ML19224B259

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Health Physics Procedure 1624,Revision 2:radioactive Control Procedure During New Fuel Handling & Refueling
ML19224B259
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/08/1977
From:
Metropolitan Edison Co
To: Mullinix W
NRC/IE
References
1624.2, TM-0089, TM-89, NUDOCS 7906140305
Download: ML19224B259 (8)
v • d • e


Text

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THI DOCUMENTS f /f ~h f h DOCUMENT NO:

COPY MADE ON OF DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.

Wilda R. Mullinix, NRC 7906140305

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C0FTRD'1ED COPY 1624.2 Revision 2 MAS ~. il COPY o6/o8/77 JO NOT REMOV(ATION REE W ISLAN NUCLEAR SWlON HEALTH PHYSICS PROCEDURE '1624.2 RADIATI0fl CONTROL PROCEDURES DURIrlG flew FUEL HAtlDLIflG AtlD REFUELItiG Tab e of fec ve Pages Pace Date R evision Pane Date Revision Page Date R evisicc 1.0 06/08/77 2

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Date Approval M

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Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recomme ds Approval Nh Yf 4

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Date Chairman of PORC ChairInan of PW PORC comments of included PORC comments -f included (date)

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  1. StaIson Superintender. I f9}~0 W^"~"

Unit Superintendent

1624.2 Revision 2 06/08/77 THREE tilLE ISLAND flVCLEAR STATION STATION HEALTH PHYSICS PROCEDURE 1624.2 Radiation Control Procedures During tiew Fuel Handling and Refueling Unit 2 1.0 PURPOSE The purpose of this procedure is to define the radiological procedures which will be used for new fuel handling and refueling operations.

2.0 DISCUSSION Safe levels of radiation will be assured in the fuel handling and reactor buildings during new fuel and refueling operations using personnel dosimetry and the area radiation monitors located in the respective building. Additional radiological controls specified in the Radiation Protection Manual sill also be follcwed.

3.0 REFERENCES

3.1 Three Mile Island Radiation Protection Manual.

3.2 H.P.P. 1640 3.3 H.P.P. 1641 3.4 2105-1.12 3.5 2501-6.2 3.6 2501-6.1 4.0 EQUIPMENT 4.1 Fila. Badge.

4.2 T.L.D.

4.3 Self Reading Dosimeter.

4.4 Portable Area Monitor.

4.5 Neutron Accident Dosimeters.

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1624.2 Revision 2 06/08/77 4.6 R.M.S. HP-R-223.

4.7 Beta-Gamma Survey Meter.

5.0 OPERATIti3 INSTRUCTI0tlS 5.1 Special Radiological Control Requirements for New Fuel Operations.

5.1.1 All personnel entering the local controlled areas in the fuel handling building shall wear a film badge /TLD and a self reading dosimeter.

The handling and processing of data from these instruments shall be in accordance with Health Physics Procedures, HPP 1640 and HPP 1641.

5.1.2 An area gamma monitor near the spent fuel handling bridge shall be in operation when fuel is in the fuel storage building.

The alarm set points for this monitor shall be set as directed by the Radiation Protection Supervisor / Foreman.

5.1.3 An area gamma monitor, similar to a Victoreen VAMP monitor, shall be located near the area where the fuel shipping containers are opened.

The alarm set points for this monitor shall be set as directed by the Radiation Protecuon Supervisor / Foreman.

5.1.4 Four neutron accident dosimeters shall be located in the fuel handling building.

These dosimeters are solely for information purposes and need not be monitored during operation.

5.1.5 The Spent Fuel Air Monitor HP-R-223 or equivalent shall be in operation near the fuel inspection stand.

The alarm set points for this monitor shall be in accordance with 2105-1.12

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" Radiation Monitoring System Setpoints".

If HP-R-223 or equivalent is out of service during fuel handling operations, air samples will be taken once per shift in the area of fuel handling operations.

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1624.2 Revision 2 06/03/77 5.2 Special Radiological Control Requirements for Refueling.

5.2.1 All personnel entering the local controlled area in the Reactor Building shall wear a film badge and/or Tt.D and a self reading dosimeter.

The handling and processing of data from these instruments shall be in accordance with Health Physics Procedures HPP 1640 and HPP 1641.

l 5.2.2 Area gamma monitors HP-R-214, HP-R-209, and HP-R-210 shall be in operation when Refueling Operations are in progress in the Reactor Building.

The alarm setpoints for the monitors shall be in accordance with 2105-1.12, " Radiation Monitoring System Setpoints".

5.2.3 The atmospheric Radiation Monitors, HP-R-227 and HP-R-219 shall be in operation when refueling cperations are in progress in the Reactor Building.

The alarm setpoints fcr the monitors shall be in accorditnce with 2105-1.12, " Radiation Monitoring System Setpoints".

5.3 Special Radiological Control Requirements for Unloading New Fuel Shipping Containers.

5.3.1 Prior to unloading the truck, perform a beta-gamma dose rate survey of the truck and fuel shipping container exterior by using an Eberline (E520) GM survey instrument or equivalent and record results on Form HPP 1624.2-1.

5.3.2 Also, before unloading the truck, perform a smear survey of

,I each shipping container (two (2) smears per container), and record results on Form HPP 1609 l.

NOTE:

Record the locations of smears taken on shipping containers on Form HPP 1624.2-2.

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1624.2 Revision 1 05/05/77 5.3.3 When shipping container top half is raised, take a beta-camma survey inside the shipping container along the fuel assembly.

Record results on Form HPP 1624.2-3.

5.3.4 Take a smear per fuel assembly (outside of poly covering) and record Beta Gamma and Alpha results on Form HPP 1609-1.

NOTE:

Record locations of smears taken on fuel assemblies on Form HPP 1624.2-3.

5.3.5 As soor, as the polyethylene cover at the top of the fuel assembly has been opened for verification of the correct fuel assembly number; take a smear of the top of the assembly.

Record the Beta Gamma and Alpha results of the smear on Form HPF 1609-1.

5.3.6 After poly covering is removed, take four (4) smears per fuel assembly and record Beta Gamma and Alpha results on Form HPP 1609-1,

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