ML20217N708

1997 Annual Rept of Primary Coolant Specific Activity

ML20217N708
Person / Time
Site:	Seabrook
Issue date:	12/31/1997
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AR#-97004828, NYN-98024, NUDOCS 9803090156
Download: ML20217N708 (5)

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1 North North Atlantic Energy Service Corporation yp3 Atlantic P.O. Box 300 Seahreet, xii O3874 (603) 474-952t The Northeast Utilities Systern February 27,1998 Docket No. 50-443 NYN-98024

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t AR# 97004828 United States Nuclear Regulatory Commission

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Attn.: Document Control Desk i

Washington, DC 20555-0001 Seabrook Station 1997 Annual Renort of Primary Coolant Soecific Activity Seabrook Station Technical Specification 6.8.1.2.b requires an annual report of primary coolant specific activity analyses which are required to be conducted if the limits of Technical Specification 3.4.8," Specific Activity" are exceeded in accordance with this requirement, North Atlantic Energy S:rvice Corporation hereby reports that one exceedance of Technical Specification 3.4.8, Primary Coolant Specific Activity Limits did occur on May 10,1997.The j

enclosed report provides the requested information as outlined in Technical Specification 6.8.1.2, Annual Reports.

Should you have any additional questions concerning this information, please contact Mr. Terry L. liarpster, Director of Licensing Services, at (603) 773-7765.

Very truly yours, NORTII ATLANTICENERGESERVICE CORP.

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C. FeigGiauni

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Executive Vice Pres tand Chief Nuclear Officer cc:

II. J. Miller, NRC Region I Administrator I

i C. W. Smith, NRC Project Manager R. K. Lorson, NRC Senior Resident inspector j3

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ENCLOSURE TO NYN-9802 8 i

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REACTOR COOLANT ANNUAL ACTIVITY REPORT (T.S. 3.4.8)

On 10-May-1997 at 02:45 a sample that exceeded the Dose Equivalent Jodine limit of 1.0 uCi/gm was obtained. A downpower for a refueling outage had commenced 9-May-1997 at 06.GO. On 10-May-1997 at 0215 a reactor trip occurred from 8 % Reactor power.

1)

Attachment I depicts, in graphical and tabular fonnat, Reactor Power starting on 8-May-1997 at 02:00.

The Reactor tripped on 10-May-1997 at 0215.

2)

The following Dose Equivalent Iodine values were obtained prior to, during and post the exceedance event.

9.60E-01 uCi/gm 10-May-199714:25 1.14E400 uCilgm 10-May-199712:30 1.06E+00 uCi/gm 10-May-199710:22 1.84E400 uCi/gm 10-May-1997 07:49 2.38E+00 uCi/gm 10-May-1997 04:30 1.78E+00 uCi/gm 10-May-1997 02:45 7.29E-02 uCi/gm 09-May-1997 20:00 3)

Attachment ' depicts, in graphical and tabular format, the purification clean-up flows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to i

and durinF radioiodine exceedance.

4)

The follow.. g graph depicts lodine-131 and Iodine-133 as a function of time during the radioiodine exceedance event.

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l-131,1-133 vs TIME l

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l 1.00E+01 i

1.00E+00 m-i

1. % -s l -+- l-131 l;

. uCilgm I

1.00E-01 [-

_a_ g 133, !

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1.00E-02 5/9/97 5/10/97 5/10/97 5/10/97 5/10/97 5/10/97 5/10/97 8 00 2.45 4:30 7.49 10-22 12:30 2.25 i

DATE/ TIME i

t-j 5)

The specific activity of the primary coolant exceeded the Dose Equivalent lodine limit of 1.0 uCi!gm i

for 11.7 hrs.

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ATTACllMENT I SE4 BROOK STATION REACTOR POWER lilSTORY 8-MAY-1997 MAY-1997 Date/ Time % Power Date/ Time % Power Date/ Time % Power 5/8 2:00 100 5/9 2:00 100 5/10 2:00 16 5/8 3:00 100 5/9 3.00 100 5/10 3:00 0

5/8 4:00 100 5/9 4:00 100 5/10 4:00 0

5/8 5:00 100 5/9 5:00 100 5/10 5:00 0

5/8 6:00 100 5/9 6:00 98 5/10 6:00 0

5/8 7:00 100 5/9 7:00 95 5/10 7:00 0

5/8 8:00 100 5/9 8:00 89 5/10 8:00 0

5/8 9:00 100 5/9 9:00 85 5/10 9:00 0

5/8 10:00 100 5/9 10:00 79 5/10 10:00 0

5/8 11:00 100 5/9 11:00 75 5/10 11:00 0

5/8 12:00 100 5/9 12:00 69 5/10 12:00 0

5/8 13:00 100 5/9 13:00 66 5/10 13:00 0

5/8 14:00 100 5/9 14:00 59 5/10 14:00 0

5/8 15:00 100 5/9 15:00 56 5/10 15:00 0

5/8 16:00 100 5/9 16:00 49 5/8 17:00 100 5/9 17:00 46 5/8 18:00 100 5/9 18:00 39 5/8 19:00 100 5/9 19:00 36 5/8 20:00 100 5/9 20:00 30 5/8 21:00 100 5/9 21:00 26 5/8 22:00 100 5/9 22:00 20 5/8 23:00 100 5/9 23:00 16 5/9 0:00 100 5/10 0:00 16 5/9 1:00 100 5/10 1:00 16 Seabrook Station % Reactor Power 100 90 80 70 60 50 40 30 20 II 9 -- ------

-==== =-- = -

O 5/8 5/8 5/8 5/8 5/8 5/8 5/9 5/9 5/9 5/9 5/9 5/9 5/10 5/10 5/10 5/10 2.00 6.00 10 00 14.00 18.00 22:00 2:00 6:00 10.00 14.00 18 00 22.00 2:00 6:00 10:00 14:00 A-1

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'ATTACllMENT 2 SEABROOK STATION HISTORICAL CLEAN-UP FLOW 5/8/97 - 5/10/97 Date/ Time. Clean-up Date/ Time Clean-up Date/ Time Clean-up Flow Flow Flow (gpm)

(gpm)

(gpm) 5/8 2:00 99 5/9 2:00 101 5/10 2:00 97 5/8 3:00 99.

5/9 3:00 100 5/10 3:00 99 5/8 4:00 99 5/9 4:00 101 5/10 4:00 99 5/8 5:00 98 5/9 5:00 99 5/10 5:00 100 5/8 6:00 98 5/9 6:00 100 5/10 6:00 100 5/8 7:00 99 5/9 7:00 99 5/10 7:00 99 5/8 8.00 98 5/9 8:00 99 5/10 8:00 99 5/8 9.00 100 5/9 9:00 99 5/10 9:00 49 5/8 10:00 100 5/9 10:00 99 5/10 10:00 99 5/8 11:00 100 5/9 11:00 99 5/10 11:00 99 5/8 12:00 100 5/9 12:00 99 5/10 12:00 100 5/8 13:00 100 5/9 13:00 99 5/10 13:00 105 5/8 14:00 101 5/9 14:00 99 5/10 14:00 104 5/8 15:00 101 5/9 15:00 99 5/10 15:00 00 5/8 16:00 100 5/9 16:00 99 5/8 17:00 100 5/9 17:00 99 5/8 18:00 100 5/9 18:00 99 5/8 19:00 100 5/9 19:00 99 5/8 20:00 100 5/9 20:00 98 5/8 21:00 100 5/9 21:00 98 5/8 22:00 101 5/9 22:00 98 5/8 23.00 100 5/9 23:00 97 5/9 0:00 101 5/10 0:00 96 5/9 1:00 101 5/10 1:00 97 12C..

100 l

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