ML17261B096: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 15: Line 15:
| page count = 4
| page count = 4
}}
}}
See also: [[followed by::IR 05000244/1990007]]


=Text=
=Text=
{{#Wiki_filter:,II~Pir ng IS II WPII A h lI'h'IhIIJIIIfl$
{{#Wiki_filter:,II~Pir ng IS II WPII A h lI'h'IhIIJIIIfl$
$/II PZilhiIIll~i,III
$/II PZilhiIIll~i,III ROCHESTER GAS AND ELECTRIC CORPORATION RSR'~V~~//I',h"'SOahI SSAIS~89 EAST AVENUE, ROCHESTER, N.Y.14649-0001
ROCHESTER GAS AND ELECTRIC CORPORATION
>CLCRIhOIIC ARCA CODC VIS 546.2700 May 29, 1990 Thomas T.Martin Regional Administrator U.S.Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406  
RSR'~V~~//I',h"'SOahI SSAIS~89 EAST AVENUE, ROCHESTER, N.Y.14649-0001
 
>CLCRIhOIIC
==Dear Mr.Martin:==
ARCA CODC VIS 546.2700 May 29, 1990 Thomas T.Martin Regional Administrator
Routine Inspection Report 50-244/90-07, Appendix A, stated in part: Oa's a result of the inspection conducted on April 16 to 20, 1990, and in accordance with the NRC Enforcement Policy (10 CFR 2,...,Appendix.,C),,,,the,.follows,ng violation...was identi.ied:I"<'"-
U.S.Nuclear Regulatory
h V h I'h~~~h iV~"h"~Technical Specification 6.11, Radiation Protection Program, states, in part, that"Radiation control procedures shall be prepared=and made available to all station personnel or other persons who may be subject to radiation exposure at the station.The program shall be adhered to for all operations involving personnel radiation exposure." Radiation Protection Procedure HP-1.2,"External Exposure Limits", states in Section 6.2.4'.2 that.personnel having a completed Form NRC-4 shall be administratively limited to 2000 mRem per calendar quarter.Contrary to the above, on March 24, 1990, an individual with 1672 mRem of occupational exposure for the first calendar quarter of 1990 was given an administrative dose limit of 1973 mRem for the first calendar quarter of 1990.This resulted in the individual's exposure being administratively limited to 3645 mRem for the first calendar quarter of 1990.Rochester Gas&Electric Corporation agrees with the violation as stated.1.Cause of Violation a.The root cause of the violation was personnel error.2.Event Description
Commission
Region 1 475 Allendale Road King of Prussia, PA 19406 Dear Mr.Martin: Routine Inspection
Report 50-244/90-07, Appendix A, stated in part: Oa's a result of the inspection
conducted on April 16 to 20, 1990, and in accordance
with the NRC Enforcement
Policy (10 CFR 2,...,Appendix.,C),,,,the,.follows,ng
violation...was
identi.ied:I"<'"-
h V h I'h~~~h iV~"h"~Technical Specification
6.11, Radiation Protection
Program, states, in part, that"Radiation
control procedures
shall be prepared=and made available to all station personnel or other persons who may be subject to radiation exposure at the station.The program shall be adhered to for all operations
involving personnel radiation exposure." Radiation Protection
Procedure HP-1.2,"External Exposure Limits", states in Section 6.2.4'.2 that.personnel having a completed Form NRC-4 shall be administratively
limited to 2000 mRem per calendar quarter.Contrary to the above, on March 24, 1990, an individual
with 1672 mRem of occupational
exposure for the first calendar quarter of 1990 was given an administrative
dose limit of 1973 mRem for the first calendar quarter of 1990.This resulted in the individual's
exposure being administratively
limited to 3645 mRem for the first calendar quarter of 1990.Rochester Gas&Electric Corporation
agrees with the violation as stated.1.Cause of Violation a.The root cause of the violation was personnel error.2.Event Description
~007200 1 92 90s)70I=, s-'De ADDGk 0 0(i(>24r>9 PDI., Q  
~007200 1 92 90s)70I=, s-'De ADDGk 0 0(i(>24r>9 PDI., Q  
 
Incoming personnel are required to provide documentation
Incoming personnel are required to provide documentation of current quarterly exposure along with other past exposure data in order to obtain a TLD for work in radiologically controlled areas at Ginna.Procedure HP-1.2 requires processing historical dose data into the RDMS system (a computerized dose tracking system)on two separate screens.In the case in question, the worker had both a record dose (1645 mRem rather than 1672 mRem as reported in the inspec-tion report)and an estimated dose (10 mRem).On one.screen, both doses were properly entered, on the second screen (which was used to produce the Form 4), only the 10 mRem estimated dose was entered.The Form 4 attachment letter produced was then reviewed by the worker who signed the document as being accurate.The information from the Form 4 was then used to determine the workers administrative dose limit of 2000 mRem as described in the violation.
of current quarterly exposure along with other past exposure data in order to obtain a TLD for work in radiologically
3.Corrective Actions When this, error was determined, the'worker's"records"were immediately, corrected.
controlled
The worker'eceived no'signi-'icant exposure for the time while the error occurred.b.The records for all workers processed in from January 1, 1990 until the date of discovery of the error were confirmed accurate.No further errors were discovered.
areas at Ginna.Procedure HP-1.2 requires processing
C.Rochester Gas and Electric has since instituted the following corrective action.All NRC Form 4 dose histories for the quarter will be totaled by one dosimetry clerk and any estimated doses will be added to the of f icial record.The maximum quarterly dose allowed will be 1000 mRem, when estimated doses are included, minus this total.These calculations will then be checked by.either an additional dosimetry clerk or HP technician, and signed off as such prior to being made official.This value will then be up-dated when the official records for the quarter are made available.
historical
The worker's quarterly limit will also then be updated.d.In addition to this, the following longer term corrective actions are planned to the dosimetry software: 1)Automatically total all the dose histories of an individual (yearly, quarterly, lifetime).
dose data into the RDMS system (a computerized
2)Improve the data input sequence.
dose tracking system)on two separate screens.In the case in question, the worker had both a record dose (1645 mRem rather than 1672 mRem as reported in the inspec-tion report)and an estimated dose (10 mRem).On one.screen, both doses were properly entered, on the second screen (which was used to produce the Form 4), only the 10 mRem estimated dose was entered.The Form 4 attachment
3)4)Add any'estimated doses for a quarter to the official records and calculate the administrative limit.Correct the quarterly limit when official records are available.
letter produced was then reviewed by the worker who signed the document as being accurate.The information
These upgrades are anticipated to be completed by January 1, 1991.We are currently in full compliance.
from the Form 4 was then used to determine the workers administrative
Very truly yours, Robert C.M cr Division Manager Nuclear Production XC: U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Ginna USNRC Senior Resident Inspector Ronald R.Bellamy, Chief Facilities Radiological Safety and Safeguards Branch U.S.Nuclear Regulatory Commission Region 1.475 Allendale Road King of Prussia, PA 19406}}
dose limit of 2000 mRem as described in the violation.
3.Corrective
Actions When this, error was determined, the'worker's"records"were
immediately, corrected.
The worker'eceived no'signi-'icant
exposure for the time while the error occurred.b.The records for all workers processed in from January 1, 1990 until the date of discovery of the error were confirmed accurate.No further errors were discovered.
C.Rochester Gas and Electric has since instituted
the following corrective
action.All NRC Form 4 dose histories for the quarter will be totaled by one dosimetry clerk and any estimated doses will be added to the of f icial record.The maximum quarterly dose allowed will be 1000 mRem, when estimated doses are included, minus this total.These calculations
will then be checked by.either an additional
dosimetry clerk or HP technician, and signed off as such prior to being made official.This value will then be up-dated when the official records for the quarter are made available.
The worker's quarterly limit will also then be updated.d.In addition to this, the following longer term corrective
actions are planned to the dosimetry software: 1)Automatically
total all the dose histories of an individual (yearly, quarterly, lifetime).
2)Improve the data input sequence.  
3)4)Add any'estimated
doses for a quarter to the official records and calculate the administrative
limit.Correct the quarterly limit when official records are available.
These upgrades are anticipated
to be completed by January 1, 1991.We are currently in full compliance.
Very truly yours, Robert C.M cr Division Manager Nuclear Production
XC: U.S.Nuclear Regulatory
Commission
Document Control Desk Washington, DC 20555 Ginna USNRC Senior Resident Inspector Ronald R.Bellamy, Chief Facilities
Radiological
Safety and Safeguards
Branch U.S.Nuclear Regulatory
Commission
Region 1.475 Allendale Road King of Prussia, PA 19406
}}

Revision as of 14:38, 17 August 2019

Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred
ML17261B096
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/29/1990
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Martin T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17261B095 List:
References
NUDOCS 9007200191
Download: ML17261B096 (4)


Text

,II~Pir ng IS II WPII A h lI'h'IhIIJIIIfl$

$/II PZilhiIIll~i,III ROCHESTER GAS AND ELECTRIC CORPORATION RSR'~V~~//I',h"'SOahI SSAIS~89 EAST AVENUE, ROCHESTER, N.Y.14649-0001

>CLCRIhOIIC ARCA CODC VIS 546.2700 May 29, 1990 Thomas T.Martin Regional Administrator U.S.Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406

Dear Mr.Martin:

Routine Inspection Report 50-244/90-07, Appendix A, stated in part: Oa's a result of the inspection conducted on April 16 to 20, 1990, and in accordance with the NRC Enforcement Policy (10 CFR 2,...,Appendix.,C),,,,the,.follows,ng violation...was identi.ied:I"<'"-

h V h I'h~~~h iV~"h"~Technical Specification 6.11, Radiation Protection Program, states, in part, that"Radiation control procedures shall be prepared=and made available to all station personnel or other persons who may be subject to radiation exposure at the station.The program shall be adhered to for all operations involving personnel radiation exposure." Radiation Protection Procedure HP-1.2,"External Exposure Limits", states in Section 6.2.4'.2 that.personnel having a completed Form NRC-4 shall be administratively limited to 2000 mRem per calendar quarter.Contrary to the above, on March 24, 1990, an individual with 1672 mRem of occupational exposure for the first calendar quarter of 1990 was given an administrative dose limit of 1973 mRem for the first calendar quarter of 1990.This resulted in the individual's exposure being administratively limited to 3645 mRem for the first calendar quarter of 1990.Rochester Gas&Electric Corporation agrees with the violation as stated.1.Cause of Violation a.The root cause of the violation was personnel error.2.Event Description

~007200 1 92 90s)70I=, s-'De ADDGk 0 0(i(>24r>9 PDI., Q

Incoming personnel are required to provide documentation of current quarterly exposure along with other past exposure data in order to obtain a TLD for work in radiologically controlled areas at Ginna.Procedure HP-1.2 requires processing historical dose data into the RDMS system (a computerized dose tracking system)on two separate screens.In the case in question, the worker had both a record dose (1645 mRem rather than 1672 mRem as reported in the inspec-tion report)and an estimated dose (10 mRem).On one.screen, both doses were properly entered, on the second screen (which was used to produce the Form 4), only the 10 mRem estimated dose was entered.The Form 4 attachment letter produced was then reviewed by the worker who signed the document as being accurate.The information from the Form 4 was then used to determine the workers administrative dose limit of 2000 mRem as described in the violation.

3.Corrective Actions When this, error was determined, the'worker's"records"were immediately, corrected.

The worker'eceived no'signi-'icant exposure for the time while the error occurred.b.The records for all workers processed in from January 1, 1990 until the date of discovery of the error were confirmed accurate.No further errors were discovered.

C.Rochester Gas and Electric has since instituted the following corrective action.All NRC Form 4 dose histories for the quarter will be totaled by one dosimetry clerk and any estimated doses will be added to the of f icial record.The maximum quarterly dose allowed will be 1000 mRem, when estimated doses are included, minus this total.These calculations will then be checked by.either an additional dosimetry clerk or HP technician, and signed off as such prior to being made official.This value will then be up-dated when the official records for the quarter are made available.

The worker's quarterly limit will also then be updated.d.In addition to this, the following longer term corrective actions are planned to the dosimetry software: 1)Automatically total all the dose histories of an individual (yearly, quarterly, lifetime).

2)Improve the data input sequence.

3)4)Add any'estimated doses for a quarter to the official records and calculate the administrative limit.Correct the quarterly limit when official records are available.

These upgrades are anticipated to be completed by January 1, 1991.We are currently in full compliance.

Very truly yours, Robert C.M cr Division Manager Nuclear Production XC: U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Ginna USNRC Senior Resident Inspector Ronald R.Bellamy, Chief Facilities Radiological Safety and Safeguards Branch U.S.Nuclear Regulatory Commission Region 1.475 Allendale Road King of Prussia, PA 19406