RIS 2005-11, Requirements for Power Reactor Licensees in Possession of Devices Subject to the General License Requirements of 10 CFR 31.5: Difference between revisions

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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES
                              NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION
                  OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
                          OFFICE OF NUCLEAR REACTOR REGULATION
OFFICE OF NUCLEAR REACTOR REGULATION
                                  WASHINGTON, DC 20555-0001 July 11, 2005 NRC REGULATORY ISSUE SUMMARY 2005-11 REQUIREMENTS FOR POWER REACTOR LICENSEES IN
WASHINGTON, DC 20555-0001 July 11, 2005 NRC REGULATORY ISSUE SUMMARY 2005-11 REQUIREMENTS FOR POWER REACTOR LICENSEES IN
    POSSESSION OF DEVICES SUBJECT TO THE GENERAL LICENSE
POSSESSION OF DEVICES SUBJECT TO THE GENERAL LICENSE
                            REQUIREMENTS OF 10 CFR 31.5  
REQUIREMENTS OF 10 CFR 31.5  


==ADDRESSEES==
==ADDRESSEES==
Line 27: Line 27:
==INTENT==
==INTENT==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
to remind and/or inform addressees of the requirements for the receipt, possession, use, and transfer of generally licensed devices as described in 10 CFR 31.5 and 10 CFR 32.52. No specific action nor written response is required.
to remind and/or inform addressees of the requirements for the receipt, possession, use, and transfer of generally licensed devices as described in 10 CFR 31.5 and 10 CFR 32.52. No specific action nor written response is required.


==BACKGROUND==
==BACKGROUND==
Line 35: Line 35:
The licensee incorrectly assumed that these devices were not under the jurisdiction of NRC,
The licensee incorrectly assumed that these devices were not under the jurisdiction of NRC,
and therefore did not include them in its radiation protection program required by its 10 CFR
and therefore did not include them in its radiation protection program required by its 10 CFR
Part 50 license. Additionally, the licensee failed to include the devices in any program that would ensure they were maintained in accordance with regulatory requirements. Since the devices at issue are possessed and used as part of the operation of a production or utilization facility (i.e., the nuclear power plant), to comply with NRC requirements in 10 CFR 73.55, the NRC has exclusive jurisdiction over the byproduct material contained in these devices.
Part 50 license. Additionally, the licensee failed to include the devices in any program that would ensure they were maintained in accordance with regulatory requirements. Since the devices at issue are possessed and used as part of the operation of a production or utilization facility (i.e., the nuclear power plant), to comply with NRC requirements in 10 CFR 73.55, the NRC has exclusive jurisdiction over the byproduct material contained in these devices.


Accordingly, a violation of NRC requirements was identified in the above-mentioned inspection.
Accordingly, a violation of NRC requirements was identified in the above-mentioned inspection.
Line 42: Line 42:
All Part 50 licensees are required to comply with the regulations in 10 CFR 31.5, if they possess and use byproduct material contained in devices subject to general licenses to support the operation of their facilities.
All Part 50 licensees are required to comply with the regulations in 10 CFR 31.5, if they possess and use byproduct material contained in devices subject to general licenses to support the operation of their facilities.


Section 31.5 contains the regulatory requirements for issuing a general license to commercial and industrial firms to acquire, receive, possess, use, or transfer in accordance with the provisions in paragraphs (b), (c), and (d) of this section byproduct material contained in certain measuring, detecting, and gauging devices. Some key examples of these requirements are stated, in part, below:
Section 31.5 contains the regulatory requirements for issuing a general license to commercial and industrial firms to acquire, receive, possess, use, or transfer in accordance with the provisions in paragraphs (b), (c), and (d) of this section byproduct material contained in certain measuring, detecting, and gauging devices. Some key examples of these requirements are stated, in part, below:
        Section 31.5(c)(1) requires assuring that labels are affixed at the time of receipt and bear statements that removals of such labels are prohibited;
Section 31.5(c)(1) requires assuring that labels are affixed at the time of receipt and bear statements that removals of such labels are prohibited;
        Section 31.5(c)(2) requires assuring the devices are tested for leakage of radioactive material and proper operation of the on-off mechanisms and indicators, if any, at no longer than 6 month intervals, or at such other intervals as specified on the labels;
Section 31.5(c)(2) requires assuring the devices are tested for leakage of radioactive material and proper operation of the on-off mechanisms and indicators, if any, at no longer than 6 month intervals, or at such other intervals as specified on the labels;
        Section 31.5(c)(4) requires maintaining records showing compliance with testing requirements;
Section 31.5(c)(4) requires maintaining records showing compliance with testing requirements;
        Section 31.5(c)(12) requires appointment of an individual responsible for having knowledge of the appropriate regulations and requirements and the authority for taking required actions to ensure the day-to-day compliance with appropriate regulations.
Section 31.5(c)(12) requires appointment of an individual responsible for having knowledge of the appropriate regulations and requirements and the authority for taking required actions to ensure the day-to-day compliance with appropriate regulations.


Commercial power reactor licensees are hereby informed that generally licensed devices used to support reactor operations are under exclusive Federal jurisdiction and are subject to NRC
Commercial power reactor licensees are hereby informed that generally licensed devices used to support reactor operations are under exclusive Federal jurisdiction and are subject to NRC
inspections. Vendors are hereby informed that generally licensed devices transferred to power reactor licensees need to be reported in their NRC quarterly reports in accordance with 10 CFR
inspections. Vendors are hereby informed that generally licensed devices transferred to power reactor licensees need to be reported in their NRC quarterly reports in accordance with 10 CFR
32.52.
32.52.


Line 67: Line 67:
Please direct any questions about this matter to the technical contact(s) or the Lead Project Manager listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Please direct any questions about this matter to the technical contact(s) or the Lead Project Manager listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


/RA/                                                       /Original Signed by Patricia K. Holahan/
/RA/
Patrick L. Hiland, Chief                                   Charles L. Miller, Director Reactor Operations Branch                                 Division of Industrial and Division of Inspection Program Management                   Medical Nuclear Safety Office of Nuclear Reactor Regulation                       Office of Nuclear Material Safety and Safeguards Technical Contacts: Stephen P. Klementowicz, NRR           Anthony S. Kirkwood, NMSS
/Original Signed by Patricia K. Holahan/
                      (301) 415-1084                     (301) 415-6140
Patrick L. Hiland, Chief Charles L. Miller, Director Reactor Operations Branch Division of Industrial and Division of Inspection Program Management Medical Nuclear Safety Office of Nuclear Reactor Regulation Office of Nuclear Material Safety and Safeguards Technical Contacts:
                      E-mail: sxk@nrc.gov                 E-mail: ask@nrc.gov Attachment: List of Recently Issued NMSS Generic Communications Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
Stephen P. Klementowicz, NRR
Anthony S. Kirkwood, NMSS
(301) 415-1084
(301) 415-6140
E-mail: sxk@nrc.gov E-mail: ask@nrc.gov Attachment: List of Recently Issued NMSS Generic Communications Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.


===PAPERWORK REDUCTION ACT STATEMENT===
===PAPERWORK REDUCTION ACT STATEMENT===
Line 81: Line 85:
Please direct any questions about this matter to the technical contact(s) or the Lead Project Manager listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Please direct any questions about this matter to the technical contact(s) or the Lead Project Manager listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


/RA/                                                         /Original Signed by Patricia K. Holahan/
/RA/
Patrick L. Hiland, Chief                                     Charles L. Miller, Director Reactor Operations Branch                                   Division of Industrial and Division of Inspection Program Management                     Medical Nuclear Safety Office of Nuclear Reactor Regulation                         Office of Nuclear Material Safety and Safeguards Technical Contacts: Stephen P. Klementowicz, NRR             Anthony S. Kirkwood, NMSS
/Original Signed by Patricia K. Holahan/
                      (301) 415-1084                       (301) 415-6140
Patrick L. Hiland, Chief Charles L. Miller, Director Reactor Operations Branch Division of Industrial and Division of Inspection Program Management Medical Nuclear Safety Office of Nuclear Reactor Regulation Office of Nuclear Material Safety and Safeguards Technical Contacts:
                      E-mail: sxk@nrc.gov                   E-mail: ask@nrc.gov Attachment: List of Recently Issued NMSS Generic Communications Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
Stephen P. Klementowicz, NRR
Anthony S. Kirkwood, NMSS
(301) 415-1084
(301) 415-6140
E-mail: sxk@nrc.gov E-mail: ask@nrc.gov Attachment: List of Recently Issued NMSS Generic Communications Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.


DISTRIBUTION:         IMNS/ R/F             OES R/F
DISTRIBUTION:
ML051290143                                         *See previous concurrence OFFICE MSIB*             NMSS*             IMNS Gen. Coord. MSIB*                 IMNS*
IMNS/ R/F
NAME AKirkwood           EKraus             ICabrera               THarris         RCorreia DATE       5/9/05       5/11/05             7/05/05             5/19/05         5/25/05 OFFICE IMNS*             OSTP*             OGC*                   NRR*             NRR*
OES R/F
NAME JHickey             PLohaus           STreby/NLO             SKlementowicz TQuay DATE       5/23/05       6/02/05             6/23/05               5/31/05         5/31/05 OFFICE IMNS             NRR               NRR                   NRR
ML051290143  
NAME CMiller             AWMarkley         EJBenner               PLHiland DATE       07/06/05     7/08/05           7/08/05               7/11/05 OFFICIAL RECORD COPY
*See previous concurrence OFFICE MSIB*
NMSS*
IMNS Gen. Coord. MSIB*
IMNS*
NAME
AKirkwood EKraus ICabrera THarris RCorreia DATE
5/9/05
5/11/05
  7/05/05
5/19/05
5/25/05 OFFICE IMNS*
OSTP*
OGC*
NRR*
NRR*
NAME
JHickey PLohaus STreby/NLO
SKlementowicz TQuay DATE
5/23/05
6/02/05
6/23/05
5/31/05
5/31/05 OFFICE IMNS
NRR
NRR
NRR
NAME
CMiller AWMarkley EJBenner PLHiland DATE
07/06/05
7/08/05
7/08/05
7/11/05 OFFICIAL RECORD COPY


Attachment Recently Issued NMSS Generic Communications Date         GC No.               Subject                        
Attachment Recently Issued NMSS Generic Communications Date GC No.
 
Subject  


==Addressees==
==Addressees==
06/10/05     RIS-05-10   Performance-Based             All industrial radiography Approach for Associated       licensees and manufacturers and Equipment in 10 CFR 34.20     distributors of industrial radiography equipment.
06/10/05 RIS-05-10  
Performance-Based Approach for Associated Equipment in 10 CFR 34.20
All industrial radiography licensees and manufacturers and distributors of industrial radiography equipment.


04/18/05     RIS-05-06   Reporting Requirements for   All material licensees possessing Gauges Damaged at            portable gauges, regulated under Temporary Job Sites          10 CFR Part 30.
04/18/05 RIS-05-06 Reporting Requirements for Gauges Damaged at Temporary Job Sites All material licensees possessing portable gauges, regulated under
10 CFR Part 30.


04/14/05     RIS-05-04   Guidance on the Protection   All holders of operating licenses of Unattended Openings        or construction permits for nuclear that Intersect a Security    power reactors, research and test Boundary or Area              reactors, decommissioning reactors with fuel on site, Category 1 fuel cycle facilities, critical mass facilities, uranium conversion facility, independent spent fuel storage installations, gaseous diffusion plants, and certain other material licensees.
04/14/05 RIS-05-04 Guidance on the Protection of Unattended Openings that Intersect a Security Boundary or Area All holders of operating licenses or construction permits for nuclear power reactors, research and test reactors, decommissioning reactors with fuel on site, Category 1 fuel cycle facilities, critical mass facilities, uranium conversion facility, independent spent fuel storage installations, gaseous diffusion plants, and certain other material licensees.


6/23/05     IN-05-17   Manual Brachytherapy         All medical licensees authorized Source Jamming                to possess a Mick applicator.
6/23/05 IN-05-17 Manual Brachytherapy Source Jamming All medical licensees authorized to possess a Mick applicator.


05/17/05     IN-05-013   Potential Non-conservative   All licensees using the Keno-V.a Error in Modeling            criticality code module in Geometric Regions in the      Standardized Computer Analyses Keno-v.a Criticality Code    for Licensing Evaluation (SCALE)
05/17/05 IN-05-013 Potential Non-conservative Error in Modeling Geometric Regions in the Keno-v.a Criticality Code All licensees using the Keno-V.a criticality code module in Standardized Computer Analyses for Licensing Evaluation (SCALE)
                                                          software developed by Oak Ridge National Laboratory (ORNL)
software developed by Oak Ridge National Laboratory (ORNL)
  05/17/05     IN-05-012   Excessively Large Criticality All licensees authorized to Safety Limits Fail to        possess a critical mass of special Provide Double                nuclear material.
05/17/05 IN-05-012 Excessively Large Criticality Safety Limits Fail to Provide Double Contingency at Fuel Cycle Facility All licensees authorized to possess a critical mass of special nuclear material.


Contingency at Fuel Cycle Facility
04/07/05 IN-05-010
  04/07/05     IN-05-010   Changes to 10 CFR Part 71     All 10 CFR Part 71 licensees and Packages                      certificate holders.
Changes to 10 CFR Part 71 Packages All 10 CFR Part 71 licensees and certificate holders.


Note: NRC generic communications may be found on the NRC public website, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
Note: NRC generic communications may be found on the NRC public website, http://www.nrc.gov, under Electronic Reading Room/Document Collections.

Latest revision as of 19:26, 15 January 2025

Requirements for Power Reactor Licensees in Possession of Devices Subject to the General License Requirements of 10 CFR 31.5
ML051290143
Person / Time
Issue date: 07/11/2005
From: Hiland P, Chris Miller
NRC/NMSS/IMNS, NRC/NRR/DIPM/IROB
To:
Kirkwood A
References
RIS-05-011
Download: ML051290143 (5)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, DC 20555-0001 July 11, 2005 NRC REGULATORY ISSUE SUMMARY 2005-11 REQUIREMENTS FOR POWER REACTOR LICENSEES IN

POSSESSION OF DEVICES SUBJECT TO THE GENERAL LICENSE

REQUIREMENTS OF 10 CFR 31.5

ADDRESSEES

All holders of operating licenses for nuclear power reactors and generally licensed device vendors.

INTENT

The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)

to remind and/or inform addressees of the requirements for the receipt, possession, use, and transfer of generally licensed devices as described in 10 CFR 31.5 and 10 CFR 32.52. No specific action nor written response is required.

BACKGROUND

During a recent NRC radiation safety inspection at a commercial nuclear power plant, it was discovered that generally licensed devices used in the operation of the plant, as required by 10 CFR 73.55, were not being maintained in accordance with the requirements in 10 CFR 31.5.

The licensee incorrectly assumed that these devices were not under the jurisdiction of NRC,

and therefore did not include them in its radiation protection program required by its 10 CFR Part 50 license. Additionally, the licensee failed to include the devices in any program that would ensure they were maintained in accordance with regulatory requirements. Since the devices at issue are possessed and used as part of the operation of a production or utilization facility (i.e., the nuclear power plant), to comply with NRC requirements in 10 CFR 73.55, the NRC has exclusive jurisdiction over the byproduct material contained in these devices.

Accordingly, a violation of NRC requirements was identified in the above-mentioned inspection.

SUMMARY OF ISSUE

All Part 50 licensees are required to comply with the regulations in 10 CFR 31.5, if they possess and use byproduct material contained in devices subject to general licenses to support the operation of their facilities.

Section 31.5 contains the regulatory requirements for issuing a general license to commercial and industrial firms to acquire, receive, possess, use, or transfer in accordance with the provisions in paragraphs (b), (c), and (d) of this section byproduct material contained in certain measuring, detecting, and gauging devices. Some key examples of these requirements are stated, in part, below:

Section 31.5(c)(1) requires assuring that labels are affixed at the time of receipt and bear statements that removals of such labels are prohibited;

Section 31.5(c)(2) requires assuring the devices are tested for leakage of radioactive material and proper operation of the on-off mechanisms and indicators, if any, at no longer than 6 month intervals, or at such other intervals as specified on the labels;

Section 31.5(c)(4) requires maintaining records showing compliance with testing requirements;

Section 31.5(c)(12) requires appointment of an individual responsible for having knowledge of the appropriate regulations and requirements and the authority for taking required actions to ensure the day-to-day compliance with appropriate regulations.

Commercial power reactor licensees are hereby informed that generally licensed devices used to support reactor operations are under exclusive Federal jurisdiction and are subject to NRC

inspections. Vendors are hereby informed that generally licensed devices transferred to power reactor licensees need to be reported in their NRC quarterly reports in accordance with 10 CFR 32.52.

FEDERAL REGISTER NOTICE

A notice of opportunity for public comment was not published in the Federal Register because this RIS provides information that does not represent a departure from current regulatory requirements.

SMALL BUSINESS REGULATORY ENFORCEMENT FAIRNESS ACT

NRC has determined that this action is not subject to the Small Business Regulatory Enforcement Fairness Act of 1996.

PAPERWORK REDUCTION ACT STATEMENT

This RIS does not request any information collection and, therefore, is not subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501, et seq.).

BACKFIT DISCUSSION

This RIS requires no specific action nor written response.

CONTACT

Please direct any questions about this matter to the technical contact(s) or the Lead Project Manager listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

/RA/

/Original Signed by Patricia K. Holahan/

Patrick L. Hiland, Chief Charles L. Miller, Director Reactor Operations Branch Division of Industrial and Division of Inspection Program Management Medical Nuclear Safety Office of Nuclear Reactor Regulation Office of Nuclear Material Safety and Safeguards Technical Contacts:

Stephen P. Klementowicz, NRR

Anthony S. Kirkwood, NMSS

(301) 415-1084

(301) 415-6140

E-mail: sxk@nrc.gov E-mail: ask@nrc.gov Attachment: List of Recently Issued NMSS Generic Communications Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.

PAPERWORK REDUCTION ACT STATEMENT

This RIS does not request any information collection and, therefore, is not subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501, et seq.).

BACKFIT DISCUSSION

This RIS requires no specific action nor written response.

CONTACT

Please direct any questions about this matter to the technical contact(s) or the Lead Project Manager listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

/RA/

/Original Signed by Patricia K. Holahan/

Patrick L. Hiland, Chief Charles L. Miller, Director Reactor Operations Branch Division of Industrial and Division of Inspection Program Management Medical Nuclear Safety Office of Nuclear Reactor Regulation Office of Nuclear Material Safety and Safeguards Technical Contacts:

Stephen P. Klementowicz, NRR

Anthony S. Kirkwood, NMSS

(301) 415-1084

(301) 415-6140

E-mail: sxk@nrc.gov E-mail: ask@nrc.gov Attachment: List of Recently Issued NMSS Generic Communications Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.

DISTRIBUTION:

IMNS/ R/F

OES R/F

ML051290143

  • See previous concurrence OFFICE MSIB*

NMSS*

IMNS Gen. Coord. MSIB*

IMNS*

NAME

AKirkwood EKraus ICabrera THarris RCorreia DATE

5/9/05

5/11/05

7/05/05

5/19/05

5/25/05 OFFICE IMNS*

OSTP*

OGC*

NRR*

NRR*

NAME

JHickey PLohaus STreby/NLO

SKlementowicz TQuay DATE

5/23/05

6/02/05

6/23/05

5/31/05

5/31/05 OFFICE IMNS

NRR

NRR

NRR

NAME

CMiller AWMarkley EJBenner PLHiland DATE

07/06/05

7/08/05

7/08/05

7/11/05 OFFICIAL RECORD COPY

Attachment Recently Issued NMSS Generic Communications Date GC No.

Subject

Addressees

06/10/05 RIS-05-10

Performance-Based Approach for Associated Equipment in 10 CFR 34.20

All industrial radiography licensees and manufacturers and distributors of industrial radiography equipment.

04/18/05 RIS-05-06 Reporting Requirements for Gauges Damaged at Temporary Job Sites All material licensees possessing portable gauges, regulated under

10 CFR Part 30.

04/14/05 RIS-05-04 Guidance on the Protection of Unattended Openings that Intersect a Security Boundary or Area All holders of operating licenses or construction permits for nuclear power reactors, research and test reactors, decommissioning reactors with fuel on site, Category 1 fuel cycle facilities, critical mass facilities, uranium conversion facility, independent spent fuel storage installations, gaseous diffusion plants, and certain other material licensees.

6/23/05 IN-05-17 Manual Brachytherapy Source Jamming All medical licensees authorized to possess a Mick applicator.

05/17/05 IN-05-013 Potential Non-conservative Error in Modeling Geometric Regions in the Keno-v.a Criticality Code All licensees using the Keno-V.a criticality code module in Standardized Computer Analyses for Licensing Evaluation (SCALE)

software developed by Oak Ridge National Laboratory (ORNL)

05/17/05 IN-05-012 Excessively Large Criticality Safety Limits Fail to Provide Double Contingency at Fuel Cycle Facility All licensees authorized to possess a critical mass of special nuclear material.

04/07/05 IN-05-010

Changes to 10 CFR Part 71 Packages All 10 CFR Part 71 licensees and certificate holders.

Note: NRC generic communications may be found on the NRC public website, http://www.nrc.gov, under Electronic Reading Room/Document Collections.