ML20212C638

From kanterella
Jump to navigation Jump to search
Ro:On 860612,plant Tripped When Excess Flow Check Valve Inadvertently Closed.Dose Equivalent Iodine (Dei) Activity Also Exceeded 1 Uci/G.Dei Activity & Plant Operating Characteristics Presented in Tables 1 & 2,respectively
ML20212C638
Person / Time
Site: Maine Yankee
Issue date: 07/15/1986
From: Whittier G
Maine Yankee
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
GDW-86-171, MN-86-92, NUDOCS 8608120107
Download: ML20212C638 (3)


Text

.

MAIRE HARHEE AToml0 POWER 00MPARUe avaug,,Ka?n"e%'s (207) 623-3521 e

July 15, 1986 HN-86-92 GDH-86-171 l

Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Hurley, Regional Administrator

References:

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

Subject:

Maine Yankee Technical Specification 3.2.C Gentlemen:

The following report on the primary coolant system iodine spike is submitted pursuant to Maine Yankee Technical Specification 3.2.C.

On June 12, 1986 at 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br />, the plant tripped when the #2 Excess Flow Check Valve inadvertently closed. At 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> on June 12, 1986, Dose Equivalent Iodine (DEI) activity exceeded 1.0 uCi/ gram and remained above this level until 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br /> on June 13, 1986.

The DEI activity, along with plant operating characteristics, and the fuel burnup by core region are presented in Tables 1 and 2, respectively.

Very truly yours, HAINE YANKEE ATOMIC P0HER COMPANY

) J J.9 W G. D. Whittier, Manager Nuclear Engineering and Licensing

/

GDH/plb Enclosure cc: Mr. Ashok C. Thadani Hr. Pat Sears Mr. Cornelius F. Holdr-7752L-GDH l

8608120107 860715 l

gDR ADOCK 05000309 l

PDR

[-

MAINE YANKEE ATOMIC POWER COMPANV o

TABLE 1.

Reactor Coolant System Dose Equivalent I-131 (DEI) Activity and Plant Operating Characteristics, June 10-13, 1986.

LETDOHN FLOH DEGASSIFIER D_ ATE II3E DEI (uCi/a) REACTOR P0HER(%)

RATE (aom)

OPERATION 06/10/86 1.10E-1,

99 80 0

06/11/86 1.17E-1 99 80 0

06/12/86 1003 1.01E-1 99 80 DA-1A 860 gal.

1320 0

80 DA-1B-1735 gal.

1510 2.35E0 0

124 1600 2.40E0 0

124 1705 2.31E0 0

124 1820 2.31E0 0

125 4

1930 2.09E0 0

124 2135 1.92E0 0

123 2330 1.56E0 0

124 06/13/86 0130 1.32E0 0

125 0325 1.07E0 0

123 0525 9.07E-1 0

124 7752L-GDH 2A l

MAINE YANKEE ATOMIC POWER COMPANV O

I TABLE 2.

Fuel Burnup By Core Region.

CYCLE BURNUP (MHD/MT)

TOTAL BURNUP (MHD/MT)

REGION-06/12/86 06/16/86 06/12/86 06/16/61 E16 5668 5668 26102 26102 LO 4773 4773 26099 26099 L4 6105 6105 33702 33702 L8 3990 3990-

-30478 30478 L12 5653 5653 34813 34813 2

M0 7466 7466 19365 19365 M4 6265 6265 19201 19201 M8 7189 7189 22660 22660 N0 6681 6681 6681 6681 i

N4 6437 6437 6437 6437 N8 7673 7673 7673 7673 Core 6227 6227 19453 19453 1

1 l

7752L-GDH

-..