ML20148L340

Reg Guide 1.16 Man-Rem Final End of Yr Rept for 1996. W/

ML20148L340
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1996
From:	Hebert J Maine Yankee
To:	Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RTR-NUREG-01.016, RTR-NUREG-1.016 JRH-97-161, MN-97-77, NUDOCS 9706190219
Download: ML20148L340 (9)

Text

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e MaineYankee AELI ABLE ELECTRICITY SINCE 1972 329 BATH ROAD BRUNSWICK. MAINE 04011 * (207) 798-4100 June 12,1997 MN-97-77 JRH-97-161 Region i UNITED STATES NUCLEAR REGULATORY COMMISSION .

475 Allendale Road K!ng of Prussia, PA 19406 Attention: Mr. Hubert Miller, Regional Administrator

Reference:

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

Subject:

Annual Personnel Exposure Report - 1996 Gentlemen:  ;

Enclosed is the Maine Yankcc Annuc! Report for 1996 submitted in accordance with Technical Specification 5.9.1.3 A and 5.9.1.3 B.

I trust you find this report acceptable; however, should you have any questions, please contact me.

Very truly yours, )

m k, S "

IJames R. Hebert, Manager p l l Regulatory Affairs Department j l Enclosure c: Mr. J. T. Yerokun I Mr. Daniel H. Dorman l l Mr. Patrick J. Dostie '

Document Control Desk ,

American Nuclear Insurers Mr. Clough Toppan, DHE Mr. Uldis Vanags 9706190219 961231 '

PDR ADOCK 05000309 R PDR- l ll l!b,lllll,!!l !lil L:\97mn\9777.wpd

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a ANNUAL REPORT

, 5.9.1.3 Annual Reports covering activities as described below for the previous l calendar year shallinclude:

A. A tabulation on an annual basis of the number of station, utility and eihor personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure l

according to work and job functions,

• e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special l

maintenance (describe maintenance), waste processing, and refutiling.

The dose assignment to various duty functions may be estimates beced on pocket dosimeter, TLD, or film badge measurements.

Small exposures totaling less than 20% of the individual total dose l

need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from extemal sources shall be l assigned to specific major work functions.

• This tabulation supplements the requirement of Section 20.407 of 10 CFR Part 20.

Response: Attached please find a table," Maine Yankee Atomic Power Company Reg. Guide 1.16, Man-Rem Final End of the Year Report for 1996".

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• . MA!NE YANKEE ATOMIC POWER COMPANY

• REG. QUIDE 1.16 MAN REM FINAL END OF THE YEAR REPORT FOR 1996

• NUMOER OF PERSONNEL OVER 100 MREM TOTAL MAN. REM a

STATION UTILITY CONTRACT WORKERS STATION UTILITY CONTRACT WORKERS EMPLOYEES EMPLOYEES AND OTHERS EMPLOYEES EMPLOYEES AND OTHERS REACTOR OPS / SURVEILLANCE ,

I MAINTENANCE O O O 0.242 0.000 0.359 OPERAT!0NS 0 0 0 0.072 0.000 0.048 NEALTH PHYSICS 0 0 0 0.040 0.000 0.015

$UPERvlSORY 0 0 0 0.020 0.000 0.329 ENGINEERING 1 0 0 1.835 0.000 0.000 ROUTINE MAINTENANCE MAINTENANCE 30 0 37 8.141 0.000 10.086 ,

OPERATIONS 28 0 3 9.405 0.000 1.C23 l NEALTH PHYSICS 16 0 37 3.686 0.000 13.530 ,

SUPERVISORY 2 0 2 0.718 0.000 0.634 i ENGINEERING 8 0 1 2.870 0.000 0.675 ,

i IN SERVICE INSPECTION MAINTENANCE O 0 0 0.000 0.000 0.000 t OPERATIONS 0 0 0 0.000 0.000 0.000  ;

HEALTH PHYSICS 0 0 0 0.000 0.000 0.000  ;

SUPERVISORY 0 0 0 0.000 0.000 0.000  !

ENGINEERING 0 0 0 0.012 0.000 0.051 SPECIAL MAINTENANCE MAINTENANCE 2 0 16 1.147 0.000 4.336 OPERATIONS 0 0 0 0.243 0.000 0.122 HEALTH PHYSICS 1 0 5 0.734 0.000 1.227  :

0.877 I SUPERVISORY 0 0 4 0.010 0.000 ENGlWEERING 0 0 4 0.152 0.000 0.881 1 1

• WASTE PROCESSING i

MAINTENANCE 0 0 0 0.000 0.000 0.000 l

OPERATIONS 0 0 0 0.000 0.000 0.000 l

HEALTH PHYSICS 0 0 0 0.000 0.000 0.000 SUPERV!SCRY 0 0 0 0.000 0.000 0.000 0 0 0 0.000 0.000 0.000 ENGINEERING l

REFUELING O 0 0 0.050 0.000 0.010 MAINTENANCE 0 0 0 0.000 0.000 0.000 l l OPERATIONS l 0 0 0 0.000 0.000 0.000 l HEALTH PHYSICS 0 0 0 0.000 0.000 0.005 )

SUPERVISORY 0 0 0 0.000 0.000 0.000 l ENGINEERING l 1

e TOTALS 32 0 53 9.580 0.000 14.791 MAINTENANCE 28 0 3 9.720 0.000 1.193 OPERATIONS 17 0 42 4.460 0.000 14.772 HEALTH PHYSICS 2 0 6 0.748 0.000 1.845 SUPFf d SORY 9 0 5 4.869 0.000 1.607 i ENGR M GNG 1

88 0 109 29.377 0.000 34.208 GRAND TOTAL Approved by : - - ~ ~ ~ - - - - "

Radiation Protection Manager Date I

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ANNUAL REPORT 5.9.1.3 B. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.2. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior

! to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

Response: See Attached i

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Itadioiodine Concentrations for October 09,1996, ReactorTrip -

Radiciodine Activity (pCi/g) Letdown i Reactor Flow Rate Date Time 1-131 1-132 1-133 1-134 1-135 DEI l'ower ,

GPM 10/9/96 0736 5.03c-03 3.02e-02 2.32e-02 5.0le-02 3.36c-02 1.60c-02 90 95 .

0950 Trip 1050 6.23e-02 6.78e-02 8.12e-02 5.22e-02 6.79e-02 9.32e-02 0 95 I150 1.29c-01 8.86c-02 1.25e-01 3.18e-02 8.45e-02 1.74e-01 0 95 1250 1.40c-01 8.15e-02 1.35c-01 1.75e-02 7.73e-02 1.86e-01 0 94 1355 1.36c-01 7.65c-02 1.27c-01 8.49e-03 6.94e-02 1.79e-01 0 94 1450 1.30c-01 7.00e-02 1.1Se-01 4.57c-03 5.9Ie-02 1.68e-01 0 94 1620 1.2 i e-D I 6.48e-02 1.02e-01 1.48e-03 4.8 I e-02 1.55e-01 0 95 1720 1.13c-01 5.87e-02 9.15e-02 4.08e-02 1.44e-01 0 95 ,

1900 1.03c-01 5.20c-02 7.90c-02 3.08e-02 1.29c-01 0 95 2200 8.92c-02 4.68c-02 6.66e-02 2.04e-02 1.1 t e-01 0 93 10/10/96 0200 6.49e-02 3.83c f)2 4.62e-02 1.04e-02 7.96e-02 0 110 0606 5.08c-02 3.66c-02 3.23c-02 5.26c-03 6.12e-02 0 l10 1

Reactor had been at 90% power for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the trip. Dose equivalent 1-131 exceeded 0.1 uCi/g for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and 10 minutes.

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Radioiodine Concentrations for December 05,1996, Shutdown -

Radiciodine Activity (pCi/g) Letdown Reactor Flow Rate Date Time 1-135 DEg Power GPM I-131 1-132 1-133 1-134 ,

i2/5/96 0124 1.43c-02 3.51c-02 3.50c-02 5.68c-02 4.2 ie-02 2.95e-02 90 112 2145 Commence Shutdown 12/6/96 0055 3.7 I c-02 6.2 I c-02 6.83c-02 4.90e-02 6.19e-02 630e-02 mt 15%/hr 125 0127 7.45c-02 1.I I c-01 1.19c-01 5.80e-02 9.57e-02 1.20e-01 125 0138 1.22c-01 1.54c-01 1.75e-01 6.09e-02 1.23e-01 1.86e-01 125 0152 1.75c-01 2.03c-01 2.15c-01 6.59e-02 1.50c-01 2.54e-01 125 0204 2.15c-01 2.33c-01 2.63c-01 6.66c-02 1.69e-01 3.10e-01 125 ,

0220 2.38c-01 2.45c-01 2.82c-01 5.98e-02 1.82e-01 3.40e-01 125 0545 3.25c-UI 2.13c-01 3.31 c-01 1.59e-01 4.35e-01 120 0945 2.59c-01 1.66c-01 2.37c-01 8.59e-02 3.37e-01 132 1350 1.90e-01 1.31c-01 1.55c-01 4.34e-02 2.4 ie-01 125 1625 1.72c-01 1.29c-01 1.36c-01 2.81e-02 2.15c-01 126 2015 1.42c-01 1.13c-01 1.00c-01 1.61e-02 1.75e-01 125 t

0030 1.17c-01 1.l le-01 7.21c-02 8.81e-03 1.41e-01 123 12/7/96 0435 9. loc-02 9.91c-02 4.91c-02 1.08e-01 123 0845 7.18c-02 9.56e-02 3.32c-02 2.13e-03 8.43c-02 130 1234 6.76c-02 9.31 c-02 2.93c-02 7.88e-02 128 Iteactor had been at 90% power for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> belbre the shutdown. Dose equivalent 1-131 exceeded 0.1 uCi/g for 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> and 8 minutes.

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