Information Notice 1990-68, Stress Corrosion Cracking of Reactor Coolant Pump Bolts: Difference between revisions

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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:UNITED STATES                         K--
                          NUCLEAR REGULATORY COMMISSION


COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION


===OFFICE OF NUCLEAR REACTOR REGULATION===
WASHINGTON, D.C. 20555 October 30, 1990
WASHINGTON, D.C. 20555 K--October 30, 1990 NRC INFORMATION
NRC INFORMATION NOTICE NO. 90-68:  STRESS CORROSION CRACKING OF REACTOR


NOTICE NO. 90-68: STRESS CORROSION
COOLANT PUMP BOLTS
 
CRACKING OF REACTOR COOLANT PUMP BOLTS


==Addressees==
==Addressees==
:
:
All holders of operating
All holders of operating licenses or construction permits for pressurized water
 
licenses or construction
 
permits for pressurized


water reactors (PWRs).
reactors (PWRs).


==Purpose==
==Purpose==
: This information
:
This information notice is intended to alert addressees of a significant event


notice is intended to alert addressees
which occurred at a foreign reactor. The event involves the use of a material


of a significant
sensitive to intergranular stress corrosion cracking (IGSCC) in the fabrication


event which occurred at a foreign reactor. The event involves the use of a material sensitive
of the bolts fastening the turning vanes of the reactor coolant pumps.   It is


to intergranular
expected that recipients will review the information for applicability to their


stress corrosion
facilities and consider actions, as appropriate, to avoid similar problems.


cracking (IGSCC) in the fabrication
However, suggestions contained in this information notice do not constitute NRC


of the bolts fastening
requirements; therefore, no specific action or written response is required.


the turning vanes of the reactor coolant pumps. It is expected that recipients
==Description of Circumstances==
:
The U.S. Nuclear Regulatory Commission (NRC) has received information concerning


will review the information
cracking of the bolts fastening the turning vanes of the reactor coolant pumps


for applicability
at a foreign reactor plant. There are 23 bolts fastening the turning vanes in


to their facilities
each of three reactor coolant pumps. Five of these bolts had experienced stress


and consider actions, as appropriate, to avoid similar problems.However, suggestions
corrosion cracking. The bolts were made of a stainless steel all'y which is


contained
designated by the American Society for Testing and Materials as A453 grade 660.


in this information
The material is commonly described commercially as alloy A-286. The reactor


notice do not constitute
coolant pumps are similar in design to those manufactured by the Westinghouse


NRC requirements;
Electric Company.
therefore, no specific action or written response is required.Description


of Circumstances:
Considerable information has previously been available regarding the suscepti- bility of alloy A-286 to IGSCC. For example, licensees of U.S. reactors
The U.S. Nuclear Regulatory


Commission (NRC) has received information
designed by Babcock and Wilcox (B&W) have noted stress corrosion cracking of


concerning
bolts fabricated of alloy A-286. Specifically, bolts fastening the B&W reactor


cracking of the bolts fastening
internals, including the core barrel and lower thermal shield, were fabricated


the turning vanes of the reactor coolant pumps at a foreign reactor plant. There are 23 bolts fastening
of alloy A-286. Between 1981 and 1984, bolt cracking and indication of cracking


the turning vanes in each of three reactor coolant pumps. Five of these bolts had experienced
were documented at Oconee, Rancho Seco, Crystal River and Arkansas Unit 1. In


stress corrosion
response, the B&W owners group formed a special task force to study the internal


cracking.
bolts of the reactor vessel. This task force documented its conclusions in


The bolts were made of a stainless
BAW-1842, "The B&W Owners Group Evaluation of Internals Bolting Concerns in 177 FA Plants," August 1984. The task force concluded that bolts fabricated


steel all'y which is designated
9010240315 LA-


by the American Society for Testing and Materials
IN 90-68 October 30, 1990 of alloy A-286 are subject to IGSCC at peak stresses above 100 ksi. The


as A453 grade 660.The material is commonly described
occurrence of IGSCC also appeared to be a function of chromium content, fabrication practice and environment. As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use


commercially
fastener materials that are less sensitive to IGSCC than alloy A-286-or to


as alloy A-286. The reactor coolant pumps are similar in design to those manufactured
reduce the maximum stress loadings of bolts fabricated of alloy A-286 to less


by the Westinghouse
than 100 ksi.


Electric Company.Considerable
In addition, the Brookhaven National Laboratory (BNL) performed an extensive


information
study of bolting which is documented in NUREG/CR-3604, "Bolting Applications,"
May 1984. The report discusses the direct relationship between loading and


has previously
IGSCC of bolts fabricated of alloy A-286. In this report, BNL recommended


been available
that alloy A-286 not be used as a reactor structural material because of its


regarding
susceptibility to IGSCC.


the suscepti-bility of alloy A-286 to IGSCC. For example, licensees
This information notice requires no specific action or written response.     If


of U.S. reactors designed by Babcock and Wilcox (B&W) have noted stress corrosion
you have any questions about this matter, please contact one of the


cracking of bolts fabricated
technical contacts listed below or the appropriate NRR project manager.


of alloy A-286. Specifically, bolts fastening
_                              *:a~rlesv NM , riector


the B&W reactor internals, including
E.


the core barrel and lower thermal shield, were fabricated
Division ofOperation-ar Events Assensment*-
                                    Office of Nuclear Reactor Regulation


of alloy A-286. Between 1981 and 1984, bolt cracking and indication
Technical Contacts:  Clifford Sellers, NRR


of cracking were documented
(301) 492-0703 Walton Jensen, NRR


at Oconee, Rancho Seco, Crystal River and Arkansas Unit 1. In response, the B&W owners group formed a special task force to study the internal bolts of the reactor vessel. This task force documented
(301) 492-1157 Attachment:  List of Recently Issued NRC Information Notices


its conclusions
Attachment 1 IN 90-68 October 30, 1990 LIST OF RECENTLY ISSUED


in BAW-1842, "The B&W Owners Group Evaluation
NRC INFORMATION NOTICES


of Internals
Information                                    Date of


Bolting Concerns in 177 FA Plants," August 1984. The task force concluded
Notice No.               Subject              Issuance    Issued to


that bolts fabricated
90-67          Potential Security Equipment    10/29/90    All holders of OLs


9010240315 LA-
Weaknesses                                  or CPs for
IN 90-68 October 30, 1990 of alloy A-286 are subject to IGSCC at peak stresses above 100 ksi. The occurrence


of IGSCC also appeared to be a function of chromium content, fabrication
nuclear power


practice and environment.
reactors and


As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use fastener materials
Category I fuel


that are less sensitive
facilities.


to IGSCC than alloy A-286-or to reduce the maximum stress loadings of bolts fabricated
90-66            Incomplete Draining and        10/25/90    All holders of OLs


of alloy A-286 to less than 100 ksi.In addition, the Brookhaven
Drying of Shipping Casks                      for nuclear


National Laboratory (BNL) performed
power reactors


an extensive study of bolting which is documented
and all registered


in NUREG/CR-3604, "Bolting Applications," May 1984. The report discusses
users of NRC


the direct relationship
approved waste


between loading and IGSCC of bolts fabricated
shipping packages.


of alloy A-286. In this report, BNL recommended
88-63,         High Radiation Hazards          10/5/90      All holders of OLs


that alloy A-286 not be used as a reactor structural
Supp. 1      4robimrria3'ated Incore                        or CPs for nuclear


material because of its susceptibility
Detectors and Cables                        power reactors.


to IGSCC.This information
90-65          Recent Orifice Plate            10/5/90      All holders of OLs


notice requires no specific action or written response.
Problems                                    or CPs for nuclear


If you have any questions
power reactors.


about this matter, please contact one of the technical
90-64          Potential for Common-Mode      10/4/90      All holders of OLs


contacts listed below or the appropriate
Failure Of High Pressure                    or CPs for pres- Safety Injection Pumps or                    surized-water


NRR project manager._ *:a~rlesv
Release of Reactor Coolant                    reactors.


E. NM , riector Division ofOperation-ar
Outside Containment During


Events Assensment*-
A Loss-Of-Coolant Accident


===Office of Nuclear Reactor Regulation===
90-63          Management Attention to the    10/3/90      All fuel cycle
Technical


Contacts:
Establishment and Main-                     licensees possess- tenance of A Nuclear                        ing more than
Clifford Sellers, NRR (301) 492-0703 Walton Jensen, NRR (301) 492-1157 Attachment:
List of Recently Issued NRC Information


Notices
Criticality Safety Program                  critical mass


Attachment
quantities of


1 IN 90-68 October 30, 1990 LIST OF RECENTLY ISSUED NRC INFORMATION
special nuclear


NOTICES Information
material.


Date of Notice No. Subject Issuance Issued to 90-67 90-66 88-63, Supp. 1 90-65 90-64 90-63 Potential
OL = Operating License


===Security Equipment Weaknesses===
CP = Construction Permit
Incomplete


Draining and Drying of Shipping Casks High Radiation
IN 90-68 October 30, 1990 of alloy A-286 are subject to IGSCC at peak stresses above 100 ksi. The


Hazards 4robimrria3'ated
occurrence of IGSCC also appeared to be a function of chromium content, fabrication practice and environment. As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use


Incore Detectors
fastener materials that are less sensitive to IGSCC than alloy A-286 or to


and Cables Recent Orifice Plate Problems Potential
reduce the maximum stress loadings of bolts fabricated of alloy A-286 to less


for Common-Mode
than 100 ksi.


Failure Of High Pressure Safety Injection
In addition, the Brookhaven National Laboratory (BNL) performed an extensive


Pumps or Release of Reactor Coolant Outside Containment
study of bolting which is documented in NUREG/CR-3604, "Bolting Applications,"
May 1984. The report discusses the direct relationship between loading and


During A Loss-Of-Coolant
IGSCC of bolts fabricated of alloy A-286. In this report, BNL recommended


Accident Management
that alloy A-286 not be used as a reactor structural material because of its


Attention
susceptibility to IGSCC.


to the Establishment
This information notice requires no specific action or written response. If


and Main-tenance of A Nuclear Criticality
you have any questions about this matter, please contact one of the


Safety Program 10/29/90 10/25/90 10/5/90 10/5/90 10/4/90 10/3/90 All holders of OLs or CPs for nuclear power reactors and Category I fuel facilities.
technical contacts listed below or the appropriate NRR project manager.


All holders of OLs for nuclear power reactors and all registered
Odginal Signed by


users of NRC approved waste shipping packages.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for pres-surized-water
Charles E. Rossi, Director Chades E.Rossi


reactors.All fuel cycle licensees
Division of Operational Events Assessment


possess-ing more than critical mass quantities
Office of Nuclear Reactor Regulation


of special nuclear material.OL = Operating
Technical Contacts:    Clifford Sellers, NRR


License CP = Construction
(301) 492-0703 Walton Jensen, NRR


Permit
(301) 492-1157 Attachment:  List of Recently Issued NRC Information Notices


IN 90-68 October 30, 1990 of alloy A-286 are subject to IGSCC at peak stresses above 100 ksi. The occurrence
*SEE PREVIOUS CONCURRENCE


of IGSCC also appeared to be a function of chromium content, fabrication
NRR:EAB        NRR:EAB        TECH ED        GPA:IP          NRR:EMCB


practice and environment.
*WJensen        *NPKadambi                      *KBurke        *CSellers


As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use fastener materials
08/01/90        08/13/90        07/27/90        08/21/90      08/10/90
  NRR:EMCB      NRR:DET          NRR: EAB        NRR:GCB


that are less sensitive
*CYCheng        *JRichardson    *PBaranowsky    *CBerlinger


to IGSCC than alloy A-286 or to reduce the maximum stress loadings of bolts fabricated
08/27/90        08/27/90        09/06/90        10/19/90      10/290
  DOCUMENT NAME:  IN 90-68


of alloy A-286 to less than 100 ksi.In addition, the Brookhaven
IN 90-XX


National Laboratory (BNL) performed
October XX, 1990 of alloy A-2&6 are subject to IGSCC at peak stresses above 100 ksl. The


an extensive study of bolting which is documented
occurrence of IGSCC also appeared to be a function of chromium content, fabrication practice and environment. As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use


in NUREG/CR-3604, "Bolting Applications," May 1984. The report discusses
fastener materials that are less sensitive to IGSCC than alloy A-286 or to


the direct relationship
reduce the maximum stress loadings of bolts fabricated of alloy A-286 to less


between loading and IGSCC of bolts fabricated
than 100 ksi.


of alloy A-286. In this report, BNL recommended
In addition, the Brookhaven national Laboratory (BNL) performed an extensive


that alloy A-286 not be used as a reactor structural
study of bolting which is documented in NUREG/CP-3604, "Bolting Applications,"
May 1984. The report discusses the direct relationship between loading and


material because of its susceptibility
IGSCC of bolts fabricated of alloy A-286. In this report, BNL recommended


to IGSCC.This information
that alloy A-286 not be used as a reactor structural material because of its


notice requires no specific action or written response.
susceptibility to IGSCC.


If you have any questions
This information notice requires no specific action or written response. If


about this matter, please contact one of the technical
you have any questions about this matter, please contact one of the(tiO-
technical contacts listed below or the appropriate NRR project manager.


contacts listed below or the appropriate
Charles E. Rossi, Director


NRR project manager.Odginal Signed by Charles E. Rossi, Director Chades E. Rossi Division of Operational
Division of Operational Events Assessment


===Events Assessment===
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Technical
Technical Contacts:    Clifford Sellers, NRR


Contacts: Clifford Sellers, NRR (301) 492-0703 Walton Jensen, NRR (301) 492-1157 List of Recently Issued NRC Information
(301) 492-0703 Walton Jensen, NRR


Notices Attachment:
(301) 492-1157 Attachment:   List of Recently Issued NRC Information Notices
*SEE PREVIOUS NRR:EAB*WJensen 08/01/90 NRR:EMCB*CYCheng 08/27/90 CONCURRENCE


NRR:EAB*NPKadambi
*SEE PdEVIOUS CONCURRENCE


08/13/90 NRR:DET*JRichardson
NRR:EAE          PRR:EAB        TECH ED        GPA:IP        NRP:EHCB


08/27/90 TECH ED 07/27/90 NRR: EAB*PBaranowsky
*VJ1ensen        *NPKadambi                      *KBurke        *CSel lers


09/06/90 GPA:IP*KBurke 08/21/90 NRR:GCB*CBerlinger
08/01/90        08/13/90       07/27/90        08/21/90       08/10/90
NRR:EMCE        NPR:DET        NPR:EAB        N :GCE        NRR:DOE,
*CYCheng        *J~ichardson    *P~aranowsky v Berlinger      CRossi t


10/19/90 NRR:EMCB*CSellers 08/10/90 10/290 DOCUMENT NAME: IN 90-68 IN 90-XX October XX, 1990 of alloy A-2&6 are subject to IGSCC at peak stresses above 100 ksl. The occurrence
08/27/90         08/27/90       09/06/90     q  ecWW  9      09/  /90
                                                201(/l


of IGSCC also appeared to be a function of chromium content, fabrication
DOCUIMENT NAME:  INBOLT


practice and environment.
IN 90-XX


As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use fastener materials
July XX, 1990 materials that are


that are less sensitive
internal bolts was modified at B&W plants to use fastener    the maximum stress


to IGSCC than alloy A-286 or to reduce the maximum stress loadings of bolts fabricated
less sensitive to IGSCC than alloy A-286 or to reduce     than 100 ksi.


of alloy A-286 to less than 100 ksi.In addition, the Brookhaven
loadings of bolts fabricated of alloy A-286 to less


national Laboratory (BNL) performed
an extensive study of bolting


an extensive study of bolting which is documented
The Brookhaven National Laboratory (BNL) performed                      "Bolting


in NUREG/CP-3604, "Bolting Applications," May 1984. The report discusses
for the NRC staff. This study is documented in NUREG/CR-3604, direct  relationship  between


the direct relationship
Applications," May 1984. The report discusses the           In  this  report,  BNL


between loading and IGSCC of bolts fabricated
loading and IGSCC of bolts fabricated of alloy A-286. structural material


of alloy A-286. In this report, BNL recommended
recommended that alloy     A-286 not  be  used as a reactor


that alloy A-286 not be used as a reactor structural
because of its susceptibility to IGSCC.


material because of its susceptibility
or written response. If


to IGSCC.This information
This information notice requires no specific action    contact  one of the the


notice requires no specific action or written response.
you have any questions about this matter, please          NRR  project  manager.


If you have any questions
technical contacts listed below or the appropriate


about this matter, please contact one of the(tiO-technical
Charles E. Rossi, Director


contacts listed below or the appropriate
Division of Operational Events Assessment


NRR project manager.Charles E. Rossi, Director Division of Operational
===Events Assessment===
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Technical
Technical Contacts:     Clifford Sellers, NRR
 
Contacts: Clifford Sellers, NRR (301) 492-0703 Walton Jensen, NRR (301) 492-1157 Attachment:
List of Recently Issued NRC Information
 
Notices*SEE PdEVIOUS NRR:EAE*VJ1ensen 08/01/90 NRR:EMCE*CYCheng 08/27/90 CONCURRENCE
 
PRR:EAB*NPKadambi
 
08/13/90 NPR:DET*J~ichardson
 
08/27/90 TECH ED GPA:IP*KBurke 07/27/90 08/21/90 NPR:EAB N :GCE*P~aranowsky
 
v Berlinger 09/06/90 q ecWW 9 201(/l NRP:EHCB*CSel lers 08/10/90 NRR:DOE, CRossi t 09/ /90 DOCUIMENT
 
NAME: INBOLT
 
IN 90-XX July XX, 1990 internal bolts was modified at B&W plants to use fastener materials
 
that are less sensitive


to IGSCC than alloy A-286 or to reduce the maximum stress loadings of bolts fabricated
(301) 492-0703 Walton Jensen, NRR


of alloy A-286 to less than 100 ksi.The Brookhaven
(301) 492-1157 Attachment:  List of Recently Issued NRC Information Notices


National Laboratory (BNL) performed
DISTRIBUTION:
  CRossi                DOEA r/f


an extensive
WJensen              EAB r/f


study of bolting for the NRC staff. This study is documented
NPKadambi            Central Files


in NUREG/CR-3604, "Bolting Applications," May 1984. The report discusses
CSellers              JRichardson


the direct relationship
PBaranowsky          CBerlinger


between loading and IGSCC of bolts fabricated
V If


of alloy A-286. In this report, BNL recommended
*SEE PREVIOUS CONCURRENCE                      -XGPA: P        -rNRR:EMCB      c<;
 
  NRR:EAB        NRR:EAB        *TECH ED
that alloy A-286 not be used as a reactor structural
 
material because of its susceptibility
 
to IGSCC.This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about this matter, please contact one of the the technical
 
contacts listed below or the appropriate
 
NRR project manager.Charles E. Rossi, Director Division of Operational
 
===Events Assessment===
Office of Nuclear Reactor Regulation


Technical
*NPKadambi                          KBurke            CSellers


Contacts: Clifford Sellers, NRR (301) 492-0703 Walton Jensen, NRR (301) 492-1157 Attachment:
*WJensen                                                            08/10/90
List of Recently Issued NRC Information
  08/01/90        08/13/90        07/27/90        08/21/90
                  NRR:DEf4        NRRffM                            NRR:DOEA


Notices DISTRIBUTION:
NRR:E                                                              CRossi


===CRossi WJensen NPKadambi CSellers PBaranowsky===
CYCh d ''      JRichardo        P aranowsky
DOEA r/f EAB r/f Central Files JRichardson


CBerlinger
o8.7 o          08'/            IC 6/90
  DOCUMENT NAME:  INBOLT


V If-XGPA: P -rNRR:EMCB
IN 90-XX


c<;KBurke CSellers 08/21/90 08/10/90*SEE PREVIOUS CONCURRENCE
July XX, 1 0
                                                                            Page 2 o 2 fastener materials hat are


NRR:EAB NRR:EAB*WJensen *NPKadambi
internal bolts was modified at B&W plants to usereduce          the maximum tress


08/01/90 08/13/90 NRR:E NRR:DEf4 CYCh d '' JRichardo o8.7 o 08'/*TECH ED 07/27/90 NRRffM P aranowsky IC 6/90 NRR:DOEA CRossi DOCUMENT NAME: INBOLT
less sensitive to IGSCC than alloy A-286 or to                than  100 ksi


IN 90-XX July XX, 1 0 Page 2 o 2 internal bolts was modified at B&W plants to use fastener materials
loadings of bolts fabricated of alloy A-286 to less


hat are less sensitive
an extensi      study of bolting


to IGSCC than alloy A-286 or to reduce the maximum tress loadings of bolts fabricated
The Brookhaven National Laboratory (BNL) performed                      , 'Bolting


of alloy A-286 to less than 100 ksi The Brookhaven
for the NRC staff. This study is documented in          NUREG/CR-36 elationship between


National Laboratory (BNL) performed
Applications,u May 1984. The report discusses the direct        In  ihs report, BNL


an extensi study of bolting for the NRC staff. This study is documented
loading and IGSCC of bolts fabricated of alloy A-286. s ructural material


in NUREG/CR-36 , 'Bolting Applications,u
recommended that alloy A-286 not be used as a reactor


May 1984. The report discusses
because of its susceptibility to IGSCC.


the direct elationship
written response.  If


between loading and IGSCC of bolts fabricated
This information notice requires no specific actio or              one of the the


of alloy A-286. In ihs report, BNL recommended
ntact


that alloy A-286 not be used as a reactor s ructural material because of its susceptibility
you have any questions about this matter, please                  project  manager.


to IGSCC.This information
technical contacts listed below or the appropria            NRR


notice requires no specific actio or written response.
Charles E. ossi, Director


If you have any questions
Division f Operational Events Assessment


about this matter, please ntact one of the the technical
Office    Nuclear Reactor Regulation


contacts listed below or the appropria
Technical Contacts:    Clifford Sellers,        R


NRR project manager.Charles E. ossi, Director Division f Operational
(301) 492-0703 Walton Jensen,       RR


===Events Assessment===
(301) 492-11 Attachment:    List of Recently    ssued NRC Information Notices
Office Nuclear Reactor Regulation


Technical
DISTRIBUTION:
  CRossi                DOEA /f


Contacts:
WJensen              EAB f
Clifford Sellers, R (301) 492-0703 Walton Jensen, RR (301) 492-11 Attachment:
List of Recently ssued NRC Information


Notices DISTRIBUTION:
NPKadambi             C tral Files
CRossi DOEA /f WJensen EAB f NPKadambi


===C tral Files CSellers Richardson===
CSellers               Richardson
PBaranowsky


Ceerlginger
PBaranowsky          Ceerlginger                                                         )C, 1+ v


NRRR: RR:EAB TECH E GPA:IP NRR:EMCB W NPKadambi
RR:EAB         TECH E             GPA:IP           NRR:EMCB


.4NA// KBurke CSellers DA CJ (00/// 90 07/ i/90 &z4 /90 GR/ /90 O-/NRR: T NRR:EAB NRR:GCB NRR:DOEA JRi ardson PBaranowsky
NRRR:
                                                      KBurke           CSellers DA     CJ (
  W              NPKadambi          .4NA//
                                                                                        O-/
                          90       07/i/90             &z4 /90         GR/ /90
  00///
  NRR: T           NRR:EAB         NRR:GCB           NRR:DOEA


CBerlinger
JRi ardson      PBaranowsky      CBerlinger         CRossi


CRossi 07 /90 07/ /90 07/ /90 DOCUMENT NAME: INBOLT)C, 1+ v}}
07   /90       07/ /90         07/ /90
  DOCUMENT NAME:   INBOLT}}


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

Latest revision as of 04:03, 24 November 2019

Stress Corrosion Cracking of Reactor Coolant Pump Bolts
ML031130215
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 10/30/1990
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-90-068, NUDOCS 9010240315
Download: ML031130215 (8)
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UNITED STATES K--

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 October 30, 1990

NRC INFORMATION NOTICE NO. 90-68: STRESS CORROSION CRACKING OF REACTOR

COOLANT PUMP BOLTS

Addressees

All holders of operating licenses or construction permits for pressurized water

reactors (PWRs).

Purpose

This information notice is intended to alert addressees of a significant event

which occurred at a foreign reactor. The event involves the use of a material

sensitive to intergranular stress corrosion cracking (IGSCC) in the fabrication

of the bolts fastening the turning vanes of the reactor coolant pumps. It is

expected 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 information notice do not constitute NRC

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

Description of Circumstances

The U.S. Nuclear Regulatory Commission (NRC) has received information concerning

cracking of the bolts fastening the turning vanes of the reactor coolant pumps

at a foreign reactor plant. There are 23 bolts fastening the turning vanes in

each of three reactor coolant pumps. Five of these bolts had experienced stress

corrosion cracking. The bolts were made of a stainless steel all'y which is

designated by the American Society for Testing and Materials as A453 grade 660.

The material is commonly described commercially as alloy A-286. The reactor

coolant pumps are similar in design to those manufactured by the Westinghouse

Electric Company.

Considerable information has previously been available regarding the suscepti- bility of alloy A-286 to IGSCC. For example, licensees of U.S. reactors

designed by Babcock and Wilcox (B&W) have noted stress corrosion cracking of

bolts fabricated of alloy A-286. Specifically, bolts fastening the B&W reactor

internals, including the core barrel and lower thermal shield, were fabricated

of alloy A-286. Between 1981 and 1984, bolt cracking and indication of cracking

were documented at Oconee, Rancho Seco, Crystal River and Arkansas Unit 1. In

response, the B&W owners group formed a special task force to study the internal

bolts of the reactor vessel. This task force documented its conclusions in

BAW-1842, "The B&W Owners Group Evaluation of Internals Bolting Concerns in 177 FA Plants," August 1984. The task force concluded that bolts fabricated

9010240315 LA-

IN 90-68 October 30, 1990 of alloy A-286 are subject to IGSCC at peak stresses above 100 ksi. The

occurrence of IGSCC also appeared to be a function of chromium content, fabrication practice and environment. As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use

fastener materials that are less sensitive to IGSCC than alloy A-286-or to

reduce the maximum stress loadings of bolts fabricated of alloy A-286 to less

than 100 ksi.

In addition, the Brookhaven National Laboratory (BNL) performed an extensive

study of bolting which is documented in NUREG/CR-3604, "Bolting Applications,"

May 1984. The report discusses the direct relationship between loading and

IGSCC of bolts fabricated of alloy A-286. In this report, BNL recommended

that alloy A-286 not be used as a reactor structural material because of its

susceptibility to IGSCC.

This information notice requires no specific action or written response. If

you have any questions about this matter, please contact one of the

technical contacts listed below or the appropriate NRR project manager.

_ *:a~rlesv NM , riector

E.

Division ofOperation-ar Events Assensment*-

Office of Nuclear Reactor Regulation

Technical Contacts: Clifford Sellers, NRR

(301) 492-0703 Walton Jensen, NRR

(301) 492-1157 Attachment: List of Recently Issued NRC Information Notices

Attachment 1 IN 90-68 October 30, 1990 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

90-67 Potential Security Equipment 10/29/90 All holders of OLs

Weaknesses or CPs for

nuclear power

reactors and

Category I fuel

facilities.

90-66 Incomplete Draining and 10/25/90 All holders of OLs

Drying of Shipping Casks for nuclear

power reactors

and all registered

users of NRC

approved waste

shipping packages.

88-63, High Radiation Hazards 10/5/90 All holders of OLs

Supp. 1 4robimrria3'ated Incore or CPs for nuclear

Detectors and Cables power reactors.

90-65 Recent Orifice Plate 10/5/90 All holders of OLs

Problems or CPs for nuclear

power reactors.

90-64 Potential for Common-Mode 10/4/90 All holders of OLs

Failure Of High Pressure or CPs for pres- Safety Injection Pumps or surized-water

Release of Reactor Coolant reactors.

Outside Containment During

A Loss-Of-Coolant Accident

90-63 Management Attention to the 10/3/90 All fuel cycle

Establishment and Main- licensees possess- tenance of A Nuclear ing more than

Criticality Safety Program critical mass

quantities of

special nuclear

material.

OL = Operating License

CP = Construction Permit

IN 90-68 October 30, 1990 of alloy A-286 are subject to IGSCC at peak stresses above 100 ksi. The

occurrence of IGSCC also appeared to be a function of chromium content, fabrication practice and environment. As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use

fastener materials that are less sensitive to IGSCC than alloy A-286 or to

reduce the maximum stress loadings of bolts fabricated of alloy A-286 to less

than 100 ksi.

In addition, the Brookhaven National Laboratory (BNL) performed an extensive

study of bolting which is documented in NUREG/CR-3604, "Bolting Applications,"

May 1984. The report discusses the direct relationship between loading and

IGSCC of bolts fabricated of alloy A-286. In this report, BNL recommended

that alloy A-286 not be used as a reactor structural material because of its

susceptibility to IGSCC.

This information notice requires no specific action or written response. If

you have any questions about this matter, please contact one of the

technical contacts listed below or the appropriate NRR project manager.

Odginal Signed by

Charles E. Rossi, Director Chades E.Rossi

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Clifford Sellers, NRR

(301) 492-0703 Walton Jensen, NRR

(301) 492-1157 Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCE

NRR:EAB NRR:EAB TECH ED GPA:IP NRR:EMCB

  • WJensen *NPKadambi *KBurke *CSellers

08/01/90 08/13/90 07/27/90 08/21/90 08/10/90

NRR:EMCB NRR:DET NRR: EAB NRR:GCB

  • CYCheng *JRichardson *PBaranowsky *CBerlinger

08/27/90 08/27/90 09/06/90 10/19/90 10/290

DOCUMENT NAME: IN 90-68

IN 90-XX

October XX, 1990 of alloy A-2&6 are subject to IGSCC at peak stresses above 100 ksl. The

occurrence of IGSCC also appeared to be a function of chromium content, fabrication practice and environment. As a result of the task force findings, the design of the reactor internal bolts was modified at B&W plants to use

fastener materials that are less sensitive to IGSCC than alloy A-286 or to

reduce the maximum stress loadings of bolts fabricated of alloy A-286 to less

than 100 ksi.

In addition, the Brookhaven national Laboratory (BNL) performed an extensive

study of bolting which is documented in NUREG/CP-3604, "Bolting Applications,"

May 1984. The report discusses the direct relationship between loading and

IGSCC of bolts fabricated of alloy A-286. In this report, BNL recommended

that alloy A-286 not be used as a reactor structural material because of its

susceptibility to IGSCC.

This information notice requires no specific action or written response. If

you have any questions about this matter, please contact one of the(tiO-

technical contacts listed below or the appropriate NRR project manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Clifford Sellers, NRR

(301) 492-0703 Walton Jensen, NRR

(301) 492-1157 Attachment: List of Recently Issued NRC Information Notices

  • SEE PdEVIOUS CONCURRENCE

NRR:EAE PRR:EAB TECH ED GPA:IP NRP:EHCB

  • VJ1ensen *NPKadambi *KBurke *CSel lers

08/01/90 08/13/90 07/27/90 08/21/90 08/10/90

NRR:EMCE NPR:DET NPR:EAB N :GCE NRR:DOE,

  • CYCheng *J~ichardson *P~aranowsky v Berlinger CRossi t

08/27/90 08/27/90 09/06/90 q ecWW 9 09/ /90

201(/l

DOCUIMENT NAME: INBOLT

IN 90-XX

July XX, 1990 materials that are

internal bolts was modified at B&W plants to use fastener the maximum stress

less sensitive to IGSCC than alloy A-286 or to reduce than 100 ksi.

loadings of bolts fabricated of alloy A-286 to less

an extensive study of bolting

The Brookhaven National Laboratory (BNL) performed "Bolting

for the NRC staff. This study is documented in NUREG/CR-3604, direct relationship between

Applications," May 1984. The report discusses the In this report, BNL

loading and IGSCC of bolts fabricated of alloy A-286. structural material

recommended that alloy A-286 not be used as a reactor

because of its susceptibility to IGSCC.

or written response. If

This information notice requires no specific action contact one of the the

you have any questions about this matter, please NRR project manager.

technical contacts listed below or the appropriate

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Clifford Sellers, NRR

(301) 492-0703 Walton Jensen, NRR

(301) 492-1157 Attachment: List of Recently Issued NRC Information Notices

DISTRIBUTION:

CRossi DOEA r/f

WJensen EAB r/f

NPKadambi Central Files

CSellers JRichardson

PBaranowsky CBerlinger

V If

  • SEE PREVIOUS CONCURRENCE -XGPA: P -rNRR:EMCB c<;

NRR:EAB NRR:EAB *TECH ED

  • NPKadambi KBurke CSellers
  • WJensen 08/10/90

08/01/90 08/13/90 07/27/90 08/21/90

NRR:DEf4 NRRffM NRR:DOEA

NRR:E CRossi

CYCh d JRichardo P aranowsky

o8.7 o 08'/ IC 6/90

DOCUMENT NAME: INBOLT

IN 90-XX

July XX, 1 0

Page 2 o 2 fastener materials hat are

internal bolts was modified at B&W plants to usereduce the maximum tress

less sensitive to IGSCC than alloy A-286 or to than 100 ksi

loadings of bolts fabricated of alloy A-286 to less

an extensi study of bolting

The Brookhaven National Laboratory (BNL) performed , 'Bolting

for the NRC staff. This study is documented in NUREG/CR-36 elationship between

Applications,u May 1984. The report discusses the direct In ihs report, BNL

loading and IGSCC of bolts fabricated of alloy A-286. s ructural material

recommended that alloy A-286 not be used as a reactor

because of its susceptibility to IGSCC.

written response. If

This information notice requires no specific actio or one of the the

ntact

you have any questions about this matter, please project manager.

technical contacts listed below or the appropria NRR

Charles E. ossi, Director

Division f Operational Events Assessment

Office Nuclear Reactor Regulation

Technical Contacts: Clifford Sellers, R

(301) 492-0703 Walton Jensen, RR

(301) 492-11 Attachment: List of Recently ssued NRC Information Notices

DISTRIBUTION:

CRossi DOEA /f

WJensen EAB f

NPKadambi C tral Files

CSellers Richardson

PBaranowsky Ceerlginger )C, 1+ v

RR:EAB TECH E GPA:IP NRR:EMCB

NRRR:

KBurke CSellers DA CJ (

W NPKadambi .4NA//

O-/

90 07/i/90 &z4 /90 GR/ /90

00///

NRR: T NRR:EAB NRR:GCB NRR:DOEA

JRi ardson PBaranowsky CBerlinger CRossi

07 /90 07/ /90 07/ /90

DOCUMENT NAME: INBOLT


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