ML20137B587

Monthly Operating Rept for Mar 1978

ML20137B587
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1978
From:	Graves R, Wong H CONNECTICUT YANKEE ATOMIC POWER CO.
To:	Volgenau E 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-78-114, NUDOCS 8511260306
Download: ML20137B587 (11)

Text

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t CONNECTICUT YANKEE ATOMIC POWER COMPANY llADDAM NECK PLANT

!!ADDAM, CONNECTICUT MONTilLY OPERATING REPORT NO. 78-3 FOR Tile MONTil OF MARCll, 1978 8511260306 851119 PDR FOIA

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, PLANT OPERATIONS The following is a chronological description of plant operations for the month of March, 1978.

3-1 "D" service water pump removed from service for maintenance.

3-11 Cooling fan 9A on main transformer failed at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> and was returned to service, after repair at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on 3-15-78.

3-17 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> commenced load reduction due to reactor coolant low flow relay failure. Load was reduced to 400 MWe to repair relay 404-C and conduct a turbine stop and control valve test.

3-17 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br /> commenced load increase and reached full power at 1121 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.265405e-4 months <br />.

3-20 "A" high pressure safety injection pump was removed from service to replace the packing glands with mechanical seals.

3-21 1A rod drive M.G. set was removed from service for maintenance.

3-23 Plant was shutdown to change the connector boxes for the core deluge valve'.

s 3-24 At 0416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br /> the #1 seal on #4 RCP failed and necessitated isolating and depressurizing loop #4 to replace the seal.

3-24 Terminal block box replacement and retest of core deluge valves completed.

3-24 Following precritical tests and checks a critical approach was commenced at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />. Attained criticality at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on 3-24-78.

3-25 Load was increased to 150 MWe at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> and full load (380 MWe) for 3 loop operation was reached at 1322 hours0.0153 days <br />0.367 hours <br />0.00219 weeks <br />5.03021e-4 months <br />.

D service water pump was returned to service at 1520 on 3-25-78 following overhaul.

3-29 Seal replacement on #4 RCP completed and loop #4 heatup commenced at 1455 hours0.0168 days <br />0.404 hours <br />0.00241 weeks <br />5.536275e-4 months <br />.

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3-29 Load decrease from 65% full power commenced @

2200 on 3-29-78 and unit off line 0 0046 on 3-30-78.

Reactor shutdown @ 0254 and loop 4 placed in service.

3-30 Critical approach commenced 0 0331 and reactor was critical 0 0427 on 3-30-78.

Turbine was rolled and generator phased to line @ 0702.

Load increased to 150 MWe @ 0800 and held for steam generator chemistry.

Load was increased from 150 MWe @ 1040 with full load achieved @ 1705 on 3-30-78 and remained @ full power through the rest of this report period.

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SYSIDi ON CORRECTIVE A'.IION TAKEN TO PR0'JIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY 4

COMPOSENT CAUSE RESULT OPERATION REPETITION DURING REPAIR b

1. 4 Reactor Coolant Chipped Seal Failed Seal None Replaced Seal None Required Pump From Unknown Reactor Shutdown J.O. 15765 Cause j

i MOV 871 A and B N/A N/A N/A Replaced aluminum boxes at head None Required J.O. 15760 with steel due to results from Reactor Shutdown i

j Core Deluge LOCA environmental qualification During Change test 1

Reactor Containment N/A N/A N/A Checked torque on all mounting None Required Electrical Penetra-bolts Reactor Shutdown i

tion Terminal Boards During Job J.0. 15763 Run Down Battery

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WIS Channel 22 In Channel 22 Upscale Drift None Replaced battery None Trip Not

,i Differential Needed Above 10%

Amplifier Power NIS Channel 31 Faulty Bi-Stable Spiking and None Replaced power supplies and None 3 Channels 100% Power replaced Bi-stable card Available i

Meter Went To Zero

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50-213

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COMPT.ETED itY H. H.

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REl'OR r bl0NTil March 1978 ll:1.1.Pil0NE 203-267-2556 1

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loop back in service 1

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• Current plant copy of NUREC-0161 (published July 1977) does not include this exhibit. 'These particular pages

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are labeled "To be furnished later" Explanation in Cause and Corrective action column

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.t AVERIGE D AILY UNIT POhER LEVEL DOCKET NO.

50-213 Conn Yanke

t. NIT DATE COMPLETED BY 11. II. Won g 203-267-2556

,TELEPflONE MONTH March 1978 DAY AVERAGE D AILY POhER LEVEL DAY AVERAGE Dr!LY POhER LEVEL i MWe-Net I Sih e. Net )

576.5 541.3 577.8 2

is 577.2 577.5 3

39 573.7 577.8 574.4 4

,o 574,8 5

578,1 6

2 578.9 550,4 7

~3 0.0 580.6 8

• 4 580.4 257.5 9

25 580.9 10

'6 367.5 l

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368.3 580.4 12 28 369.2 580.6 13 29 358.2 566.9 271.5 g4 39 584.9 15 3:

576.0 i

579.8 1

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1 1NSTRUCTIONS On this format. fist the netage daily anit.'. wer :e.el.n MWe Net f.,r each J4) ;r. the : ;. r ing m.. nth. C :r.9 ate * -

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ClfEMISTRY DATA FOR MONTit OF March 1978 Reactor Coolant Analysis Minimun Avernee Maxinum Ph @ 25 C( 2.0E-01) 6.10E00 6.42E00 6.80E00 Conductivity, umhos/em(i25) 9.15E00

1. 31 E+ 01 1.95E+01 Chlorides, nnm(17. OE-02 )

<3 00E-02

<3.00E-02

<3.00E-02 Dissolved Oxycen, cob ( 5.OE+00) 0.00E00 0.00E00 0.00E00 Boron, pon ( 25) 8.88E+02 9.76E+02 1.106E+03 Lithium, nem ( 5%)

8.40E-01 1.17E00 1.85E00 Oross Decassed Act.,pci /m1( 2,OE-02) 2.57E-01 9.18E-01 1.69E00 Todine-131,pC1/m1( 35) 2.49E-02 1.01E-01 5.87E-01 I-131/I-133 Ratio 3.11E00 6.04E00 1.82E+01 Crud, mc/1( 1.0E-02) 2.00E-03 7.40E-03 1.30E-02 Tritium, uCi/m1( 5.OE-02) 2.57E00 3.42E00 3.89E0 Hydrogen,ce/kc(!2.OE+00) 2.54E+01 2.72E+01 3.21E+01 Aerated liquid vaste processed:

1.04E+05 gallons Waste liquid processed through Boron Recovery System:3.97E+04 gallons Average primary plant leak rate:

.144E00 Epm Primary to secondary leak rate:

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REFUELING INFORt!ATION REQUEST 1.

Name of facility.

Connecticut Yankee Atomic Power Company 2.

Scheduled date for next refueling shutdown.

February, 1979 3.

Scheduled date for restart following refueling.

Approximately six weeks from shutdown date.

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

No. Connecticut Yankee Technical Specifications are reload independent.

If answer is yes, what, in general, will these be?

N/A 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)?

Yes, see answer to 4 above If no such review has taken place, when is it scheduled?

i 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 storage pool.

(a) 157 (b) 288 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 or 1995 e

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CONNECTICUT YANKEE ATOMIC POWER COMPANY V\\.7 HADDAM NECK PLANT

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I RR = 1. DOX 127E. CAST HAMPTON CONN. 06424 J

April 12, 1978 CYli 78-114 Docket No. 50-213.

, Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 ATTENTION:

Mr. Ernest Volgenau

Dear Sir:

In accordance with reporting requirements the Connecticut Yankee Haddam Neck Monthly Operating Report i8-3 covering operations for the period of March 1, 1978 to March 31, 1978 is hereby forwarded.

Very truly yours, e

R. H. Graves Station Superintendent RHG:QB/mts Enclosures (6) cc:

(1) Director, Region I Division of Inspection 6 Enforcement U. S. Nuclear Regulatory Con' mission 631 Park Avenue King of Prussia, Pennsylvania

.19406 (2) Director, Office of Management Information and Program Control l

U. S. Nuclear Regulatory Commission Washington, D. C.

20555 8-1 we-.

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