ML19351E316

Operation Rept 111 for Mar 1970

ML19351E316
Person / Time
Site:	Yankee Rowe
Issue date:	04/21/1970
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19351E315	List: ML19351E313 ML19351E316
References
NUDOCS 8011280100
Download: ML19351E316 (8)

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YANKEE NUCLEAR POWER STATION OPERA'; ION REPORT NO.111 Regulatory Fife Cy, For the Month of i

t March 1970 Recehad w/.tr Dated OM N 1

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R3UM TO PIEATORY CENTRAL RLES ROOM DiB I

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I Submitted by l

YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts i

April 21, 1970 r

/00 801128ok L

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EGLATORY DOCKE1:JJ COPY J

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L 4 Company at Rowe, Massachusetts for th'e month of March,1970.

This report covers the operation of the Yankee Atomic Electric i

. At the start of the period, the plant load was 184.1 !Ge. Two 1

. scheduled plant shutdowns occurred during the report period. The first

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t shutdown vas on March T and 8 for reactor operator training. -The second shutdown. commenced on March 21 at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> to allow reactor demonstrative j

testing of reactor operator license candidates; following which the plant was placed in a cold shutdown condition for maintenance which included g

leak repairs-to the No. 1 steam generator. During the period March 1 - 21, f

the primary to secondary leak rate had increased from 2h0 to 2h6 gallons per day.

The third Core VIII vapor container air leakage surveillance j

period was teminated on March 21, coincident with reactor shutdown. Leakage i

during the period was normal. The fcurth Core VIII surveillance period commenced subsequent to return to pver operation March 29, and was in progress at the end of the. report period.

On March 23 the No. 1 steam generator inlet and outlet manway covers and seal velded diaphrac.e were removed; the secondary side was hydrostatic-ally tested to 200 psig; and two leaking tubes were found and marked for plugging.. Radiation levels were consistent with those experienced previously,

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exhibiting 10 - 13 r/hr at 18" from the_ tube sheet.

On March 2h, the two

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leaking tubes were sugged. A subsequent hydrostatic test of the secondary j

side to 800 psig shoved.a third tube to be-leaking, which in turn was plugged.

l Further pressurizing.of the secondary side indicated no additional tube l

leakage. A new, vender developed technique which involved the explosive j

velding of a thimble type plug to the tube internal surface was used to effect j

tube repairs. The total radiation exposure to personnel for this job was approximately 15% of that incurred in the past for similar tube plugging i

operations utilizing the conventional driven plug and seal veld technique.

By March 26, new diaphrag=s had been velded in place and both manvay covers were reinstalled. Subsequent main coolant system pressurization to 2000 psig l

revealed no leakage at the diaphragms.

Plant heatup was commenced and the reactor was brought critical on March 28. _During plant heatup on March 28, a leak was detected in the No. 3 steam generator blevdown line. The No. 3 main coolant loop was iso t ted and cooled down;. and repairs were made to the blevdown line. On Farch 29 l

at~0Th5 hcurs the No. 3 loop was placed in service and at 1918 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.29799e-4 months <br /> the i

generator was phased on the line. At-the end of the period plant load was

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185.2 IWe.

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Plant Abnormal Occurrences

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There vere no plant abnormal occurrences during the report period.

Plant Load Reductions ~

.There were no plant load reductions.during the report period.

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Plant Shutdowns Shutdown No. 105-8-70:

3/7/70 - 3/8/70, plant shutdown for reactor operator training. Total outage time: 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> 58 minutes.

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i Chutdown No. 106-3-70:

3/21/70 - 3/29/70, scheduled plant shutdown for f

reactor demonstrative testing of reactor operator I

license candidates; and No. 1 steam generator i

leak repairs. Total outage time:

206 hours0.00238 days <br />0.0572 hours <br />3.406085e-4 weeks <br />7.8383e-5 months <br />,

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18 minutes.

Plant Maintenance j

The following is a list of major plant maintenance items performed by the plant st, ff during the cold shutdown maintenance period.

1.

The fuel transfer train, which was removed for maintenance during the Core VII-VIII refueling period, was reinstalled and test run, successfully.

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A loop seal was placed in the valve stem leakoff line in the primrry l

auxiliary building valve room.

3 The No. L main coolant loop flow differential pressure cell bypass j

line valve was replaced.

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The Ho. 2 main coolant loop check valve '.as removed for inspection and after minor maintenance, was reinstalle1.

e5 The turbine No. 3 control valve was removed for inspection of its inner j

cylinder no le chamber.

No abnormal conditions were detected. This l

l inspection served as a random check for all four such chambers which j

were renewed during the Core VII-VIII refueling.

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An inspection of the generator end low p - -"re turbine gland steam

'i seal was performed. Clearances betwee7 aousing top and inner casing were adjusted as required.

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The low pressure turbine blading and tne no:,

e separators were in-

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spected. No abnormal conditions were detected.

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The tubes in the main condenser West water box were cleaned with scraper plugs. Two leaking tubes were plugge1.

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9 The station T-1 air circuit breaker wr.s: inspected during the shutdown j

period. Based on the inspection, as a preventive maintenance measure, I

a new air circuit breaker was installed.

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The main coolant bleed line vari-orifice valve was removed and a replace-ment valve installed. New seat rings and vedges were installed in the bleed line isolation valves CH-MOV-527 and CH-MOV-528. The bleed line drain valve VD-V-85L was replaced with a new valve. A 2400 psig auxiliary system hydrostatic test of the above four valves was completed March 27 I

11.

Numerous primary and secondary system valtes were inspected and repacked.

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g ;trumentation and Control The'following is a list'of major instrumentation and control maintenance items performed by the plant staff during the cold shutdown maintenance period.

1..The neutron detectors in thimbles No. 1 and No. 5 were replaced.

2.

A vibration detector was installed on main coolant pump No. 3.

A similar detector was installed'on No. 2 main coolant pump during the March 7 - 8 shutdown.

5.

The~incore thermocouples were recalibrated as required.

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A dropped rod first-out_ panel was placed in service which operates in conjunction with the dropped rod contacts for channels 3, h, 5, 6, 7, and 8.

Mechanical stops were installed at zero indication for all six channels.

Reactor Plant Performance A middle of core life physics testing program was performed on March 28 - 29.

Preliminary results indicated agreement with predicted core parameters. Final analysis of the data was in progress at the end of the report period.

4 Secondary Plant Performance Feedvater heater terminal differences were as follows:

No. 1 = 5.49 F No. 2 = 11.7 F No. 3 = 6.08 F Uhe Condenser. performance was as follows:

785.6 MWe; 1.19" Hg. B.P.;

586 MWt; 3h.96 F C.W. in; TTD = 28.85 F; cleanliness factor = 91.39%

Chemistry The mait ?colant boron concentration was decreased from 588 to 489 ppm during the period _to compensate for normal core depletion..The average pH vas 5.67 On March 21 the main coolant was borated to a 5% shut-down concentration and averaged 1628 ppm with an average pH of 5.h3 during the shutdown period. After physics testing the main coolant boron concentration was reduced by dilution to h28 ppm at the end of the period.

During' power operation the average gross beta-gamma activity and

. crud level were 8.75 x 10-2 ue/ml and 0.02 ppm respectively. During the

-2 March 21 - 29 shutdown period-the gross beta-gamma activity averaged 4.37 x 10 uc 'ml.

l The main coolant tritium concentration decreased from 1.83 ue/ml at 8

-tht beginning of the period to 1.hk uc/ml at the time of shutdown,'due to dilution. Further dilution coincident with reactor startup reduced the l

l tritium. concentration to 0.34 ue/ml at the end of the report period.

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j During power nrieration the average iodine-131 specific activity i

j was 2.36 x 10-5 uc/ml a the iodine 131/133 atomic ratio was 0.41 indicating l

the absence of detectabls "uel defects.

L A representative crud sample for the month, collected on March 16, j

had the following radiochemical analyses; dpm/cg crud j

i Cr-51 Mn-5h Fe-59 7

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1.12 x 10 2.08 x 10 h.95 x 10 l

l Co-58 Co-60 Ag-110M I

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1.20 x 10 2.90 x 10 2.06 x 10 I

A main coolant gas sample collected on March 16, had the following l

radiochemica) analyses: uc/cc gas l

Xe-133 Xe-135 Ar kl

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8.60 x 10 1.3h x 10 1.38 l

Health and Safety l

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One shipment of h5 drums of low level vaste containing a total activity of 32.h me was made during the period.

Waste disposal liquid releases totalled 75,070 gallons containing f

0.0h6 me of gross beta-ga ma activity and 85.96 curies of tritium. Gaseous l

releases during the period totalled 1. 730 curies of gross beta-garma activity j

and 3.111 ne of tritium.

Secondary plant water discharged totalled h59,175 l

i gallons centaining 10.59 me of gross beta-gamma activity and h0.85 curies of l

tritium.

In addition to the above releases 0.767 me of gross beta-gamma j

particulate activity and 3.790 curies of tritium as a vapor were released to i

the environs during the period.

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Work area radiation levels noted during maintenance to the No. 2 l

main coolant loop check valve were 2 r/hr at l' above and 3.5 r/hr inside the

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open valve body; and 2.0 r/hr and 0.h r/hr, on contact and at l' respectively i

from the sving check, removed.

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Radiation exposure doses for Yankee personnel and NEPSCo personnel j

as measured by film badge, for the month of March, 1970 were:

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Yankee Plant Personnel:

1 Average accumulated exposure se:

273 mrem u

Maximum accumulated e.cposure dose: 1160 mrem j

NEPSCo Personnel:

5 Average accumulated exposure dose:

287 mrem j

Maximum accumulated exposure dose:

990 mren 1

• NEPSCo personnel on-site only during March 21-29 shutdown period.

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Overations Attached is a summary of plant operating statistics and a plot of daily average load for the month of March, 1970.

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YANKEE ATOM 1t' ELECTRIC COMPANY - OPERATING SUb' MARY March 1970 ELECTRICAL F10 NTH YFAR TO DATE Gross Generation KWH 9h,779,700 349,482,900 10,565,141,h00 Sta. Service (While Gen. Incl. Losses)

KWH 5,633,826 20,7h9,396 690,754,260 Net Output KWH 89,145,87h 328,733,504 9,87h,387,140 Station Service 5.9h 5.9h 6.54 Sta. Service (While Hot Gen. Incl. Losses) KWH 670,728 872,245 29,780,174 h

l Ave. Gen. For Month (744)

KW 127,392 I

Ave. Gen. Running (519.73)

KW 182,363 4

PLANT PERFDRMANCE Net Plant Efficiency 29.82 29.74 28.45 Net Plant Heat Rate btu /KWH 11,hh5 11,475 11,996 Plant Capacity Factor 66.96 85.30 74.96 P

l Reactor Plant Availability A

07.28 87.50 83.95 i

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i NUCLEAR MONTH CORE VIII TOTAL Hours Critical HRS 535 58 h,318.03 70,137.81 Times Scrammed 0

1 59 Burnup Core Average FMD/?EU 599.44 4,977 00 Region Average FMD/?RU h-A (INNER) 555.28 h,519.39 2h ;0.29 B (MIDDLE) 683.2h 5,721.h5

.t,757.51 i

C (OUTER) 520.25 h,259.03 h,259.03 i

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