ML19351E110

Operation Rept 89 for May 1968

ML19351E110
Person / Time
Site:	Yankee Rowe
Issue date:	06/24/1968
From:	YANKEE ATOMIC ELECTRIC CO.
To:
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ML19351E106	List: ML19351E105 ML19351E110
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NUDOCS 8011250611
Download: ML19351E110 (9)

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1 YANKEE f _ CLEAR POWER STATION 1

OPERATION REPORT NO, 89 For the month of MAY 1968

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YANKEE ATOMIC ELECTRIC COMPANY O

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June 2h, 1968 8 011 'J 5 0 h / e

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o This report covers the operation of the Yankee Atomic Electric eampany plant at Rowe, Massachusetts for the month of May,1968.

On May 1 at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, the Core VII physics startup test program was completed; steam lines were warmed and vacuum was established in the main condenser in preparation for plant startup.

Turbine rolling commenced and at 1119 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.257795e-4 months <br /> the generator was phased on the line.

The Core VI-VII refueling and maintenance outage time was approximately 39 days.

Reactor power level was increased to h50 MWt and then $ho MWt; on May 2 at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> full power was attained witn plant generation at 178 MWe. During the remainder of the period plant load varied between 177 MWe and 182 MWe as circulation water inlet temperature fluctuated between h2 F and 50 F.

Plant load was reduced to l$ MWe on May 2 at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> to repair a +urbine orifice drain line leak; load was restored at 17h5 hours. On May 21, load was decreased to lh5 MWe for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to the presence of an electrical storm in the area.

The International Atomic Energy Agency seals were placed on the reactor head missile shield by a representative from that organization.

On May lh the monthly control rod exercise was performed; it was necessary to nove control rod No. 22 six steps out to bc in phase with tae rest of the group, Control rod groups B, C, and D were banked at 87 0/8 inches for the

',, ltart of the step wear program. Every six weeks these control rod groups are

- Joved out one step; the purpose of this program is to distribute guide block wear.

The first air charge to the vapor container was completed on May 9 Plant Shutdown Shutdown No. 93-6-8 3/23-$/1/68 A 928.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> scheduled shutdown for Core VI-VII refueling.

Plant Maintenance The following is a list of pertinent maintenance items performed by the plant staff during the month of May,1968.

1.

The No.1 service water punp was inspected and repaired.

Two sections of the shaft were built up with netal; in addition, the motor lower guide bearing was replaced.

2.

The "hydropad" in the No. 2 charging pump discharge line was removed, vented and placed in storage. This equipnent was installed to determine if this type device could surpress charging line vibration. Subsequent testing indicated that the "hydropad" was ineffective.

, s3 The inboard bearing of the No. 2 component cooling water pump and both

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shaft sleeves vere replaced.

h.

The evaporator circulating pump mechanical seals were replaced.

5.

Packing rings were renewed in No.1 plunger of No.1 charging purp.

e o Ins tranentation and Control e

The following is a list of pertinent instrunentation and control naintenance itens performed by the plant staff during the nonth of May, 1.

The control point on the automatic nakeup valve to the conponent cooling water surge tank was decressed from 7 5 to 6 3 feet.

This change was nade to allow a more accurato deternination of any leakage from that oystem.

2, Installation of a pneumatically operated valve in the generator hydrogen vent line was started-This additica will pernit the discharge of generator hydrogen from a control in the main control roon in an emergency situation.

3 Installation of incere flux wires modified with a snall dianeter one inch tip was continued-h.

Permanent repairs were nade to the underwater television camera housing.

5 The recorder and measuring systen for determining Sherman Station tailrace water temperature was installed.

Reactor Plant Performance Fbllowing the completion of Core VII physics startup test program on May 1, annonia was added to the coolant and plant power operation commenced.

g ~lowar coefficient data were collected as reactor power level was increased to j$0 MWt; thereafter, Xenon effects precluded the compiling of additional data.

However, an extrapolation of the available information to 600 MWt indicates that a gain of 0 7% A K/K was realized as compared to comparable data obtained during startups with unadjusted pH cFemistry.

On May 2 plant load was reduced from 600 MWt to 50 MWt to effect secondaly system repairs; plant load was restored after approximately one hour.

Three days after this load cycle the annonia feed to the coolant was secured and it was apparent that a reactivity gain was occurring-On May 8, nixed bed purification was initiated and all ammonia was renoved from the system.

Ammorta renoval cancelled the ceactivity gain which had reached 0,2% K/K The boron depletion slope for Core VII is O 157 ppn/ MWD /MTU at 1200 ppn The following parancters were deternined by means of incore ins t rumentation A.

Zircaloy assenbly o

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592 MWT, 52h 8 F TAVG, control rod group A at 83, B, C, and D at 90,

1373 ppm boron.

F

= 2.01 7~-

g FaH = 1,90 Minimum DNBR = 3-32 o

Maxinun outlet temperature = 585 F

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Stainless steel assembly g

$97 MwT, $25.0 F Tgyg, control rod group A at 89, B. C. and D at 87,

12$$ ppm boron, Fq = 2.6$

F H= 2.26 Minimum DNBR = 2.80 Maximum outlet ter:perature = $96,h F Secondary Plant Performance During Core VI-VII refueling, repairs were made on feedwater heaters #2 and #3 These repairs resulted in a terminal difference decrease 0

of 1.5 F and 9 20F respectively.

Terminal differences for the month were as follows:

1. 1 = 7.3

1. 2 = 12.1

1. 3 = $.h The condenser performsnce was as follows:

TTD = 36.86 cleanliness fu ter = 6h.3%

Chemistry Prior to power operation on May 1, ammonium hydroxide was added to

_ the mai_ coolant system to raise the pH above $.o as required by plant Technical

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fpecifications; when the generator was phased on the line at 1119 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.257795e-4 months <br /> on

- May 1, 6.h5 ppm of ammonia had been added to produce a pH of 6.oh in the main coolant system.

Normal boron dilution consistent wlth power operation and the buildup of equilibrium Xenon permitted removal of the ammonia on May 8-The amonia was removed fron the system using a mixed bed (H B03 ::) demineralizer.

Following amonia removal, the main coolant pH has averaged 3.3 and coolant boron concentration at the end of the period was 1170 ppm.

Main coolant gross beta-gamma specific activities as high as 2.1 x 10~1 uc/nl and crud levels as high as 19.7 ppm were experienced during the early part of the period because of the reactor startup and changing chemistry conditions.

During the re levels averaged 1.13 x lo gainder of the month specific activity and crud uc/ml and 0.27 ppm, respectively.

The nain coolant tritium specific activity has increased from 0.oh uc/nl to 3.61 uc/ml since the reac tor was brought to power.

The iodine - 131 specific activity averaged 2.h x 10-6 ue/ml; the iodine 131/133 atomic ratio was 0.80.

A crud sample collected on May 6, while the system was annoniated and borated, had the following radiochemical analyses:

dpm/mg crud Cr-51 Hf-161 Mn-5h Fe-39 6

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6 3.5h x lo 1.3 x 11 3.93 x lo 1.02 x lo Co-58 co-60 Ag-lloMh 6

2.65 x 107 7.66 x 10 2,6h x lo N

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s h-A crud sample collected on May 17, after the ammonia had been removed, had the following radicchenical analyses dpm/cg crud:

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Cr-51 Hf-181 Mn-5h Fe-59 5

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5 8.09 x 10 3.1 x 10 1.16 x 10 h.kl x 10 Co-58 Co-60

^8-llCM h 6

6 5.61 x 10 1.89 x 10 2.31 x 10 A main coolant gas sample collected on May 27 had the following radiochemical analyses:

pc/cc gas i

Xe-133 Xe-135 Ar bl

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-2 1.h7 x 10 1,74 x 10 5.90 x lo-Health and Safety Waste disposal liquid releases totaling 64,h20 gallons contained 10h uc of gross beta-gamma activity and 56.62 curies of tritium. Gaseous releases during this period were 20.h me of gross beta-gamma activity.

Gecondary plant water discharged was 282,h87 gallons and contained a total of 31.09 pc of gross beta-gamma activity and 228 me of tritium.

Three shipments of low level radioactive vaste containing 165 drums with a total activity of 612.5 cc were made during the month of May.

In addition, one shipment of 1h drums contained in a shielded cask with a total activity of 2.985 curies was made.

Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of May,1968 were as follows:

Average accumulated exposure dose 175 mrem.

Maximum accumulated exposure dose h51 mrem.

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a YALTEE ATOMIC ELECTRIC COMPANY - OPERATING SUfotARY MAY 1968 ELECTRICAL MONTH YEAR TO DATE Gross Generation KWH 130,504,800 414,064,800 8,12h,949,h00 sta. Service (While. Gen. Incl. Losses)

KWH 7,970,507 27,721,840 540,388,773 Net Output KWH 122,534,293 368,342,960 7,584,560,627 Station Service 6.11 6.70 6.65 Sta. Service (While Not Gen. Incl. Losses) KWH 78,822 960,041 25,765,568 Ave. Gen. For Month KW 175,h10 Ave. Gen. Running KV 178,120 PLANT PERFORMANCE Net Plant Efficiency 5

28.39 28.04 28.38 Net Plant Heat Rate btu /KWH 12,021 12,171 12,025 Plant Operating Factor 96.69 62 97 72.90 7

Reactor Plant Availability 99.12 74.71 82.91 NUCLEAR MONTH CORE VII

"'OTAL Hours Critical HRS 738.58 753.31 55,860.73 Times Scrammed 0

0 55 Burnup Core Average MWD /MTU 870.k2 870.h2 Region Average MWD /MTU A (INNER) 877.413 877.43 23,392.74 B (MIDDLE) 1012.201 1012.201 10,999.63 C (OUTER) 667.733 667.733 667.73 D (ZIRCALOY) 1253.891 1253.891 1253.89 l

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YANKEE ATOMIC EIJLTRIC COMPANY -- OPHIATING

SUMMARY

APRIL 1968 EIJCTRICAL PONTH YELR TO DLTE Oross Generation DGi 0

283,560,000 7,994,hhh,600 Sta. Service (While Gen. Incl. Losses)

DGI o

19,751,333 532,h18,266 Net Output DGI o

263,808,667 7,h62,026,33h Station Service 0

6.97 6.66 Sta. Service (While Not Gen. Incl. Iosses)

DGI 690,566 881,219 25,686,746 Ave Gen. For Month Di 0

Ave. Gen. Running Di 0

PIAUT PEEFORMANCE Not Plant. Efficiency 5

0 27.88 28.37 Not Plant Heat Rate Iffu/ Dill 12,2h1 12,029 Plant Operating Factor 0

54.32 72.61 7

3 Reactor Plant Availability 0

68.h6 82.72 NUCs. EAR J0tfrH CORE VI TOTAL Hours Critical HRS 14.73 11,381.74*

55,122.15 Times Scrammed 0

3 55 Barnup Core Average WD/MTU 0

12,418.76 Region Average WD/MTU A (INNDt) 0 12,493.587 29,266.08 B (MIDDLE) 0 1h,840.042 22,515.33 C (OUTER) 0 9,987.432 9,987.43 The hours critical for Core VI was inadvertently reported as 11,396.h7 in April 1968 (Operation Report No. 88).

The corrected number is 11,381.74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.

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