, EAST HAMPTON, CONN. 06424 April,15, 1985 Docket No. 50-213 Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Monthly Operating Report 85-03, covering operations for the period March 1, 1985 to March 31, 1985 is hereby forwarded.

Very truly yours, Richard H. Graves Station Superintendent RIIC/ sos Enclosures cc:

(1) Director, Region I Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2) Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 hI 3

l

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