Information Notice 2014-02, Failure to Properly Pressure Test Reactor Vessel Flange Leak-Off Lines: Difference between revisions

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| issue date = 02/25/2014
| issue date = 02/25/2014
| title = Failure to Properly Pressure Test Reactor Vessel Flange Leak-Off Lines
| title = Failure to Properly Pressure Test Reactor Vessel Flange Leak-Off Lines
| author name = Cheok M C, Kokajko L E
| author name = Cheok M, Kokajko L
| author affiliation = NRC/NRO/DCIP, NRC/NRR/DPR
| author affiliation = NRC/NRO/DCIP, NRC/NRR/DPR
| addressee name =  
| addressee name =  
Line 9: Line 9:
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Anchondo I A, Wallace J S
| contact person = Anchondo I, Wallace J
| case reference number = TAC MF1794
| case reference number = TAC MF1794
| document report number = IN-14-002
| document report number = IN-14-002
Line 15: Line 15:
| page count = 4
| page count = 4
}}
}}
{{#Wiki_filter:ML13193A002 February 25, 2014 NRC INFORMATION NOTICE 2014-02: FAILURE TO PROPERLY PRESSURE TEST REACTOR VESSEL FLANGE LEAK-OFF LINES
{{#Wiki_filter:UNITED STATES
 
NUCLEAR REGULATORY COMMISSION
 
OFFICE OF NUCLEAR REACTOR REGULATION
 
OFFICE OF NEW REACTORS
 
WASHINGTON, DC 20555-0001 February 25, 2014 NRC INFORMATION NOTICE 2014-02:               FAILURE TO PROPERLY PRESSURE TEST
 
REACTOR VESSEL FLANGE LEAK-OFF LINES


==ADDRESSEES==
==ADDRESSEES==
All holders of an operating license or construction permit for a nuclear power reactor under Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vesse All holders of and applicants for a power reactor early site permit, combined license, standard design certification, standard design approval, or manufacturing license under 10 CFR Part 52,  
All holders of an operating license or construction permit for a nuclear power reactor under
"Licenses, Certifications, and Approvals for Nuclear Power Plants."
 
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of
 
Production and Utilization Facilities, except those who have permanently ceased operations
 
and have certified that fuel has been permanently removed from the reactor vessel.
 
All holders of and applicants for a power reactor early site permit, combined license, standard
 
design certification, standard design approval, or manufacturing license under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.


==PURPOSE==
==PURPOSE==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform addressees of instances in which inspections of reactor vessel flange leak-off lines as required by Section XI of the American Society of Mechanical Engineers (ASME) Code and, therefore, 10 CFR 50.55a were not performed or were inadequately performe The NRC expects that recipients will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problem However, suggestions contained in this IN are not NRC requirements; therefore, no specific action or written response is require
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform
 
addressees of instances in which inspections of reactor vessel flange leak-off lines as required
 
by Section XI of the American Society of Mechanical Engineers (ASME) Code and, therefore,
10 CFR 50.55a were not performed or were inadequately performed. The NRC expects that
 
recipients will review the information for applicability to their facilities and consider actions, as
 
appropriate, to avoid similar problems. However, suggestions contained in this IN are not NRC
 
requirements; therefore, no specific action or written response is required.


==DESCRIPTION OF CIRCUMSTANCES==
==DESCRIPTION OF CIRCUMSTANCES==
Palo Verde Nuclear Generating Station (Palo Verde), Unit 2 During an inservice inspection (ISI) at Palo Verde, Unit 2, NRC inspectors identified that the licensee had not adequately performed the required system leakage test of the reactor vessel flange leak-off lines, as described by ASME Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components." The licensee entered the issue into its corrective action program and submitted a proposed alternative examination to the Office of Nuclear Reactor Regulation (NRR) for review and authorizatio The proposed alternative employed a VT-2 visual examination of the accessible areas of the vessel flange leak-off lines while they were subjected to the static pressure head of water when the reactor cavity was filled, a pressure less than that required by ASME Code, Section XI, IWC-522 The NRC authorized the use of the proposed alternative in the licensee's ISI program (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13085A254). Additional information appears in "Palo Verde Nuclear Generating Station - NRC Integrated Inspection Report 05000528/2012005, 05000529/2012005, and 05000530/2012005," dated February 7, 2013 (ADAMS Accession No. ML13038A565).
Palo Verde Nuclear Generating Station (Palo Verde), Unit 2 During an inservice inspection (ISI) at Palo Verde, Unit 2, NRC inspectors identified that the
 
licensee had not adequately performed the required system leakage test of the reactor vessel
 
flange leak-off lines, as described by ASME Code, Section XI, Rules for Inservice Inspection of
 
Nuclear Power Plant Components. The licensee entered the issue into its corrective action
 
program and submitted a proposed alternative examination to the Office of Nuclear Reactor
 
Regulation (NRR) for review and authorization. The proposed alternative employed a VT-2 visual examination of the accessible areas of the vessel flange leak-off lines while they were
 
subjected to the static pressure head of water when the reactor cavity was filled, a pressure less
 
than that required by ASME Code, Section XI, IWC-5220. The NRC authorized the use of the
 
proposed alternative in the licensees ISI program (Agencywide Documents Access and
 
Management System (ADAMS) Accession No. ML13085A254).
 
ML13193A002 Additional information appears in Palo Verde Nuclear Generating Station - NRC Integrated
 
Inspection Report 05000528/2012005, 05000529/2012005, and 05000530/2012005, dated
 
February 7, 2013 (ADAMS Accession No. ML13038A565).
 
Arkansas Nuclear One (ANO), Unit 2 During an ISI at ANO, Unit 2, NRC inspectors questioned whether the reactor vessel flange seal


Arkansas Nuclear One (ANO), Unit 2 During an ISI at ANO, Unit 2, NRC inspectors questioned whether the reactor vessel flange seal leak-off line was included in the licensee's ISI program for Unit Even though the flange leak- off line was classified as ASME Code Class 2, the licensee failed to incorporate the flange leak- off line into their ISI program and failed to perform the system leakage test and associated VT-2 visual examination, required by subparagraph IWC-5221 of ASME Code, Section XI, during prior 10-year interval The licensee performed a VT-2 visual examination of the accessible areas of the vessel flange leak-off line while the reactor vessel head was removed and the reactor cavity was filled to its normal refueling water leve Since the static pressure head developed by the refueling water level was less than the pressure required by ASME Code, Section XI, the licensee requested and received authorization of this alternative from the NRC (ADAMS Accession No. ML13161A241).
leak-off line was included in the licensees ISI program for Unit 2. Even though the flange leak- off line was classified as ASME Code Class 2, the licensee failed to incorporate the flange leak- off line into their ISI program and failed to perform the system leakage test and associated VT-2 visual examination, required by subparagraph IWC-5221 of ASME Code, Section XI, during


Additional information appears in "Arkansas Nuclear One - NRC Integrated Inspection Report 05000313/2012005 and 05000368/2012005," dated February 13, 2013 (ADAMS Accession N ML13045A520).
prior 10-year intervals. The licensee performed a VT-2 visual examination of the accessible
 
areas of the vessel flange leak-off line while the reactor vessel head was removed and the
 
reactor cavity was filled to its normal refueling water level. Since the static pressure head
 
developed by the refueling water level was less than the pressure required by ASME Code, Section XI, the licensee requested and received authorization of this alternative from the NRC
 
(ADAMS Accession No. ML13161A241).
 
Additional information appears in Arkansas Nuclear One - NRC Integrated Inspection Report
 
05000313/2012005 and 05000368/2012005, dated February 13, 2013 (ADAMS Accession No.
 
ML13045A520).


==BACKGROUND==
==BACKGROUND==
Related NRC Requirements & Industry Standards As required by 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in Section XI of the ASME Code, to the extent practical within the limitations of design, geometry, and materials of construction of the component The regulations also require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), "Standards approved for incorporation by reference,"12 months prior to the start of the 120-month ISI program interval, subject to the limitations and modifications listed therei The ASME Code, Section XI, Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 require that a system leakage test be conducted in accordance with IWB-5220, IWC-5220, and IWD-5220 for Class 1, 2, and 3 pressure retaining components, respectively, prior to plant startup following each refueling outag Subarticle IWA-5200 of Section XI of the ASME Code specifies the system test requirement for pressure-retaining components and states that the system leakage tests shall be conducted at the pressure and temperature for Class 1, Class 2 and Class 3 components specified in IWB-5000, IWC-5000 and IWD-5000, respectivel
Related NRC Requirements & Industry Standards
 
As required by 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including
 
supports) must meet the requirements, except the design and access provisions and the
 
preservice examination requirements, set forth in Section XI of the ASME Code, to the extent
 
practical within the limitations of design, geometry, and materials of construction of the
 
components. The regulations also require that inservice examination of components and
 
system pressure tests conducted during the first 10-year interval and subsequent intervals
 
comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), Standards approved for incorporation by
 
reference,12 months prior to the start of the 120-month ISI program interval, subject to the
 
limitations and modifications listed therein.
 
The ASME Code, Section XI, Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 require that a
 
system leakage test be conducted in accordance with IWB-5220, IWC-5220, and IWD-5220 for
 
Class 1, 2, and 3 pressure retaining components, respectively, prior to plant startup following
 
each refueling outage.
 
Subarticle IWA-5200 of Section XI of the ASME Code specifies the system test requirement for
 
pressure-retaining components and states that the system leakage tests shall be conducted at
 
the pressure and temperature for Class 1, Class 2 and Class 3 components specified in
 
IWB-5000, IWC-5000 and IWD-5000, respectively.


==DISCUSSION==
==DISCUSSION==
The reactor head flange is sealed to the vessel flange by two concentric, self-energizing, metallic O-rings positioned inboard of the reactor vessel closure stud circl Potential O-ring leakage is monitored by the O-ring leak detection system that is comprised of the O-ring flange leak-off lines and supporting component The portions of the detection system that are classified as ASME Code Class components are subject to pressure testing as described by the applicable paragraphs of the ASME Code, Section XI, and, therefore, inadequate testing fails to be in compliance with NRC regulations as provided by 10 CFR 50.55a(g)(4). This IN provides examples of instances where the licensee did not perform, or inadequately performed, a system pressure test of the reactor vessel flange leak-off line
The reactor head flange is sealed to the vessel flange by two concentric, self-energizing, metallic O-rings positioned inboard of the reactor vessel closure stud circle. Potential O-ring
 
leakage is monitored by the O-ring leak detection system that is comprised of the O-ring flange
 
leak-off lines and supporting components. The portions of the detection system that are
 
classified as ASME Code Class components are subject to pressure testing as described by the
 
applicable paragraphs of the ASME Code, Section XI, and, therefore, inadequate testing fails to
 
be in compliance with NRC regulations as provided by 10 CFR 50.55a(g)(4). This IN provides
 
examples of instances where the licensee did not perform, or inadequately performed, a system
 
pressure test of the reactor vessel flange leak-off lines.


==CONTACT==
==CONTACT==
This IN requires no specific action or written respons Please direct any questions about this matter to the technical contacts listed below or to the appropriate NRC project manage /RA/ /RA/ Lawrence E. Kokajko, Director Michael C. Cheok, Director Division of Policy and Rulemaking Division of Construction Inspection Office of Nuclear Reactor Regulation and Operational Programs Office of New Reactors
This IN requires no specific action or written response. Please direct any questions about this
 
matter to the technical contacts listed below or to the appropriate NRC project manager.
 
/RA/                                   /RA/
Lawrence E. Kokajko, Director                 Michael C. Cheok, Director
 
Division of Policy and Rulemaking             Division of Construction Inspection
 
Office of Nuclear Reactor Regulation           and Operational Programs
 
Office of New Reactors


Technical Contacts: Isaac Anchondo, RIV Jay Wallace, NRR 817-200-1152 301-415-7638 E-mail: Isaac.Anchondo@nrc.gov E-mail: Jay.Wallace@nrc.gov
Technical Contacts:   Isaac Anchondo, RIV                   Jay Wallace, NRR


Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Librar
817-200-1152                          301-415-7638 E-mail: Isaac.Anchondo@nrc.gov        E-mail: Jay.Wallace@nrc.gov


==DISCUSSION==
Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library.
The reactor head flange is sealed to the vessel flange by two concentric, self-energizing, metallic O-rings positioned inboard of the reactor vessel closure stud circl Potential O-ring leakage is monitored by the O-ring leak detection system that is comprised of the O-ring flange leak-off lines and supporting component The portions of the detection system that are classified as ASME Code Class components are subject to pressure testing as described by the applicable paragraphs of the ASME Code, Section XI, and, therefore, inadequate testing fails to be in compliance with NRC regulations as provided by 10 CFR 50.55a(g)(4). This IN provides examples of instances where the licensee did not perform, or inadequately performed, a system pressure test of the reactor vessel flange leak-off line
 
ML13193A002                        *concurred via e-mail        TAC MF1794 NRR/DE        RIV/DRS                            NRR/DE                        NRR/DPR
 
OFFICE                                    Tech Editor*                        NRR/DE/D
 
ESGB          PSB2*                            EPNB/BC                        PGCB/PM
 
TLupold
 
NAME        JWallace      IAnchondo      JDougherty                          PHiland        MBanic
 
(DAlley for)
DATE        01/27/2014    02/11/2014        07/18/13        02/11/2014      01/29/2014      02/11/2014 NRR/DPR        NRR/DPR


==CONTACT==
OFFICE                                    NRO/DCIP/D        NRR/DPR/DD      NRR/DPR/D
This IN requires no specific action or written respons Please direct any questions about this matter to the technical contacts listed below or to the appropriate NRC project manage /RA/ /RA/ Lawrence E. Kokajko, Director Michael C. Cheok, Director Division of Policy and Rulemaking Division of Construction Inspection Office of Nuclear Reactor Regulation and Operational Programs Office of New Reactors


Technical Contacts: Isaac Anchondo, RIV Jay Wallace, NRR 817-200-1152 301-415-7638 E-mail: Isaac.Anchondo@nrc.gov E-mail: Jay.Wallace@nrc.gov
PGCB/LA      PGCB/ABC*
NAME        CHawes        SStuchell        MCheok          SBahadur        LKokajko


Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Librar ADAMS Accession No.: ML13193A002 *concurred via e-mail TAC MF1794 OFFICIAL RECORD COPY OFFICE NRR/DE ESGB RIV/DRS PSB2* Tech Editor* NRR/DE EPNB/BC NRR/DE/D NRR/DPR PGCB/PM NAME JWallace IAnchondo JDougherty TLupold (DAlley for) PHiland MBanic DATE 01/27/2014 02/11/2014 07/18/13 02/11/2014 01/29/2014 02/11/2014 OFFICE NRR/DPRPGCB/LA NRR/DPR PGCB/ABC* NRO/DCIP/D NRR/DPR/DD NRR/DPR/D NAME CHawes SStuchell MCheok SBahadur LKokajko DATE 02/12/2014 02/12/2014 2/21/2014 2/21/2014 2/25/2014}}
DATE       02/12/2014   02/12/2014       2/21/2014         2/21/2014       2/25/2014}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 17:05, 4 November 2019

Failure to Properly Pressure Test Reactor Vessel Flange Leak-Off Lines
ML13193A002
Person / Time
Issue date: 02/25/2014
From: Michael Cheok, Kokajko L
Division of Construction Inspection and Operational Programs, Division of Policy and Rulemaking
To:
Anchondo I, Wallace J
References
TAC MF1794 IN-14-002
Download: ML13193A002 (4)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

OFFICE OF NEW REACTORS

WASHINGTON, DC 20555-0001 February 25, 2014 NRC INFORMATION NOTICE 2014-02: FAILURE TO PROPERLY PRESSURE TEST

REACTOR VESSEL FLANGE LEAK-OFF LINES

ADDRESSEES

All holders of an operating license or construction permit for a nuclear power reactor under

Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of

Production and Utilization Facilities, except those who have permanently ceased operations

and have certified that fuel has been permanently removed from the reactor vessel.

All holders of and applicants for a power reactor early site permit, combined license, standard

design certification, standard design approval, or manufacturing license under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.

PURPOSE

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform

addressees of instances in which inspections of reactor vessel flange leak-off lines as required

by Section XI of the American Society of Mechanical Engineers (ASME) Code and, therefore,

10 CFR 50.55a were not performed or were inadequately performed. The NRC expects that

recipients will review the information for applicability to their facilities and consider actions, as

appropriate, to avoid similar problems. However, suggestions contained in this IN are not NRC

requirements; therefore, no specific action or written response is required.

DESCRIPTION OF CIRCUMSTANCES

Palo Verde Nuclear Generating Station (Palo Verde), Unit 2 During an inservice inspection (ISI) at Palo Verde, Unit 2, NRC inspectors identified that the

licensee had not adequately performed the required system leakage test of the reactor vessel

flange leak-off lines, as described by ASME Code,Section XI, Rules for Inservice Inspection of

Nuclear Power Plant Components. The licensee entered the issue into its corrective action

program and submitted a proposed alternative examination to the Office of Nuclear Reactor

Regulation (NRR) for review and authorization. The proposed alternative employed a VT-2 visual examination of the accessible areas of the vessel flange leak-off lines while they were

subjected to the static pressure head of water when the reactor cavity was filled, a pressure less

than that required by ASME Code,Section XI, IWC-5220. The NRC authorized the use of the

proposed alternative in the licensees ISI program (Agencywide Documents Access and

Management System (ADAMS) Accession No. ML13085A254).

ML13193A002 Additional information appears in Palo Verde Nuclear Generating Station - NRC Integrated

Inspection Report 05000528/2012005, 05000529/2012005, and 05000530/2012005, dated

February 7, 2013 (ADAMS Accession No. ML13038A565).

Arkansas Nuclear One (ANO), Unit 2 During an ISI at ANO, Unit 2, NRC inspectors questioned whether the reactor vessel flange seal

leak-off line was included in the licensees ISI program for Unit 2. Even though the flange leak- off line was classified as ASME Code Class 2, the licensee failed to incorporate the flange leak- off line into their ISI program and failed to perform the system leakage test and associated VT-2 visual examination, required by subparagraph IWC-5221 of ASME Code,Section XI, during

prior 10-year intervals. The licensee performed a VT-2 visual examination of the accessible

areas of the vessel flange leak-off line while the reactor vessel head was removed and the

reactor cavity was filled to its normal refueling water level. Since the static pressure head

developed by the refueling water level was less than the pressure required by ASME Code,Section XI, the licensee requested and received authorization of this alternative from the NRC

(ADAMS Accession No. ML13161A241).

Additional information appears in Arkansas Nuclear One - NRC Integrated Inspection Report 05000313/2012005 and 05000368/2012005, dated February 13, 2013 (ADAMS Accession No.

ML13045A520).

BACKGROUND

Related NRC Requirements & Industry Standards

As required by 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including

supports) must meet the requirements, except the design and access provisions and the

preservice examination requirements, set forth in Section XI of the ASME Code, to the extent

practical within the limitations of design, geometry, and materials of construction of the

components. The regulations also require that inservice examination of components and

system pressure tests conducted during the first 10-year interval and subsequent intervals

comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), Standards approved for incorporation by

reference,12 months prior to the start of the 120-month ISI program interval, subject to the

limitations and modifications listed therein.

The ASME Code,Section XI, Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 require that a

system leakage test be conducted in accordance with IWB-5220, IWC-5220, and IWD-5220 for

Class 1, 2, and 3 pressure retaining components, respectively, prior to plant startup following

each refueling outage.

Subarticle IWA-5200 of Section XI of the ASME Code specifies the system test requirement for

pressure-retaining components and states that the system leakage tests shall be conducted at

the pressure and temperature for Class 1, Class 2 and Class 3 components specified in

IWB-5000, IWC-5000 and IWD-5000, respectively.

DISCUSSION

The reactor head flange is sealed to the vessel flange by two concentric, self-energizing, metallic O-rings positioned inboard of the reactor vessel closure stud circle. Potential O-ring

leakage is monitored by the O-ring leak detection system that is comprised of the O-ring flange

leak-off lines and supporting components. The portions of the detection system that are

classified as ASME Code Class components are subject to pressure testing as described by the

applicable paragraphs of the ASME Code,Section XI, and, therefore, inadequate testing fails to

be in compliance with NRC regulations as provided by 10 CFR 50.55a(g)(4). This IN provides

examples of instances where the licensee did not perform, or inadequately performed, a system

pressure test of the reactor vessel flange leak-off lines.

CONTACT

This IN requires no specific action or written response. Please direct any questions about this

matter to the technical contacts listed below or to the appropriate NRC project manager.

/RA/ /RA/

Lawrence E. Kokajko, Director Michael C. Cheok, Director

Division of Policy and Rulemaking Division of Construction Inspection

Office of Nuclear Reactor Regulation and Operational Programs

Office of New Reactors

Technical Contacts: Isaac Anchondo, RIV Jay Wallace, NRR

817-200-1152 301-415-7638 E-mail: Isaac.Anchondo@nrc.gov E-mail: Jay.Wallace@nrc.gov

Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library.

ML13193A002 *concurred via e-mail TAC MF1794 NRR/DE RIV/DRS NRR/DE NRR/DPR

OFFICE Tech Editor* NRR/DE/D

ESGB PSB2* EPNB/BC PGCB/PM

TLupold

NAME JWallace IAnchondo JDougherty PHiland MBanic

(DAlley for)

DATE 01/27/2014 02/11/2014 07/18/13 02/11/2014 01/29/2014 02/11/2014 NRR/DPR NRR/DPR

OFFICE NRO/DCIP/D NRR/DPR/DD NRR/DPR/D

PGCB/LA PGCB/ABC*

NAME CHawes SStuchell MCheok SBahadur LKokajko

DATE 02/12/2014 02/12/2014 2/21/2014 2/21/2014 2/25/2014


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