ML20064H886

1993 Personnel Exposure Rept

ML20064H886
Person / Time
Site:	Vermont Yankee
Issue date:	12/31/1993
From:	Tremblay L VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-94-22, NUDOCS 9403180191
Download: ML20064H886 (4)

Text

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j V8RMONT YANKEE NUC, LEAR POWER CORPORATION s Ferry Road, Brattleboro, VT 05301-7002 yf'j ENGINE IN OFFICE M* '"i 580 M AIN STREE T BOLTON MA 01740 l

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< sari) 779-67 i ,

February 18,1994 BVY 94 - 22 l

l United States Nuclear Regulatory Commission ATrN: Document Control Desk Washington, DC 20555 l

References:

a. License No. DPR-28 (Docket No. 50-271)

Subject:

1993 Personnel Exposure Report l

Enclosed please find one copy of the Vermont Yankee " Reg. Guide 1.16 Man Rem Final End of the Year Report for 1993", an annual report required by Section 6.7.A.2 of our Technical Specifications. This report covers the period beginning January 1,1993 and ending December 31, 1993.

We trust this report is acceptable; however, should you have any questions, please contact this office. 4 1

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Sincerely, j VERMONT YANKEE NUCLEAR POWER CORPORATION j t mNC b ,O m f.

t Leonard A. Tremblay, Jr., P.E. '

Senior Licensing Engineer cc: USNRC Region I Administrator USNRC Resident Inspector- VYNPS i--

USNRC Project Manager- VYNPS i

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9403180191 931231 ' '

l PDR ADOCK 05000271 R pop _; /

Vermont Yaries Nuclotr Power Corp. )

j REO. Gul0E 1.16 MAN REM FINAL END OF THE YEAR PEPORI FOR 1993 )

NUMBER OF PERSONNEL OVER 100 MREM TOTAL MAN REM STATION UTILITY CONTRACT WORKERS STATION UTILITY CONTRACT WORKERS EMPLOYEES EMPLOYEES AND OTHER$ EMPLOYEES EMPLOYEES AND OTHEt$

REACTOR OPERAil0NS & SURVEILLANCE MAINilNANCE 13 0 31 3.692 0.000 14.349 OPERATIONS 31 0 1 8.742 0.000 0.330 HEALTH PHYSICS 15 0 13 4.714 0.000 5.076 i

SUPERVISORY 1 0 0 0.179 0.000 0.110 ENGINEERING 0 0 0 0.300 0.015 0.066 OTHER 2 0 0 0.388 0.000 0.053 SECURITY 0 0 0 0.425 0.000 0.449 i l

ROUTINE MAINTENANCE MAINTENANCE 33 0 190 12.017 0.000 66.779 l OPERATIONS 21 0 1 5.290 0.000 0.338 '

HEALTH PHYSICS 8 0 26 3.141 0.000 12.144 SUPERVISORY 1 0 0 0.403 0.000 0.123 l EXGlNEERING 2 0 1 0.425 0.002 0.196 OTHER 3 0 0 1.478 0.000 0.185 SECURITY 0 0 0 0.177 0.000 0.104 INSERVICE INSPECTION MAIN!ENANCE O 0 39 0.018 0.000 12.639 OPERATIONS 4 0 0 1.222 0.000 0.000 HEALTH PHYSICS 0 0 0 0.000 0.000 0.027 SUPERVISORY 0 0 0 0.000 0.000 0.032 ENGINEERING 0 0 0 0.041 0.000 0.000 OTHER 0 0 1 0.000 0.000 0.248 SECURITY 0 0 0 0,000 0.000 0.000 SPECIAL MAINTENANCE i MAINTENANCE 9 0 138 3.206 0.000 40.419 OPERATIONS 0 0 0 0.277 0.000 0.000 HEALTH PHYSICS 3 0 7 0.594 0.000 1.692 SUPERv!sORY 0 0 0 0.004 0.000 0.004 ENGINEERING 0 0 0 0.024 0.034 0.002 OTHER 0 0 0 0.111 0.000 0.005 SECURITY 0 0 0 0.000 0.000 0.000  ;

WASTE PROCESSING i KAINTENANCE O O O 0.000 0.000 0.000 OPERAT10N$ 0 0 0 0.000 0.000 0.000 HEALTH PHYSICS 1 0 1 0.130 0.000 0.121 SUPERVISORY 0 0 0 0.000 0.000 0.000 ENGINEERING 0 0 0 0.000 0.000 0.000 OTHER 0 0 0 0.000 0.000 0.000 SECURITY 0 0 0 0.000 0.000 0.000 l

.l REFUELING  !

MAINTENANCE O O O 0.132 0.000 0.971  !

OPERAil0NS 0 0 0 0.612 0,000 0.031 HEALTH PHYSICS 0 0 0 0.018 0.000 0.040 .)

SUPERVISORY 0 0 0 0.000 0.000 0.000 ENGINEERING 0 0 0 0.105 0.000 0.000 OTHER 0 0 0 0.012 0.000 0.000 SECURITY 0 0 0 0.000. 0.000 0.000 l

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MA!NTENANCE 55 0 398 19.06F 0.000 135.157 CPERATIONS 56 0 2 16.143 0.000 0.699 MEALTH PHYSICS 27 0 47 8.596 .0.000 19.100 SUPERVISORY 2 0 0 0.586 0.000 0.269 ENGINEERING 2 0 1 0.898 0.051 0.265 OTWER 5 0 1 1.988 0.000 0.491 SECURITY 0 0 0 0.602 0.000 0.553 GRAND TOT AL 147 0 449 47.878 0.051 156.534 Approved by : 'd ------- - AT =7 N- -

Radiation P.'otection Manager Oste

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The following is a list of the special maintenance that was performed in 1993 at Vermont

> Nokee:

.e Reference Leg Back fill The NRC directed that all BWRs implement hardware modifications to satisfy a regulatory concern pertaining to the accumulation of non-condensable gases in the -

reactor vessel refeience legs which could result in erroneous level indications. This work was completed during out 1993 re-fueling outage.

LYN-831 Fuel Bundle Re,overy During removal v. m i usembly LYN-831, it was dropped into the reactor core. It was estimated the bundle fell 8 feet and stopped when it came into contact with the Fuel Support Casting in its original location 21-14. This event occurred during the 1993 re-fueling outage. The work entailed numerous inspections to ensure no damage had occurred to the reactor vessel internals.

Replace RllRSW valves V-10-89 A&B These valves are the RilR heat exchanger flow control valves. Excess vibration caused damaged to the valves. The valves were determined to be oversized and were replaced during the 1993 re-fueling outage.

RHR IIx Inspection This work entailed eddy current testing of the two RHR A&B heat exchangers As a result of the inspections some tubes wcre required to be plugged, In addition, damage to the impingement plates was evident and they were repaired. This work was completed during the 1993 re-fueling outage.

Crossaroung Pipe Replacement This replacement was performect during the 1993 re-fueling outage. The piping was replaced because the interior surfaces sustained steam erosion damage.

SJAE Nozzle Replacement As a result of the bursting of a rupture disc located on the AOG 100 line it was decided that one of the possible contributing factors for the disc ruptures was the erosion of the SJAE nozzles. The nozzles were replaced during the 1993 re-fueling outage.

IST Modifications The purpose of this modific* ion was to replace exiting valves and gauges with improved models. This work was cot. ,.:eted during the 1993 re-fueling outage.

RECEtVED n

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