ML20155A859

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Ro:On 860222,dose Equivalent Iodine (I-131) Levels Exceeded 1 Uci/G for 7.5 H After Unit Shutdown on 860221 to Repair Hydrogen Leak in turbine-generator Unit.Peak Activity Spike 1.96 Was Uci/G.Cause Not Stated
ML20155A859
Person / Time
Site: Maine Yankee
Issue date: 03/24/1986
From:
Maine Yankee
To:
References
73511-SDE, GDW-86-76, MN-86-47, NUDOCS 8604100089
Download: ML20155A859 (3)


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MAIRE RHEE MOMICPOWERCOMPARUe AUGUSTA, MAINE 04336 (207) 623-3521 e

March 24, 1986 ht4-86-47 GDW-86-76 Region I United States Nuclear Regulatory Comnission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator

Reference:

(a) License No. DPR-36 (Docket No 50-309)

Subject:

Primary Coolant System Iodine Spike Gentlemen:

o ursuant to Haine Yankee Technical Soecification 3.2.C, please find attached our report on the prirrary coolant system iodine spike of February 22, 1986.

Please contact us if you have any questions.

Very tr yours, fMITE f ANKEE ATOMIC PC.iER Cut 43ANY Jhfif h r G. D. Whittler, Manager Nuclear Engineerirg and Licensiry GDW/bjp A ttachment: Suoject Report cc: Mr. Ahsak C. Thadani Mr. Pat Sears Mr. Cornelius F. Holden g4 $$0 e t S

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. M AINE YANKEE ATOMIC POWER COMPANY ATTACH ENT 1 MN-86-76 PRIMARY CDOLANT SYSTEM IODINE SPIKE FEBRUARY 22, 1986 On February 21, 1986, Maine Yankee shut down to repair a hydrogen leak in the turbine-generator unit. Approximately seven and one-half (71/2) hours after shutting down the reactor, the primary coolant system Dose Equivalent I-131 (DEI-131) levels exceeded 1 uC1/g. DEI-131 levels were above 1 uC1/g fur 7 1/2 hours on February 22, 1986. Peak activity level for the DCI-131 spike was 1.96 uC1/g (Table 1).

Table 1 depicts the del-131 activity, reactor power, primary coolant system letdown flow rates and degassifier operation during the period February 20-24, 1986. Computer data were not available from 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on February 21 until 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, February 22, 1986, because of disk drive problems. However, during thir period, the reactor was being shut down in a controlled manner, at a rate of 9% per hour, beginning at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, and attaining 0% power at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on February 21, 1986. Normal letdown flow through the demineralizer was maintained during this period. On February 21 and 23,1986, approximately 2450 gallons and 2390 gallons, respectively, of primary coolant were processed through A degassifier. The fuel burnup data by core region is summarized in Table 2.

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, .MAtNE YANKEE ATOMIC POWER COMPANY ATTACitWNT 1 TAB.E 1. TIE HISTORY OF DOSE EQUIVALENT I-131 (DE I-131) ACTIVITY AND PLANT OPERATING CHARACTERISTICS, FEBRUARY 20-24, 1986.

"A" Dose Equivalent Letdown Flow Degassifier Date Time (Est) I-131 (uCi/g) Reactor Power (%) Rate (@m) Operation 2/20/86 0415 5.37 E-2 84 80 0 gal 0820 5.08 E-2 84 82 1930 4.01 E-2 84 81 2/21/86 0345 4.87 E-2 84 82 2450 gal 0930 3.85 E-2 ND

  • NO 2000 6.01 E-2 48 to 2/22/86 0050 9.03 E-1 0 to O gal 0655 1.96 EO O 75 0800 1.76 EO O 80 1000 1.47 EO O 79 1300 1.16 EO O 80 1425 9.86 E-1 0 74 1715 7.48 E-1 0 84 2110 5.25 E-1 0 50 0

2/23/86- 0045 4.04 E-1 0 80 2390 gal 0505 3.10 E-1 0 82 0700 2.65 E-1 0 77 2050 8.54 E-2 0 76 0 -

2/24/86 0040 6.85 E-2 0 76 0 gal 1045 5.08 E-2 0 76 2255 2.72 E-2 0 76

  • ND = no data; computer disk drive problem 7351L-50E c__ _ _ _--.__---_____o

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'*' ,WAINCYANMEE ATOMIC POW 2n COMPANY

, TABLE 2. FUEL BURNLP BY CORE-REGION. ATTACHENT 1

' REGION CYCLE BURNLP (MWD /MT) TOTAL BURNLP (MWD /MT)

E16 3079.95 23514.28 LO 2626.30 23951.91 LA 3360,88 30957.37 L8 2199.44 23687.02 1

L12 3114.80 32274.84 i

MD 4180.83 16079.87 -l 6% 3475.91. ,16412.20 I

, 1 M8 3982.38 19452.56 l to 3751.78 3751.78 N4 3562.39 3M 2.39 I t

N8 4203.03 4203.03 i

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