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| issue date = 01/29/2009 | | issue date = 01/29/2009 | ||
| title = Use of Containment Atmosphere Gaseous Radioactivity Monitors as Reactor Coolant System Leakage Detection Equipment at Nuclear Power Reactors | | title = Use of Containment Atmosphere Gaseous Radioactivity Monitors as Reactor Coolant System Leakage Detection Equipment at Nuclear Power Reactors | ||
| author name = | | author name = Mcginty T | ||
| author affiliation = NRC/NRR/DPR | | author affiliation = NRC/NRR/DPR | ||
| addressee name = | | addressee name = | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION | {{#Wiki_filter:UNITED STATES | ||
OFFICE OF NUCLEAR REACTOR REGULATION | |||
WASHINGTON, DC 20555-0001 | NUCLEAR REGULATORY COMMISSION | ||
OFFICE OF NUCLEAR REACTOR REGULATION | |||
WASHINGTON, DC 20555-0001 | |||
January 29, 2009 | |||
NRC REGULATORY ISSUE SUMMARY 2009-02 | |||
USE OF CONTAINMENT ATMOSPHERE GASEOUS RADIOACTIVITY | USE OF CONTAINMENT ATMOSPHERE GASEOUS RADIOACTIVITY | ||
MONITORS AS REACTOR | MONITORS AS REACTOR COOLANT SYSTEM LEAKAGE DETECTION | ||
EQUIPMENT AT NUCLEAR POWER REACTORS | |||
EQUIPMENT AT NUCLEAR | |||
ADDRESSEES | |||
ADDRESSEES | |||
All holders of operating licenses for nuclear power reactors except those who have permanently | |||
vessel. All current and potential applicants for a combined license, manufacturing license, standard | ceased operations and have certified that fuel has been permanently removed from the reactor | ||
vessel. | |||
All current and potential applicants for a combined license, manufacturing license, standard | |||
design certification, or standard design approval for a nuclear power plant under the provisions | design certification, or standard design approval for a nuclear power plant under the provisions | ||
of Title 10 of the Code of Federal Regulations, Part 52 (10 CFR), | of Title 10 of the Code of Federal Regulations, Part 52 (10 CFR), Licenses, Certifications, and | ||
Approvals for Nuclear Power Plants. | |||
Approvals for Nuclear Power Plants | |||
All applicants for nuclear power plant construction permits and operating licenses under the provisions of 10 CFR Part 50, | All applicants for nuclear power plant construction permits and operating licenses under the | ||
INTENT The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to communicate the NRC plan to address the situation created when some containment | provisions of 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. | ||
INTENT | |||
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) | |||
to communicate the NRC plan to address the situation created when some containment | |||
atmosphere gaseous radioactivity monitors are unable to meet technical specification (TS) | atmosphere gaseous radioactivity monitors are unable to meet technical specification (TS) | ||
requirements. The plan consists of integrating a streamlined license amendment process with | requirements. The plan consists of integrating a streamlined license amendment process with | ||
the use of enforcement discretion, where appropriate. This RIS requires no action or written response on the part of an addressee. | the use of enforcement discretion, where appropriate. This RIS requires no action or written | ||
BACKGROUND INFORMATION | response on the part of an addressee. | ||
BACKGROUND INFORMATION | |||
In order to meet General Design Criterion 30, "Quality of reactor coolant pressure boundary," of | |||
Appendix A to 10 CFR Part 50, licensees typically include RCS leakage detection equipment in | |||
their plant designs because the equipment can be used to detect reactor coolant pressure | |||
boundary (RCPB) leakage. A typical RCS leakage detection system consists of a combination | boundary (RCPB) leakage. A typical RCS leakage detection system consists of a combination | ||
of the following: | of the following: | ||
* | |||
a containment atmosphere particulate radioactivity monitoring system | |||
* | |||
a containment atmosphere gaseous radioactivity monitoring system | |||
* | |||
containment sump-level and sump-pump instrumentation | |||
* | |||
containment cooler condensate monitoring instrumentation | |||
ML090120669 | |||
RIS 2009-02 | RIS 2009-02 | ||
Page 2 of 5 Containment atmosphere gaseous radioactivity monitoring systems measure RCS leakage indirectly by detecting airborne radioactivity released from RCS leakage. Response time is the | Page 2 of 5 | ||
Containment atmosphere gaseous radioactivity monitoring systems measure RCS leakage | |||
indirectly by detecting airborne radioactivity released from RCS leakage. Response time is the | |||
length of time required for these monitoring systems to detect a given volume of RCS leakage. | length of time required for these monitoring systems to detect a given volume of RCS leakage. | ||
Response time is dependant on RCS radioactivity concentration, as well as other variables. For | |||
Response time is dependant on RCS radioactivity concentration, as well as other variables. For a given volume of leakage, with all other variables held constant, a higher RCS radioactivity | a given volume of leakage, with all other variables held constant, a higher RCS radioactivity | ||
concentration will yield a shorter response time for these monitoring systems. The design analyses for the containment atmosphere gaseous radioactivity monitoring systems used in the licensing bases for most plants typically assume a RCS radioactivity concentration | concentration will yield a shorter response time for these monitoring systems. The design | ||
approximately equivalent to 0.1 percent failed fuel in the core. Improvements in fuel cladding integrity and RCS chemistry controls have significantly reduced RCS radioactivity concentration at most plants. As a result, the monitors for operating units may have longer response times than they would with 0.1 percent failed fuel in the core because the actual RCS radioactivity concentration is less than it would be with 0.1 percent failed fuel in the core. | analyses for the containment atmosphere gaseous radioactivity monitoring systems used in the | ||
licensing bases for most plants typically assume a RCS radioactivity concentration | |||
approximately equivalent to 0.1 percent failed fuel in the core. Improvements in fuel cladding | |||
integrity and RCS chemistry controls have significantly reduced RCS radioactivity concentration | |||
at most plants. As a result, the monitors for operating units may have longer response times | |||
than they would with 0.1 percent failed fuel in the core because the actual RCS radioactivity | |||
concentration is less than it would be with 0.1 percent failed fuel in the core. | |||
Most plants have TS Limiting Conditions | Most plants have TS Limiting Conditions for Operation requirements for containment | ||
atmosphere gaseous radioactivity monitoring systems used as part of RCS leakage detection | |||
equipment. The TS requirements for the | equipment. The TS requirements for the monitoring systems response times are based on the | ||
design analysis that is part of a plants licensing basis. If the monitors fail to meet these | |||
requirements, the monitors are inoperable. When the monitors are inoperable the licensee is | |||
required to take remedial actions as permitted by their TS or to shut down the reactor. | |||
Information Notice (IN) 2005-24, | Information Notice (IN) 2005-24, Nonconservatism in Leakage Detection Sensitivity | ||
(ADAMS Accession No. ML051780073), communicated the issue created by differences | |||
between actual and assumed RCS radioactivity concentrations to all licensees. The purpose of IN 2005-24 was to have licensees review information related to problems with containment | between actual and assumed RCS radioactivity concentrations to all licensees. The purpose of | ||
atmosphere gaseous radioactivity monitors used as part of RCS leakage detection equipment and consider appropriate actions as applicable to their plants. Information Notices do not | IN 2005-24 was to have licensees review information related to problems with containment | ||
atmosphere gaseous radioactivity monitors used as part of RCS leakage detection equipment | |||
and consider appropriate actions as applicable to their plants. Information Notices do not | |||
require any action by licensees. | require any action by licensees. | ||
In September 2008, NRC inspectors at the | In September 2008, NRC inspectors at the Diablo Canyon Power Plant identified a non-cited | ||
violation for not complying with TS requirements for RCS leakage detection equipment. In | |||
November 2008, the licensee for the Watts Bar Nuclear Plant and the Sequoyah Nuclear Plant requested exigent license amendments from the NRC after taking remedial actions as permitted by their TS because of a concern that the containment atmosphere gaseous radioactivity monitor channels of the RCS leakage detection system were inoperable. | November 2008, the licensee for the Watts Bar Nuclear Plant and the Sequoyah Nuclear Plant | ||
requested exigent license amendments from the NRC after taking remedial actions as permitted | |||
by their TS because of a concern that the containment atmosphere gaseous radioactivity | |||
monitor channels of the RCS leakage detection system were inoperable. | |||
To address the issue, licensees working through the industry-sponsored Technical | To address the issue, licensees working through the industry-sponsored Technical | ||
Specifications Task Force (TSTF) have attempted to create generic TS changes, model License Amendment Requests (LARs), model safety evaluations, and model proposed | Specifications Task Force (TSTF) have attempted to create generic TS changes, model License | ||
no-significant-hazards consideration determinations using the NRC TS Consolidated Line Item Improvement Process (CLIIP). See RIS 2000-10, | Amendment Requests (LARs), model safety evaluations, and model proposed | ||
no-significant-hazards consideration determinations using the NRC TS Consolidated Line Item | |||
Improvement Process (CLIIP). See RIS 2000-10, Consolidated Line Item Improvement | |||
Process For Adopting Standard Technical Specifications Changes for Power Reactors | |||
(ADAMS Accession No. ML003693442) for more information on the NRC CLIIP. | |||
RIS 2009-02 | RIS 2009-02 | ||
Page 3 of 5 SUMMARY OF ISSUE | Page 3 of 5 | ||
radioactivity concentrations during operational activities, including situations where there is RCS leakage. Thus, containment atmosphere gaseous radioactivity monitoring systems which are | SUMMARY OF ISSUE | ||
designed on the basis of higher assumed RCS radioactivity concentrations will not provide accurate indication of RCS leakage in the required length of time due to the longer response time of the monitoring system, and must be considered inoperable. | |||
Improvements in fuel cladding integrity and RCS chemistry controls result in lower RCS | |||
radioactivity concentrations during operational activities, including situations where there is RCS | |||
radioactivity monitors to be of very low safety significance. The monitors would still be able to detect degradation in the RCPB long before components fail in a manner that would affect plant safety. Additionally, plants also have multiple diverse and redundant methods available to | leakage. Thus, containment atmosphere gaseous radioactivity monitoring systems which are | ||
designed on the basis of higher assumed RCS radioactivity concentrations will not provide | |||
accurate indication of RCS leakage in the required length of time due to the longer response | |||
time of the monitoring system, and must be considered inoperable. | |||
The NRC considers the longer response times of the containment atmosphere gaseous | |||
radioactivity monitors to be of very low safety significance. The monitors would still be able to | |||
detect degradation in the RCPB long before components fail in a manner that would affect plant | |||
safety. Additionally, plants also have multiple diverse and redundant methods available to | |||
detect RCS leakage and to provide licensees with a means to detect significant RCPB | detect RCS leakage and to provide licensees with a means to detect significant RCPB | ||
degradation and to take appropriate action to ensure the continued protection of public health | degradation and to take appropriate action to ensure the continued protection of public health | ||
and safety. Finally, nuclear power plants are designed to provide adequate core cooling | |||
and safety. Finally, nuclear power plants are designed to provide adequate core cooling following postulated loss-of-coolant accidents up to and including a break equivalent in size to | following postulated loss-of-coolant accidents up to and including a break equivalent in size to | ||
the double-ended rupture of the largest pipe in the RCS. This design feature, coupled with the | the double-ended rupture of the largest pipe in the RCS. This design feature, coupled with the | ||
extremely low likelihood of unstable crack growth resulting in a loss-of-coolant accident, leads | extremely low likelihood of unstable crack growth resulting in a loss-of-coolant accident, leads | ||
the NRC to conclude that the risk | the NRC to conclude that the risk significance of this issue is very low. | ||
The NRC plans to address the issue of inoperable containment atmosphere gaseous | The NRC plans to address the issue of inoperable containment atmosphere gaseous | ||
radioactivity monitoring systems in an integrated fashion by: (i) working with the TSTF to develop revised generic TS for the monitoring system, and facilitating licensee implementation of the revised generic TS through a streamlined license amendment process; and (ii) issuing guidance on | radioactivity monitoring systems in an integrated fashion by: (i) working with the TSTF to | ||
discretion involving inoperable containment atmosphere gaseous radioactivity monitoring systems. | develop revised generic TS for the monitoring system, and facilitating licensee implementation | ||
The NRC will review the generic TS changes that the TSTF proposes for pressurized-water | of the revised generic TS through a streamlined license amendment process; and (ii) issuing | ||
guidance on NRCs exercise of enforcement discretion involving inoperable containment | |||
atmosphere gaseous radioactivity monitoring systems. | |||
The NRC will review the generic TS changes that the TSTF proposes for pressurized-water | |||
reactors (PWRs) and boiling-water reactors (BWRs). If the generic TS changes are found to be | reactors (PWRs) and boiling-water reactors (BWRs). If the generic TS changes are found to be | ||
acceptable, the NRC will make the generic model | acceptable, the NRC will make the generic model LARs, model safety evaluations, and model | ||
LARs, model safety evaluations, and model | no-significant-hazards consideration determinations available to licensees using the NRC CLIIP. | ||
no-significant-hazards consideration determinations available to licensees using the NRC CLIIP. Licensees are free to submit LARs for TS changes to address the issue. If licensees deem further action regarding the issue is unwarranted, they can choose to take no action. | Licensees are free to submit LARs for TS changes to address the issue. If licensees deem | ||
further action regarding the issue is unwarranted, they can choose to take no action. | |||
On November 14, 2008, the TSTF submitted TSTF-513, Revise Operability Requirements and | |||
Actions for RCS Leakage Instrumentation, to the NRC for review. TSTF-513 proposes generic | |||
TS changes for PWRs. The TSTF plans to submit TSTF-514 to the NRC in January 2009. | |||
TSTF-514 will propose generic TS changes for BWRs. Licensees are free to submit LARs to | |||
address the issue using TSTF-513 or TSTF-514; or they can propose alternative solutions. | |||
In certain circumstances involving inoperable containment atmosphere gaseous radioactivity | |||
monitoring systems, enforcement discretion is available. Specific guidance for this enforcement | |||
discretion is described in EGM-09-001 (ADAMS Accession No. ML090300467) and is available | |||
on the NRCs web site at www.nrc.gov. | |||
RIS 2009-02 | |||
Page 4 of 5 | |||
BACKFIT DISCUSSION | |||
The intent of this RIS is to inform addressees of the NRCs plan to address the failure of | |||
containment atmosphere gaseous radioactivity monitors used as RCS leakage detection | containment atmosphere gaseous radioactivity monitors used as RCS leakage detection | ||
equipment to meet TS requirements. | equipment to meet TS requirements. | ||
FEDERAL REGISTER NOTIFICATION | |||
The staff is not imposing any new positions on licensees. This RIS is not providing any new | |||
Federal Register | regulatory positions. This RIS only conveys the NRCs plan to address the issue of RCS | ||
leakage detection equipment failing to meet TS requirements because of the difference between | |||
actual and assumed RCS radioactivity concentrations. This RIS requires no action or written | |||
response and, therefore, is not a backfit under 10 CFR 50.109, Backfitting. Consequently, the | |||
staff did not perform a backfit analysis. | |||
FEDERAL REGISTER NOTIFICATION | |||
A notice of opportunity for public comment on this RIS was not published in the Federal Register | |||
because it is informational and pertains to a staff position that does not represent a departure | |||
from current regulatory requirements and practice. However, a public meeting to discuss this | |||
RIS was held on January 8, 2009. The meeting summary is available under ADAMS Accession | RIS was held on January 8, 2009. The meeting summary is available under ADAMS Accession | ||
No. ML090130583. The NRC intends to work with industry representatives, members of the | No. ML090130583. The NRC intends to work with industry representatives, members of the | ||
public, and other stakeholders in developing final guidance and in modifying related guidance | public, and other stakeholders in developing final guidance and in modifying related guidance | ||
documents. | documents. | ||
CONGRESSIONAL REVIEW ACT | |||
CONGRESSIONAL REVIEW ACT | |||
PAPERWORK REDUCTION ACT STATEMENT | |||
This RIS is not a rule as designated by the Congressional Review Act (5 U.S.C. §§ 801-808) | |||
PUBLIC PROTECTION NOTIFICATION | and, therefore, is not subject to the Act. | ||
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for | |||
information or an information collection requirement unless the requesting document displays a currently valid OMB control number. | PAPERWORK REDUCTION ACT STATEMENT | ||
This RIS does not contain any information collections and, therefore, is not subject to the | |||
requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501, et seq.). | |||
PUBLIC PROTECTION NOTIFICATION | |||
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for | |||
information or an information collection requirement unless the requesting document displays a | |||
currently valid OMB control number. | |||
RIS 2009-02 | RIS 2009-02 | ||
Page 5 of 5 CONTACT Please direct any questions about this matter to the technical contact listed below or to the | Page 5 of 5 | ||
CONTACT | |||
Please direct any questions about this matter to the technical contact listed below or to the | |||
appropriate Office of Nuclear Reactor Regulation (NRR) project manager. | appropriate Office of Nuclear Reactor Regulation (NRR) project manager. | ||
/RA by Theodore R. Quay For/ | |||
Timothy J. McGinty, Director | /RA by Theodore R. Quay For/ | ||
Division of Policy and Rulemaking Office of Nuclear Reactor Regulation | |||
Timothy J. McGinty, Director | |||
e-mail: matthew.hamm@nrc.gov | Division of Policy and Rulemaking | ||
Office of Nuclear Reactor Regulation | |||
Technical Contact: Matthew Hamm, NRR | |||
301-415-1472 | |||
e-mail: matthew.hamm@nrc.gov | |||
Note: NRC generic communications may be found on the NRC public Web site, | Note: NRC generic communications may be found on the NRC public Web site, | ||
http://www.nrc.gov, under Electronic Reading Room/Document Collections. | http://www.nrc.gov, under Electronic Reading Room/Document Collections. | ||
RIS 2009-02 | RIS 2009-02 | ||
Page 5 of 5 CONTACT Please direct any questions about this matter to the technical contact listed below or to the | Page 5 of 5 | ||
CONTACT | |||
Please direct any questions about this matter to the technical contact listed below or to the | |||
appropriate Office of Nuclear Reactor Regulation (NRR) project manager. | appropriate Office of Nuclear Reactor Regulation (NRR) project manager. | ||
/RA by Theodore R. Quay For/ | |||
Timothy J. McGinty, Director | /RA by Theodore R. Quay For/ | ||
Timothy J. McGinty, Director | |||
Division of Policy and Rulemaking | Division of Policy and Rulemaking | ||
Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation | ||
e-mail: matthew.hamm@nrc.gov | |||
Technical Contact: Matthew Hamm, NRR | |||
ADAMS ACCESSION No. ML090120669 OFFICIAL RECORD COPY | 301-415-1472 | ||
e-mail: matthew.hamm@nrc.gov | |||
Note: NRC generic communications may be found on the NRC public Web site, | |||
http://www.nrc.gov, under Electronic Reading Room/Document Collections. | |||
ADAMS ACCESSION No. ML090120669 | |||
OFFICIAL RECORD COPY | |||
OFFICE | |||
ITSB:DIRS | ITSB:DIRS | ||
Tech Editor BC:ITSBDIRS | Tech Editor | ||
D:DIRS PSPB DPR | BC:ITSBDIRS | ||
D:DIRS | |||
PSPB DPR | |||
BC:PSPB DPR | BC:PSPB DPR | ||
NAME MHamm via email | |||
RElliott FBrown MCheok for | NAME | ||
MHamm | |||
via email | |||
RElliott | |||
FBrown | |||
MCheok for | |||
JWilliams | JWilliams | ||
SRosenberg | SRosenberg | ||
DNelson for | DNelson for | ||
DATE | |||
12/19/2008 | |||
12/15/2008 | 12/15/2008 | ||
1/12/2009 1/12/2009 12/30/2008 | 1/12/2009 | ||
1/12/2009 | |||
12/30/2008 | |||
12/30/2008 | 12/30/2008 | ||
RI:DRP:D | OFFICE | ||
D:DSS | |||
D:DORL | |||
RI:DRP:D | |||
RII:DRP:D | RII:DRP:D | ||
| Line 200: | Line 320: | ||
RIV:DRP:D | RIV:DRP:D | ||
NAME WRuland for JGiitter | |||
DLew via email LWert via | NAME | ||
email CPederson | WRuland | ||
for JGiitter | |||
via email DChamberlain | DLew via | ||
email | |||
LWert via | |||
email | |||
CPederson | |||
via email | |||
DChamberlain | |||
via email | via email | ||
DATE | |||
1/12/2009 | |||
12/30/2008 | |||
1/15/2009 | |||
1/14/2009 | |||
1/13/2009 | |||
1/15/2009 | 1/15/2009 | ||
OFFICE | OFFICE | ||
D:DCI BC:CHPB DCIP D: DCIP/NRO | |||
OE | D:DCI | ||
BC:CHPB | |||
DCIP | |||
D: DCIP/NRO | |||
OE | |||
OGC (NLO) | OGC (NLO) | ||
OGC (CRA) | OGC (CRA) | ||
NAME MEvans TFrye CHinson for | NAME | ||
GTracy DStarkey via email | MEvans | ||
BJones NSanchez via email | TFrye | ||
CHinson for | |||
GTracy | |||
DStarkey | |||
via email | |||
BJones | |||
NSanchez | |||
via email | |||
DATE 1/15/2009 | DATE | ||
1/15/2009 | |||
01/07/2009 | |||
01/08/2009 | 01/08/2009 | ||
1/14/2009 01/27/2009 | 1/14/2009 | ||
1/28/2009 | 01/27/2009 1/28/2009 | ||
OFFICE | |||
PMDA | |||
OIS | |||
LA:PGCB | |||
PGCB | |||
LHill GTrussell | BC: PGCB | ||
D:DPR | |||
NAME | |||
LHill | |||
GTrussell | |||
CHawes | CHawes | ||
SStuchell | SStuchell | ||
MMurphy TMcGinty TRQ | MMurphy | ||
for | TMcGinty TRQ | ||
DATE 01/05/2009 | for | ||
DATE | |||
01/05/2009 | |||
01/07/2009 | 01/07/2009 | ||
1/28/2009 | 1/28/2009 | ||
Latest revision as of 13:44, 14 January 2025
| ML090120669 | |
| Person / Time | |
|---|---|
| Issue date: | 01/29/2009 |
| From: | Mcginty T Division of Policy and Rulemaking |
| To: | |
| Hawes C, NRR/DPR/PGCB, 415-1316 | |
| References | |
| RIS-09-002 | |
| Download: ML090120669 (6) | |
See also: RIS 2009-02
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001
January 29, 2009
NRC REGULATORY ISSUE SUMMARY 2009-02
USE OF CONTAINMENT ATMOSPHERE GASEOUS RADIOACTIVITY
MONITORS AS REACTOR COOLANT SYSTEM LEAKAGE DETECTION
EQUIPMENT AT NUCLEAR POWER REACTORS
ADDRESSEES
All holders of operating licenses for nuclear power reactors except those who have permanently
ceased operations and have certified that fuel has been permanently removed from the reactor
vessel.
All current and potential applicants for a combined license, manufacturing license, standard
design certification, or standard design approval for a nuclear power plant under the provisions
of Title 10 of the Code of Federal Regulations, Part 52 (10 CFR), Licenses, Certifications, and
Approvals for Nuclear Power Plants.
All applicants for nuclear power plant construction permits and operating licenses under the
provisions of 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities.
INTENT
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
to communicate the NRC plan to address the situation created when some containment
atmosphere gaseous radioactivity monitors are unable to meet technical specification (TS)
requirements. The plan consists of integrating a streamlined license amendment process with
the use of enforcement discretion, where appropriate. This RIS requires no action or written
response on the part of an addressee.
BACKGROUND INFORMATION
In order to meet General Design Criterion 30, "Quality of reactor coolant pressure boundary," of
Appendix A to 10 CFR Part 50, licensees typically include RCS leakage detection equipment in
their plant designs because the equipment can be used to detect reactor coolant pressure
boundary (RCPB) leakage. A typical RCS leakage detection system consists of a combination
of the following:
a containment atmosphere particulate radioactivity monitoring system
a containment atmosphere gaseous radioactivity monitoring system
containment sump-level and sump-pump instrumentation
containment cooler condensate monitoring instrumentation
Page 2 of 5
Containment atmosphere gaseous radioactivity monitoring systems measure RCS leakage
indirectly by detecting airborne radioactivity released from RCS leakage. Response time is the
length of time required for these monitoring systems to detect a given volume of RCS leakage.
Response time is dependant on RCS radioactivity concentration, as well as other variables. For
a given volume of leakage, with all other variables held constant, a higher RCS radioactivity
concentration will yield a shorter response time for these monitoring systems. The design
analyses for the containment atmosphere gaseous radioactivity monitoring systems used in the
licensing bases for most plants typically assume a RCS radioactivity concentration
approximately equivalent to 0.1 percent failed fuel in the core. Improvements in fuel cladding
integrity and RCS chemistry controls have significantly reduced RCS radioactivity concentration
at most plants. As a result, the monitors for operating units may have longer response times
than they would with 0.1 percent failed fuel in the core because the actual RCS radioactivity
concentration is less than it would be with 0.1 percent failed fuel in the core.
Most plants have TS Limiting Conditions for Operation requirements for containment
atmosphere gaseous radioactivity monitoring systems used as part of RCS leakage detection
equipment. The TS requirements for the monitoring systems response times are based on the
design analysis that is part of a plants licensing basis. If the monitors fail to meet these
requirements, the monitors are inoperable. When the monitors are inoperable the licensee is
required to take remedial actions as permitted by their TS or to shut down the reactor.
Information Notice (IN) 2005-24, Nonconservatism in Leakage Detection Sensitivity
(ADAMS Accession No. ML051780073), communicated the issue created by differences
between actual and assumed RCS radioactivity concentrations to all licensees. The purpose of
IN 2005-24 was to have licensees review information related to problems with containment
atmosphere gaseous radioactivity monitors used as part of RCS leakage detection equipment
and consider appropriate actions as applicable to their plants. Information Notices do not
require any action by licensees.
In September 2008, NRC inspectors at the Diablo Canyon Power Plant identified a non-cited
violation for not complying with TS requirements for RCS leakage detection equipment. In
November 2008, the licensee for the Watts Bar Nuclear Plant and the Sequoyah Nuclear Plant
requested exigent license amendments from the NRC after taking remedial actions as permitted
by their TS because of a concern that the containment atmosphere gaseous radioactivity
monitor channels of the RCS leakage detection system were inoperable.
To address the issue, licensees working through the industry-sponsored Technical
Specifications Task Force (TSTF) have attempted to create generic TS changes, model License
Amendment Requests (LARs), model safety evaluations, and model proposed
no-significant-hazards consideration determinations using the NRC TS Consolidated Line Item
Improvement Process (CLIIP). See RIS 2000-10, Consolidated Line Item Improvement
Process For Adopting Standard Technical Specifications Changes for Power Reactors
(ADAMS Accession No. ML003693442) for more information on the NRC CLIIP.
Page 3 of 5
SUMMARY OF ISSUE
Improvements in fuel cladding integrity and RCS chemistry controls result in lower RCS
radioactivity concentrations during operational activities, including situations where there is RCS
leakage. Thus, containment atmosphere gaseous radioactivity monitoring systems which are
designed on the basis of higher assumed RCS radioactivity concentrations will not provide
accurate indication of RCS leakage in the required length of time due to the longer response
time of the monitoring system, and must be considered inoperable.
The NRC considers the longer response times of the containment atmosphere gaseous
radioactivity monitors to be of very low safety significance. The monitors would still be able to
detect degradation in the RCPB long before components fail in a manner that would affect plant
safety. Additionally, plants also have multiple diverse and redundant methods available to
detect RCS leakage and to provide licensees with a means to detect significant RCPB
degradation and to take appropriate action to ensure the continued protection of public health
and safety. Finally, nuclear power plants are designed to provide adequate core cooling
following postulated loss-of-coolant accidents up to and including a break equivalent in size to
the double-ended rupture of the largest pipe in the RCS. This design feature, coupled with the
extremely low likelihood of unstable crack growth resulting in a loss-of-coolant accident, leads
the NRC to conclude that the risk significance of this issue is very low.
The NRC plans to address the issue of inoperable containment atmosphere gaseous
radioactivity monitoring systems in an integrated fashion by: (i) working with the TSTF to
develop revised generic TS for the monitoring system, and facilitating licensee implementation
of the revised generic TS through a streamlined license amendment process; and (ii) issuing
guidance on NRCs exercise of enforcement discretion involving inoperable containment
atmosphere gaseous radioactivity monitoring systems.
The NRC will review the generic TS changes that the TSTF proposes for pressurized-water
reactors (PWRs) and boiling-water reactors (BWRs). If the generic TS changes are found to be
acceptable, the NRC will make the generic model LARs, model safety evaluations, and model
no-significant-hazards consideration determinations available to licensees using the NRC CLIIP.
Licensees are free to submit LARs for TS changes to address the issue. If licensees deem
further action regarding the issue is unwarranted, they can choose to take no action.
On November 14, 2008, the TSTF submitted TSTF-513, Revise Operability Requirements and
Actions for RCS Leakage Instrumentation, to the NRC for review. TSTF-513 proposes generic
TS changes for PWRs. The TSTF plans to submit TSTF-514 to the NRC in January 2009.
TSTF-514 will propose generic TS changes for BWRs. Licensees are free to submit LARs to
address the issue using TSTF-513 or TSTF-514; or they can propose alternative solutions.
In certain circumstances involving inoperable containment atmosphere gaseous radioactivity
monitoring systems, enforcement discretion is available. Specific guidance for this enforcement
discretion is described in EGM-09-001 (ADAMS Accession No. ML090300467) and is available
on the NRCs web site at www.nrc.gov.
Page 4 of 5
BACKFIT DISCUSSION
The intent of this RIS is to inform addressees of the NRCs plan to address the failure of
containment atmosphere gaseous radioactivity monitors used as RCS leakage detection
equipment to meet TS requirements.
The staff is not imposing any new positions on licensees. This RIS is not providing any new
regulatory positions. This RIS only conveys the NRCs plan to address the issue of RCS
leakage detection equipment failing to meet TS requirements because of the difference between
actual and assumed RCS radioactivity concentrations. This RIS requires no action or written
response and, therefore, is not a backfit under 10 CFR 50.109, Backfitting. Consequently, the
staff did not perform a backfit analysis.
FEDERAL REGISTER NOTIFICATION
A notice of opportunity for public comment on this RIS was not published in the Federal Register
because it is informational and pertains to a staff position that does not represent a departure
from current regulatory requirements and practice. However, a public meeting to discuss this
RIS was held on January 8, 2009. The meeting summary is available under ADAMS Accession
No. ML090130583. The NRC intends to work with industry representatives, members of the
public, and other stakeholders in developing final guidance and in modifying related guidance
documents.
CONGRESSIONAL REVIEW ACT
This RIS is not a rule as designated by the Congressional Review Act (5 U.S.C. §§ 801-808)
and, therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT
This RIS does not contain any information collections and, therefore, is not subject to the
requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501, et seq.).
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for
information or an information collection requirement unless the requesting document displays a
currently valid OMB control number.
Page 5 of 5
CONTACT
Please direct any questions about this matter to the technical contact listed below or to the
appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
/RA by Theodore R. Quay For/
Timothy J. McGinty, Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact: Matthew Hamm, NRR
301-415-1472
e-mail: matthew.hamm@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site,
http://www.nrc.gov, under Electronic Reading Room/Document Collections.
Page 5 of 5
CONTACT
Please direct any questions about this matter to the technical contact listed below or to the
appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
/RA by Theodore R. Quay For/
Timothy J. McGinty, Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact: Matthew Hamm, NRR
301-415-1472
e-mail: matthew.hamm@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site,
http://www.nrc.gov, under Electronic Reading Room/Document Collections.
ADAMS ACCESSION No. ML090120669
OFFICIAL RECORD COPY
OFFICE
ITSB:DIRS
Tech Editor
BC:ITSBDIRS
D:DIRS
PSPB DPR
BC:PSPB DPR
NAME
MHamm
via email
RElliott
FBrown
MCheok for
JWilliams
SRosenberg
DNelson for
DATE
12/19/2008
12/15/2008
1/12/2009
1/12/2009
12/30/2008
12/30/2008
OFFICE
D:DSS
D:DORL
RI:DRP:D
RII:DRP:D
RIII:DRP:D
RIV:DRP:D
NAME
WRuland
for JGiitter
DLew via
LWert via
CPederson
via email
DChamberlain
via email
DATE
1/12/2009
12/30/2008
1/15/2009
1/14/2009
1/13/2009
1/15/2009
OFFICE
D:DCI
BC:CHPB
DCIP
D: DCIP/NRO
OGC (CRA)
NAME
MEvans
TFrye
CHinson for
GTracy
DStarkey
via email
BJones
NSanchez
via email
DATE
1/15/2009
01/07/2009
01/08/2009
1/14/2009
01/27/2009 1/28/2009
OFFICE
PMDA
OIS
LA:PGCB
PGCB
BC: PGCB
D:DPR
NAME
LHill
GTrussell
CHawes
SStuchell
MMurphy
TMcGinty TRQ
for
DATE
01/05/2009
01/07/2009
1/28/2009
1/28/2009
1/29/2009
1/29/2009