Information Notice 1997-84, Rupture in Extraction Steam Piping as a Result of Flow-Accelerated Corrosion: Difference between revisions

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{{#Wiki_filter:'UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:'
                                          UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 December 11, 1997 NRC INFORMATION


NOTICE 97-84: RUPTURE IN EXTRACTION
WASHINGTON, D.C. 20555-0001 December 11, 1997 NRC INFORMATION NOTICE 97-84: RUPTURE IN EXTRACTION STEAM PIPING AS A


STEAM PIPING AS A RESULT OF FLOW-ACCELERATED
RESULT OF FLOW-ACCELERATED CORROSION
 
CORROSION


==Addressees==
==Addressees==
All holders of operating
All holders of operating licenses for nuclear power reactors except those who have permanently


licenses for nuclear power reactors except those who have permanently
reactor


ceased operations
ceased operations and have certified that fuel has been permanently removed from the


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


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
 
Commission (NRC) is issuing this information
 
notice to alert addressees
 
to potential
 
generic problems related to the occurrence
 
and prediction
 
of flow-accelerated
 
corrosion (FAC) in extraction
 
steam systems. 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 are not NRC requirements;
therefore, no specific action or written response is required.Description
 
of Circumstances
 
On April 21, 1997, Omaha Public Power District's
 
Fort Calhoun Station, while operating
 
at 100-percent power, experienced
 
an approximate
 
0.56 m 2 [6 ftl rupture of a 30.5-centimeter
 
[12-inch]-diameter
 
sweep elbow (radius equal to five times the pipe diameter)
in the fourth-stage
 
extraction
 
steam piping. The operator, upon hearing steam noise and observing
 
steam rising from the turbine deck, believed that a steam line had broken and manually scrammed the reactor. As a precaution, emergency
 
boration was initiated.
 
The main turbine tripped automatically
 
as a result of the reactor trip. The turbine trip had the effect of isolating
 
the rupture. Plant systems and related parameters
 
responded
 
as expected during the event.The steam line rupture damaged a nonsafety-related
 
electrical
 
load center in the vicinity of the pipe break. Additionally, collateral
 
damage was experienced
 
in several cable trays and pipe hangers, and insulation
 
containing
 
asbestos was blown throughout
 
the turbine building.
 
Certain portions of the fire protection
 
system actuated in response to fusible links in the sprinkler
 
heads melting because of high temperature.
 
Because there were no personnel
 
in the immediate vicinity of the rupture, no one was injured.120 DA ,731t1i, PD n +4NT~ES 17-09 9719-11 9712 W ik l a a
 
* K.IN 97-84 December 11, 1997 The fourth-stage
 
extraction
 
steam system emanates from the outlet of the high-pressure
 
turbine and preheats the feedwater
 
heaters. The design operating
 
conditions
 
in the piping are 2068 kilopascal
 
gauge [300 psig] and 218 0 C [4250F], with a steam quality of approximately
 
92 percent. The piping is fabricated
 
of A-1 06B carbon steel and has a nominal wall thickness
 
of 0.953 centimeter
 
[0.375 inch]. The licensee's
 
root cause assessment
 
attributed
 
the failure to FAC in the extraction
 
steam piping. Initial indications
 
of degradation
 
in the extraction
 
steam line at the Fort Calhoun facility were first discovered
 
in 1985, when the furthest upstream long-radius elbow (radius equal to one and a half times the pipe diameter)
was replaced because of a pinhole leak. At that time the next upstream sweep elbow was also replaced.The fourth-stage
 
extraction
 
steam system had been recognized
 
as a system that was susceptible
 
to erosion and/or corrosion.
 
It was, therefore, being monitored
 
by the licensee's
 
erosion and corrosion
 
control program. Part of the licensee program was utilizing
 
the CHECWORKS
 
computer code to identify high-wear-rate
 
areas to be selected for inspection.
 
The CHECWORKS
 
model for the fourth-stage
 
extraction
 
steam piping predicted
 
that long-radius elbows would wear at a higher rate than the sweep elbows when exposed to similar conditions.
 
Using CHECWORKS
 
predictions, the licensee inspected
 
and replaced all four long-radius elbows, but the failed sweep elbow was never inspected.
 
Part of the licensee's
 
corrective
 
actions following
 
the rupture included inspecting
 
all sweep elbows that had not been previously
 
inspected.
 
The measured wall thickness
 
(0.112 centimeter
 
[0.044 inch]) of the furthest downstream
 
sweep elbow in the fourth-stage
 
extraction
 
piping was also significantly
 
below the minimum wall thickness


(0.272 centimeter
flow- addressees to potential generic problems related to the occurrence and prediction of


[0.107 inch]) specified
will


by code requirements
accelerated corrosion (FAC) in extraction steam systems. It is expected that recipients


and had to be replaced.
actions,  as  appropriate,    to


Additionally, another sweep elbow in the fourth-stage extraction
review the information for applicability to their facilities and consider


piping was also replaced because the wear (measured
notice  are  not  NRC


wall thickness
avoid similar problems. However, suggestions contained in this information


of 0.394 centimeter
requirements; therefore, no specific action or written response is required.


[0.155 inch]) was considered
==Description of Circumstances==
On April 21, 1997, Omaha Public Power District's Fort      Calhoun Station, while operating at 100-
                                                          2                                        [12- percent power, experienced an approximate 0.56 m [6 ftl rupture of a 30.5-centimeter


excessive, even though it was not below the minimum allowable
inch]-diameter sweep elbow (radius equal to five times the pipe diameter)      in  the  fourth-stage


thickness.
rising


The CHECWORKS
extraction steam piping. The operator, upon hearing steam noise and observing steam


predictions
from the turbine deck, believed that a steam line had broken and manually scrammed the


of the wear in the fourth-stage
reactor. As a precaution, emergency boration was initiated. The main turbine tripped


extraction
the


steam system were not consistent
automatically as a result of the reactor trip. The turbine trip had the effect of isolating


with the actual observed wear rates as measured on the components, that is, sweep elbows showed substantially
event.


greater wear than predicted.
rupture. Plant systems and related parameters responded as expected during the


IN 97-84 December 11, 1997 Subsequent
of the


investigations
The steam line rupture damaged a nonsafety-related electrical load center in the vicinity


by the licensee determined
cable    trays  and  pipe


that the inconsistencies
pipe break. Additionally, collateral damage was experienced in several


between predicted
Certain


and actual wear were due to two factors. First, the "line correction
hangers, and insulation containing asbestos was blown throughout the turbine building.


factor" calculated
heads


by CHECWORKS
portions of the fire protection system actuated in response to fusible links in the sprinkler


for the fourth-stage
melting because of high temperature. Because there were        no personnel  in  the immediate


extraction
vicinity of the rupture, no one was injured.


steamline
120                DA ,731t1i, nPD+4NT~ES                    17-09 9719-11
                                                                              9712Wik l a a


was not within the acceptable
*                        K.


range specified
IN 97-84 December 11, 1997 turbine


in the CHECWORKS
The fourth-stage extraction steam system emanates from the outlet of the high-pressure


users' manual. The line correction
and preheats the feedwater heaters. The design operating conditions in the piping are


factor in CHECWORKS
2068 kilopascal gauge [300 psig] and 218 C [4250F], with a steam quality of approximately


is used to adjust wear rate predictions
0
                                                                                            thickness of


in a given line to account for plant operating
92 percent. The piping is fabricated of A-1 06B carbon steel and has a nominal wall


conditions
to


that may vary with time. It is determined
0.953 centimeter [0.375 inch]. The licensee's root cause assessment attributed the failure


by comparing
steam line


predicted
FAC in the extraction steam piping. Initial indications of degradation in the extraction


wear to measured wear at locations
the  furthest  upstream    long- at the Fort Calhoun facility were first discovered in 1985, when


in the line which have been inspected.
of


In order for the CHECWORKS
radius elbow (radius equal to one and a half times the pipe diameter) was replaced because


predicted
a pinhole leak. At that time the next upstream sweep elbow was also replaced.


wear rate for a location to be valid, the line correction
The fourth-stage extraction steam system had been recognized as a system that was


factor must be between 0.5 and 2.5. For the line containing
susceptible to erosion and/or corrosion. It was, therefore, being monitored by the licensee's


the sweep elbow that failed, the wear rates calculated
erosion and corrosion control program. Part of the licensee program was utilizing the


by CHECWORKS
CHECWORKS computer code to identify high-wear-rate areas to be selected for inspection.


used a line correction
long- The CHECWORKS model for the fourth-stage extraction steam piping predicted that


factor that was outside this range. Therefore, as specified
to similar


in the CHECWORKS
radius elbows would wear at a higher rate than the sweep elbows when exposed


users' manual, the predicted
four long- conditions. Using CHECWORKS predictions, the licensee inspected and replaced all


wear rates for this line were not valid.Second, the line correction
radius elbows, but the failed sweep elbow was never    inspected.


factor was biased and thus underpredicted
Part of the licensee's corrective actions following the rupture included inspecting all sweep


the wear rates. In 1987, the licensee updated the parameters
centimeter


used by CHECWORKS
elbows that had not been previously inspected. The measured wall thickness (0.112 the fourth-stage    extraction  piping  was


to include the wear measured in a long-radius
[0.044 inch]) of the furthest downstream sweep elbow in


elbow. One of the inputs in CHECWORKS
[0.107  inch])  specified    by


is the length of time the component
also significantly below the minimum wall thickness (0.272 centimeter


has been In service. The licensee assumed that this elbow had been in service since initial operation
fourth- code requirements and had to be replaced. Additionally, another sweep elbow in the


of the plant In 1973; however, the elbow had been replaced in 1985. Therefore, the actual wear occurred over 2 years rather than the presumed 14 years. Thus, the period of time that was assumed for the wear to have occurred caused CHECWORKS
the wear (measured    wall thickness    of


to calculate
stage extraction piping was also replaced because


a line correction
though    it was  not  below  the


factor that underestimated
0.394 centimeter [0.155 inch]) was considered excessive, even


the wear rates for sites in the line.This event revealed the importance
minimum allowable thickness.


of understanding
were


the limitation
The CHECWORKS predictions of the wear in the fourth-stage extraction steam system


of methodologies
on  the  components,      that  is, not consistent with the actual observed wear rates as measured


used in computer programs and of incorporating
sweep elbows showed substantially greater wear than predicted.


accurate plant-specific
IN 97-84 December 11, 1997 Subsequent investigations by the licensee determined that the inconsistencies between


data from nondestructive
predicted and actual wear were due to two factors. First, the "line correction factor" calculated


examination
by CHECWORKS for the fourth-stage extraction steamline was not within the acceptable range


programs.Related Generic Communications
specified in the CHECWORKS users' manual. The line correction factor in CHECWORKS is


In NRC Bulletin 87-01, "Thinning
used to adjust wear rate predictions in a given line to account for plant operating conditions that


of Pipe Walls in Nuclear Power Plants," July 9, 1987, the staff asked licensees
may vary with time. It is determined by comparing predicted wear to measured wear at


and applicants
locations in the line which have been inspected.


to inform the NRC about their programs for monitoring
In order for the CHECWORKS predicted wear rate for a location to be valid, the line correction


the wall thickness
factor must be between 0.5 and 2.5. For the line containing the sweep elbow that failed, the


of carbon steel piping (Accession
wear rates calculated by CHECWORKS used a line correction factor that was outside this


No. 8707020018).
range. Therefore, as specified in the CHECWORKS users' manual, the predicted wear rates


In NRC Generic Letter 89-08, "Erosion/Corrosion
for this line were not valid.


Induced Pipe Wall Thinning," May 2,1989, the staff asked licensees
Second, the line correction factor was biased and thus underpredicted the wear rates. In 1987, the licensee updated the parameters used by CHECWORKS to include the wear measured in a


and applicants
long-radius elbow. One of the inputs in CHECWORKS is the length of time the component has


to Implement
been In service. The licensee assumed that this elbow had been in service since initial


long-term
operation of the plant In 1973; however, the elbow had been replaced in 1985. Therefore, the


erosion/corrosion
actual wear occurred over 2 years rather than the presumed 14 years. Thus, the period of time


monitoring
that was assumed for the wear to have occurred caused CHECWORKS to calculate a line


programs (Accession
correction factor that underestimated the wear rates for sites in the line.


No. 8905040276).
This event revealed the importance of understanding the limitation of methodologies used in


IN 97-84 December 11, 1997 Additionally, the following
computer programs and of incorporating accurate plant-specific data from nondestructive


NRC information
examination programs.


notices (INs) provide information
===Related Generic Communications===
In NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants," July 9, 1987, the staff


about similar events related to FAC: IN 82-22, "Failures
asked licensees and applicants to inform the NRC about their programs for monitoring the wall


in Turbine Exhaust Lines," July 9, 1982 (Accession
thickness of carbon steel piping (Accession No. 8707020018).


No. 8204210392).
In NRC Generic Letter 89-08, "Erosion/Corrosion Induced Pipe Wall Thinning," May 2,1989, the staff asked licensees and applicants to Implement long-term erosion/corrosion monitoring


IN 86-106, nFeedwater
programs (Accession No. 8905040276).


Line Break," December 16, 1986 (Accession
IN 97-84 December 11, 1997 Additionally, the following NRC information notices (INs) provide information about similar


No. 8612160250).
events related to FAC:
IN 82-22, "Failures in Turbine Exhaust Lines," July 9, 1982 (Accession No. 8204210392).


IN 87-36, "Significant
IN 86-106, nFeedwater Line Break," December 16, 1986 (Accession No. 8612160250).


Unexpected
IN 87-36, "Significant Unexpected Erosion of Feedwater Lines," August 4, 1987 (Accession
 
Erosion of Feedwater
 
Lines," August 4, 1987 (Accession


No. 8707290264).
No. 8707290264).


IN 88-17, "Summary of Responses
IN 88-17, "Summary of Responses to NRC Bulletin 87-01, 'Thinning of Pipe Walls In Nuclear
 
to NRC Bulletin 87-01, 'Thinning
 
of Pipe Walls In Nuclear Power Plants," April 22, 1988 (Accession
 
No. 8804180039).
 
IN 89-53, "Rupture of Extraction
 
Steam Line on High Pressure Turbine," June 13, 1989 (Accession
 
No. 8906070273).
 
IN 91-18, "High Energy Pipe Failures Caused by Wall Thinning," March 12, 1991 (Accession
 
No. 9103060153).


IN 91 -18, Supplement
Power Plants," April 22, 1988 (Accession No. 8804180039).


1, "High Energy Pipe Failures Caused by Wall Thinning," December 18, 1991 (Accession
IN 89-53, "Rupture of Extraction Steam Line on High Pressure Turbine," June 13, 1989 (Accession No. 8906070273).


No. 9112120218).
IN 91-18, "High Energy Pipe Failures Caused by Wall Thinning," March 12, 1991 (Accession No. 9103060153).


IN 93-21, "Summary of NRC Staff Observations
IN 91 -18, Supplement 1, "High Energy Pipe Failures Caused by Wall Thinning," December 18,
1991 (Accession No. 9112120218).


Compiled During Engineering
IN 93-21, "Summary of NRC Staff Observations Compiled During Engineering Audits or


Audits or Inspections
Inspections of Licensee Erosion/Corrosion Programs," March 25, 1993 (Accession
 
of Licensee Erosion/Corrosion
 
Programs," March 25, 1993 (Accession


No. 9303190051).
No. 9303190051).


IN 95-11, "Failure of Condensate
IN 95-11, "Failure of Condensate Piping Because of Erosion/Corrosion at a Flow-Straightening
 
Piping Because of Erosion/Corrosion
 
at a Flow-Straightening
 
Device," February 24, 1995 (Accession


No. 9502210050).
Device," February 24, 1995 (Accession No. 9502210050).


IN 97-84 December 11, 1997 This information
IN 97-84 December 11, 1997 This information notice requires no specific action or written response. However, recipients are


notice requires no specific action or written response.
reminded that they are required to consider industry-wide operating experience (including NRC


However, recipients
information notices) where practical, when setting goals and performing periodic evaluations


are reminded that they are required to consider industry-wide
under Section 50.65, Requirement for monitoring the effectiveness of maintenance at nuclear


operating
power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any


experience (including
questions about the information in this notice, please contact the technical contact listed below


NRC information
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


notices) where practical, when setting goals and performing
J.).    RoActing Director


periodic evaluations
Pi ision of Reactor Program Management
 
under Section 50.65, Requirement
 
for monitoring
 
the effectiveness
 
of maintenance
 
at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.J.). RoActing Director Pi ision of Reactor Program Management


ice of Nuclear Reactor Regulation
ice of Nuclear Reactor Regulation


Technical
Technical contact: J. Shackelford, RIV


contact: J. Shackelford, RIV (817) 860-8144 E-mail: jIs2@nrc.gov
(817) 860-8144 E-mail: jIs2@nrc.gov


Attachment:  
Attachment: List of Recently Issued NRC Information Notices
List of Recently Issued NRC Information
 
Notices


Attachment
Attachment


IN 97-84 December 11, 1997 LIST OF RECENTLY ISSUED NRC INFORMATION
IN 97-84 December 11, 1997 LIST OF RECENTLY ISSUED


NOTICES Information
NRC INFORMATION NOTICES


Date of Notice No. Subject Issuance Issued to 95-49, Seismic Adequacy of 12/10/97 All holders of OLs for nuclear Sup. 1 Thermo-Lag
Information                                        Date of


Panels power reactors 97-83 Recent Events Involving
Notice No.            Subject                      Issuance  Issued to


12/05/97 All holders of OLs for pressurized- Reactor Coolant System water reactors, except those Inventory
95-49,          Seismic Adequacy of                12/10/97   All holders of OLs for nuclear


Control During licensees
Sup. 1          Thermo-Lag Panels                            power reactors


who have permanently
97-83            Recent Events Involving            12/05/97  All holders of OLs for pressurized- Reactor Coolant System                        water reactors, except those


Shutdown ceased operations
Inventory Control During                      licensees who have permanently


and have certified
Shutdown                                      ceased operations and have


that fuel has been permanently
certified that fuel has been


removed from the reactor vessel 97-82 Inadvertent
permanently removed from the


Control Room 11/28/97 All holders of OLs for nuclear Halon Actuation
reactor vessel


Due to a power reactors Camera Flash 97-81 Deficiencies
97-82            Inadvertent Control Room          11/28/97  All holders of OLs for nuclear


in Failure 11/24197 All holders of OLs for nuclear Modes and Effects Analyses power reactors except those for Instrumentation
Halon Actuation Due to a                      power reactors


and Control who have ceased operations
Camera Flash


Systems and have certified
97-81            Deficiencies in Failure            11/24197  All holders of OLs for nuclear


that fuel has been permanently
Modes and Effects Analyses                    power reactors except those


removed from the vessel 97-80 Licensee Technical
for Instrumentation and Control              who have ceased operations


11/21197 All holders of OLs for Specifications
Systems                                      and have certified that fuel


nuclear power reactors Interpretations
has been permanently removed


OL = Operating
from the vessel


License CP = Construction
97-80            Licensee Technical                11/21197  All holders of OLs for


Permit
Specifications                                nuclear power reactors


e e
Interpretations


* e *i' ,E'KY IN 97-84 December 11, 1997 This information
OL = Operating License


notice requires no specific action or written response.
CP = Construction Permit


However, recipients
e e
 
are reminded that they are required to consider industry-wide
 
operating
 
experience (including
 
NRC information
 
notices) where practical, when setting goals and performing
 
periodic evaluations
 
under Section 50.65, "Requirement
 
for monitoring
 
the effectiveness
 
of maintenance
 
at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contact: J. Shackelford, RIV (817) 860-8144 E-mail: jls2@nrc.gov
 
Attachment:
List of Recently Issued NRC Information
 
Notices OFC TECH EDITOR* RIV/DRS*by
 
email RIV/DRS*by
 
email PECB:DRPM*
NAME R. Sanders J. Shackelford
 
D. Chamberlain
 
T. Greenel DATE 09/11/97 09/16/97 109/16/97
09/20/97 OFC EMCB:DE* C(A)/EMCB:DE*
D:DE* SUPECB:DRPM*
NAME K. Parczewski
 
E. Sullivan B. Sheron R. Dennig DATE 9/23/97 9/23/97 9/23/97 11/21/97 I OFC I C/PECB:DRPM*
l(AED9RPM NAME S. Richards J. &DATE 11/26/97 12/6197 j* See previous concurrence
 
[OFFICIAL
 
RECORD COPY]DOCUMENT NAME: 97-84.IN
 
I IN 97-XX November XX, 1997 This information
 
notice requires no specific action or written response.
 
However, recipients


are reminded that they are required to consider industry-wide
* e *
                                        i' ,E'                                  KY


operating
IN97-84 December 11, 1997 This information notice requires no specific action or written response. However, recipients are


experience (including
reminded that they are required to consider industry-wide operating experience (including NRC


NRC information
information notices) where practical, when setting goals and performing periodic evaluations


notices) where practical, when setting goals and performing
under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear


periodic evaluations
power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any


under Section 50.65, "Requirement
questions about the information in this notice, please contact the technical contact listed below


for monitoring
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


the effectiveness
Jack W. Roe, Acting Director


of maintenance
Division of Reactor Program Management


at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
Office of Nuclear Reactor Regulation


If you have any questions
Technical contact: J. Shackelford, RIV


about the information
(817) 860-8144 E-mail: jls2@nrc.gov


in this notice, please contact the technical
Attachment: List of Recently Issued NRC Information Notices


contact listed below or the appropriate
OFC        TECH EDITOR*        RIV/DRS*by email        RIV/DRS*by email    PECB:DRPM*
            NAME      R. Sanders          J. Shackelford          D. Chamberlain      T. Greene


Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
l DATE      09/11/97            09/16/97              109/16/97            09/20/97 OFC        EMCB:DE*              C(A)/EMCB:DE*      D:DE*                  SUPECB:DRPM*
            NAME      K. Parczewski        E. Sullivan        B. Sheron              R. Dennig


===Office of Nuclear Reactor Regulation===
DATE      9/23/97                9/23/97            9/23/97              11/21/97 I OFC
Technical


contact: J. Shackelford, RIV (817) 860-8144 E-mail: jis2@nrc.gov
NAME


Attachment:  
I C/PECB:DRPM*
List of Recently Issued NRC Information
                      S. Richards


Notices OFC l TECH EDITOR* RlV/DRS*by
l(AED9RPM


email RIV/DRS*by
J. &
            DATE        11/26/97                12/6197        j


email PECB:DRPM*
* See previous concurrence
NAME R. Sanders J. Shackelford


D. Chamberlain
[OFFICIAL RECORD COPY]
          DOCUMENT NAME: 97-84.IN


T. Greene DATE j 09/11/97 09/16/97 09/16/97 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE*
I
D:DE* SL/PECB:DRPM*
NAME K. Parczewski


E. Sullivan B. Sheron R. Dennig DATE __9/23/97  
IN 97-XX
9/23/97 j_9/23/97 j_11/21/971 , 1^_AN I/,b(7 OFC lC/PECB:DRPM*1 (A)D/DF3PM


NAME S. Richards J.DATE %I tZ697 <1/897U7* See previous concurrence
November XX, 1997 This information notice requires no specific action or written response. However, recipients are


[OFFICIAL
reminded that they are required to consider industry-wide operating experience (including NRC


RECORD COPY]DOCUMENT NAME: G:\TAG\INFAC
information notices) where practical, when setting goals and performing periodic evaluations


IJ I A o IN 97-XX November XX, 1997 This information
under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear


notice requires no specific action or written response.
power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any


===However, recipients===
questions about the information in this notice, please contact the technical contact listed below
are reminded that they are required to consider industry-wide


operating
or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


experience (including
Jack W. Roe, Acting Director


NRC information
Division of Reactor Program Management


notices) where practical, when setting goals and performing
Office of Nuclear Reactor Regulation


periodic evaluations
Technical contact: J. Shackelford, RIV


under Section 50.65, "Requirement
(817) 860-8144 E-mail: jis2@nrc.gov


for monitoring
Attachment: List of Recently Issued NRC Information Notices


the effectiveness
OFC    l TECH EDITOR*        RlV/DRS*by email      RIV/DRS*by email    PECB:DRPM*
  NAME      R. Sanders          J. Shackelford        D. Chamberlain      T. Greene


of maintenance
DATE    j 09/11/97            09/16/97              09/16/97            09/20/97 OFC        EMCB:DE*              C(A)/EMCB:DE*      D:DE*                SL/PECB:DRPM*
  NAME      K. Parczewski        E. Sullivan        B. Sheron            R. Dennig


at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
DATE __9/23/97                    9/23/97        j_9/23/97            j_11/21/971
                                                                                                    , 1^_
                                                                                AN            I/,b(7 OFC    lC/PECB:DRPM*1          (A)D/DF3PM


If you have any questions
NAME      S. Richards            J.


about the information
DATE      %ItZ697                <1/897U7


in this notice, please contact the technical
* See previous concurrence


contact listed below or the appropriate
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\TAG\INFAC


Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
IJ                                      I oA


===Office of Nuclear Reactor Regulation===
IN 97-XX
Technical


contact: J. Shackelford, RIV (817) 860-8144 E-mail: jIs2@nrc.gov
November XX, 1997 This information notice requires no specific action or written response. However, recipients


Attachment:
are reminded that they are required to consider industry-wide operating experience (including
List of Recently Issued NRC Information


Notices OFC TECH EDITOR* RIV/DRS*by
NRC information notices) where practical, when setting goals and performing periodic


email RIVIDRS*by
evaluations under Section 50.65, "Requirement for monitoring the effectiveness of


email PECB:DRPM*
maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal
NAME R. Sanders J. Shackelford


D. Chamberlain
Regulations. If you have any questions about the information in this notice, please contact


T. Greene DATE 09/11197 09/16/97 09116197 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE*
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation
D:DE* SUPECB:DRPM


NAME K. Parczewski
(NRR) project manager.


E. Sullivan B. Sheron R. DennigI DATE 9/23/97 9/23/97 9/23/97 11/21/97 IOFC C/PECB:DRPM* (A)D/DRPM NAME S. Richards f J. Roe DATE I /97 [__ /97*See previous cocrence/[OFFICIAL
Jack W. Roe, Acting Director


RECORD COPY]a Y/y7/DOCUMENT NAME: G:\TAG\INFAC
Division of Reactor Program Management


IN 97-XX November XX, 1997 This information
Office of Nuclear Reactor Regulation


notice requires no specific action or written response.
Technical contact: J. Shackelford, RIV


===However, recipients===
(817) 860-8144 E-mail: jIs2@nrc.gov
are reminded that they are required to consider industry-wide


operating
Attachment: List of Recently Issued NRC Information Notices


experience (including
OFC      TECH EDITOR*      RIV/DRS*by email        RIVIDRS*by email    PECB:DRPM*
  NAME      R. Sanders        J. Shackelford          D. Chamberlain      T. Greene


NRC information
DATE      09/11197          09/16/97                09116197            09/20/97 OFC      EMCB:DE*            C(A)/EMCB:DE*      D:DE*                SUPECB:DRPM


notices) where practical, when setting goals and performing
IOFC


periodic evaluations
NAME      K. Parczewski      E. Sullivan        B. Sheron            R. DennigI


under Section 50.65, "Requirement
DATE      9/23/97              9/23/97            9/23/97              11/21/97 NAME


for monitoring
DATE


the effectiveness
C/PECB:DRPM*
            S. Richards


of maintenance
I /97 f (A)D/DRPM


at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
J. Roe


If you have any questions
[__    /97
  *See previous cocrence/
[OFFICIAL RECORD COPY]a          Y/y7/
DOCUMENT NAME: G:\TAG\INFAC


about the information
IN 97-XX


in this notice, please contact the technical
November XX, 1997 This information notice requires no specific action or written response. However, recipients


contact listed below or the appropriate
are reminded that they are required to consider industry-wide operating experience (including


Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
NRC information notices) where practical, when setting goals and performing periodic


===Office of Nuclear Reactor Regulation===
evaluations under Section 50.65, "Requirement for monitoring the effectiveness of
Technical


contact: J. Shackelford, RIV 817-860-8144 E-mail: jls2@nrc.gov
maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal


Attachment:
Regulations. If you have any questions about the information in this notice, please contact
List of Recently Issued NRC Information


Notices OFC TECH EDITOR* RIV/DRS*by
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation


email RIV/DRS*by
(NRR) project manager.


email PECB:DRPM*
Jack W. Roe, Acting Director
NAME R. Sanders J. Shackelford


D. Chamberlain
Division of Reactor Program Management


T. Greene D 09/11/97 09/16/97 09/16/97 09/17/97 111,0111 OFC EMCB:DE* j C(A)IEMCB:DE*
Office of Nuclear Reactor Regulation
D:DE* S1 IPA PM NAME K. Parczewski


E. Sullivan B. Sheron .FLenn/iglDATE 9/23/97 9/23/97 9123197 n 197 OFC C/PECB:DRPM (A)D/DRPM NAME S. Richards J. Roe DATE / /97 / /97 lj See previous concurrence
Technical contact: J. Shackelford, RIV


[OFFICIAL
817-860-8144 E-mail: jls2@nrc.gov


RECORD COPY]DOCUMENT NAME: G:NTAGIINFAC
Attachment: List of Recently Issued NRC Information Notices


e 4 t IN 97-XX October XX, 1997 This information
OFC      TECH EDITOR*        RIV/DRS*by email        RIV/DRS*by email    PECB:DRPM*
  NAME      R. Sanders        J. Shackelford          D. Chamberlain      T. Greene


notice requires no specific action or written response.
D        09/11/97            09/16/97                09/16/97            09/17/97 111,0111 OFC      EMCB:DE*            jC(A)IEMCB:DE*      D:DE*                  S1IPA PM


===However, recipients===
NAME      K. Parczewski        E. Sullivan        B. Sheron          .FLenn/ig
are reminded that they are required to consider industry-wide


operating
lDATE      9/23/97              9/23/97            9123197          n        197 OFC      C/PECB:DRPM          (A)D/DRPM


experience (including
NAME      S. Richards          J. Roe


NRC information
DATE        / /97                  / /97          lj


notices) where practical, when setting goals and performing
See previous concurrence


periodic evaluations
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:NTAGIINFAC


under Section 50.65, "Requirement
e 4 t


for monitoring
IN 97-XX


the effectiveness
October XX, 1997 This information notice requires no specific action or written response. However, recipients


of.maintenance
are reminded that they are required to consider industry-wide operating experience (including


at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
NRC information notices) where practical, when setting goals and performing periodic


If you have any questions
evaluations under Section 50.65, "Requirement for monitoring the effectiveness of.


about the information
maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal


in this notice, please contact the technical
Regulations. If you have any questions about the information in this notice, please contact


contact listed below or the appropriate
the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation


Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
(NRR) project manager.


===Office of Nuclear Reactor Regulation===
Jack W. Roe, Acting Director
Technical


contact: J. Shackelford, RIV 817-8604144 E-mail: jls2@nrc.gov
Division of Reactor Program Management


Attachment:
Office of Nuclear Reactor Regulation
List of Recently Issued NRC Information


Notices OFC TECH EDITOR RIVIDRS a s -/:$Aq PECB:DRPM NAME R. Sanders* J. Shackelford
Technical contact:     J. Shackelford, RIV


i D. ChamberlainO)T.
817-8604144 E-mail: jls2@nrc.gov


Greene (i )DATE 09111/97 09/16/97 09/16/97 09/17/97 OFC EMCB:DE C(A)/EMCB:DE
Attachment: List of Recently Issued NRC Information Notices


:DE Si. SLIPECB:DRPM
OFC      TECH EDITOR                      RIVIDRSa        s      - /:$Aq PECB:DRPM


NAME K. Parczewski
NAME     R. Sanders*          J. Shackelford      i  D. ChamberlainO)T. Greene )    (i


E. Sullivan _. Dennig DATE /S3197 19 4A7(97;)J41
DATE     09111/97              09/16/97                09/16/97             09/17/97 OFC      EMCB:DE              C(A)/EMCB:DE          :DE                Si.
110/974J31;};3
1/97llOFC C(A)/PECB:DRPM


D/DRPYA NAME E. Goodwin J. Roe DATE / /97 1 /97* See previous concurrence
SLIPECB:DRPM


[OFFICIAL
NAME      K. Parczewski        E. Sullivan                              _.  Dennig


RECORD COPY]DOCUMENT NAME: G:\TAG\INFAC
DATE        /S3197            19 4A7(97;)J41        110/974J31;};3          1/97l


W .I a .I K) IN 97-XX September
lOFC      C(A)/PECB:DRPM          D/DRPYA


XX, 1997 This information
NAME      E. Goodwin              J. Roe


notice requires no specifi action or written response.
DATE        / /97              1      /97


===However, recipients===
* See previous concurrence
are reminded that they are required to industry-wide


operating
[OFFICIAL RECORD COPY]
      DOCUMENT NAME: G:\TAG\INFAC


experience (including
W . I a. I


NRC information
K)    IN 97-XX


notices) where practical, when setting goals and performing
September XX, 1997 This information notice requires no specifi action or written response. However, recipients


periodic evaluations
are reminded that they are required to        industry-wide operating experience (including


under Section 50.65, "Requirement
NRC information notices)                      where practical, when setting goals and


for monitoring
performing periodic evaluations under Section 50.65, "Requirement for monitoring the


the effectiveness
effectiveness of maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of


of maintenance
Federal Regulations. If you have any questions about the information in this notice, please


at nuclear power plants," to Part 50 of Title 10 of the Code of Federal Regulations.
contact the technical contact listed below or the appropriate Office of Nuclear Reactor


If you have any questions
Regulation (NRR) project manager.


about the information
Jack W. Roe, Acting Director


in this notice, please contact the technical
Division of Reactor Program Management


contact listed below or the appropriate
Office of Nuclear Reactor Regulation


Office of Nuclear Reactor Regulation (NRR) project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
Technical contact:      J. Shackelford, RIV


===Office of Nuclear Reactor Regulation===
(7817-860-8144
Technical
                                    _ E-mail: jls2@nrc.gov


contact: J. Shackelford, RIV (7817-860-8144
Attachment: List of Recently Issued NRC Information Notices
_ E-mail: jls2@nrc.gov


Attachment:  
OFC      TECH EDITOR        RIV/DRS                RIV/DRS            l PECB:DRPM
List of Recently Issued NRC Information


Notices OFC TECH EDITOR RIV/DRS RIV/DRS l PECB:DRPM NAME R. Sanders 0 J. Shackelford
NAME     R. Sanders 0       J. Shackelford         D. Chamberlain      T. Greene


D. Chamberlain
l DATE    ljul11/97              //97              1  //97            1      /97 OFC      C/EMCB:DE          D:DE                SL(A)/PECB:DRPM      C(A)/PECB:DRPM


T. Greenel DATE ljul11/97
NAME      J. Strosnider      B. Sheron          C. Petrone            R. Dennig
//97 1 //97 1 /97 OFC C/EMCB:DE


D:DE SL(A)/PECB:DRPM
DATE        I /97    _          I/197            //97              1      /97 I OFC


C(A)/PECB:DRPM
NAME


NAME J. Strosnider
DIDRPM


B. Sheron C. Petrone R. Dennig DATE I _ /97 I /197 //97 1 /97 I OFC DIDRPM NAME J. Roe DATE l /97[OFFICIAL
J. Roe


RECORD COPY]DOCUMENT NAME: G:%TAGINFAC}}
DATE  l      /97
          [OFFICIAL RECORD COPY]
          DOCUMENT NAME: G:%TAGINFAC}}


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

Revision as of 03:47, 24 November 2019

Rupture in Extraction Steam Piping as a Result of Flow-Accelerated Corrosion
ML031050037
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, 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, Crane  Entergy icon.png
Issue date: 12/11/1997
From: Roe J
Office of Nuclear Reactor Regulation
To:
References
IN-97-084, NUDOCS 9712090140
Download: ML031050037 (12)
v • d • e


'

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 December 11, 1997 NRC INFORMATION NOTICE 97-84: RUPTURE IN EXTRACTION STEAM PIPING AS A

RESULT OF FLOW-ACCELERATED CORROSION

Addressees

All holders of operating licenses for nuclear power reactors except those who have permanently

reactor

ceased operations and have certified that fuel has been permanently removed from the

vessel.

Purpose

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

flow- addressees to potential generic problems related to the occurrence and prediction of

will

accelerated corrosion (FAC) in extraction steam systems. It is expected that recipients

actions, as appropriate, to

review the information for applicability to their facilities and consider

notice are not NRC

avoid similar problems. However, suggestions contained in this information

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

Description of Circumstances

On April 21, 1997, Omaha Public Power District's Fort Calhoun Station, while operating at 100-

2 [12- percent power, experienced an approximate 0.56 m [6 ftl rupture of a 30.5-centimeter

inch]-diameter sweep elbow (radius equal to five times the pipe diameter) in the fourth-stage

rising

extraction steam piping. The operator, upon hearing steam noise and observing steam

from the turbine deck, believed that a steam line had broken and manually scrammed the

reactor. As a precaution, emergency boration was initiated. The main turbine tripped

the

automatically as a result of the reactor trip. The turbine trip had the effect of isolating

event.

rupture. Plant systems and related parameters responded as expected during the

of the

The steam line rupture damaged a nonsafety-related electrical load center in the vicinity

cable trays and pipe

pipe break. Additionally, collateral damage was experienced in several

Certain

hangers, and insulation containing asbestos was blown throughout the turbine building.

heads

portions of the fire protection system actuated in response to fusible links in the sprinkler

melting because of high temperature. Because there were no personnel in the immediate

vicinity of the rupture, no one was injured.

120 DA ,731t1i, nPD+4NT~ES 17-09 9719-11

9712Wik l a a

  • K.

IN 97-84 December 11, 1997 turbine

The fourth-stage extraction steam system emanates from the outlet of the high-pressure

and preheats the feedwater heaters. The design operating conditions in the piping are

2068 kilopascal gauge [300 psig] and 218 C [4250F], with a steam quality of approximately

0

thickness of

92 percent. The piping is fabricated of A-1 06B carbon steel and has a nominal wall

to

0.953 centimeter [0.375 inch]. The licensee's root cause assessment attributed the failure

steam line

FAC in the extraction steam piping. Initial indications of degradation in the extraction

the furthest upstream long- at the Fort Calhoun facility were first discovered in 1985, when

of

radius elbow (radius equal to one and a half times the pipe diameter) was replaced because

a pinhole leak. At that time the next upstream sweep elbow was also replaced.

The fourth-stage extraction steam system had been recognized as a system that was

susceptible to erosion and/or corrosion. It was, therefore, being monitored by the licensee's

erosion and corrosion control program. Part of the licensee program was utilizing the

CHECWORKS computer code to identify high-wear-rate areas to be selected for inspection.

long- The CHECWORKS model for the fourth-stage extraction steam piping predicted that

to similar

radius elbows would wear at a higher rate than the sweep elbows when exposed

four long- conditions. Using CHECWORKS predictions, the licensee inspected and replaced all

radius elbows, but the failed sweep elbow was never inspected.

Part of the licensee's corrective actions following the rupture included inspecting all sweep

centimeter

elbows that had not been previously inspected. The measured wall thickness (0.112 the fourth-stage extraction piping was

[0.044 inch]) of the furthest downstream sweep elbow in

[0.107 inch]) specified by

also significantly below the minimum wall thickness (0.272 centimeter

fourth- code requirements and had to be replaced. Additionally, another sweep elbow in the

the wear (measured wall thickness of

stage extraction piping was also replaced because

though it was not below the

0.394 centimeter [0.155 inch]) was considered excessive, even

minimum allowable thickness.

were

The CHECWORKS predictions of the wear in the fourth-stage extraction steam system

on the components, that is, not consistent with the actual observed wear rates as measured

sweep elbows showed substantially greater wear than predicted.

IN 97-84 December 11, 1997 Subsequent investigations by the licensee determined that the inconsistencies between

predicted and actual wear were due to two factors. First, the "line correction factor" calculated

by CHECWORKS for the fourth-stage extraction steamline was not within the acceptable range

specified in the CHECWORKS users' manual. The line correction factor in CHECWORKS is

used to adjust wear rate predictions in a given line to account for plant operating conditions that

may vary with time. It is determined by comparing predicted wear to measured wear at

locations in the line which have been inspected.

In order for the CHECWORKS predicted wear rate for a location to be valid, the line correction

factor must be between 0.5 and 2.5. For the line containing the sweep elbow that failed, the

wear rates calculated by CHECWORKS used a line correction factor that was outside this

range. Therefore, as specified in the CHECWORKS users' manual, the predicted wear rates

for this line were not valid.

Second, the line correction factor was biased and thus underpredicted the wear rates. In 1987, the licensee updated the parameters used by CHECWORKS to include the wear measured in a

long-radius elbow. One of the inputs in CHECWORKS is the length of time the component has

been In service. The licensee assumed that this elbow had been in service since initial

operation of the plant In 1973; however, the elbow had been replaced in 1985. Therefore, the

actual wear occurred over 2 years rather than the presumed 14 years. Thus, the period of time

that was assumed for the wear to have occurred caused CHECWORKS to calculate a line

correction factor that underestimated the wear rates for sites in the line.

This event revealed the importance of understanding the limitation of methodologies used in

computer programs and of incorporating accurate plant-specific data from nondestructive

examination programs.

Related Generic Communications

In NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants," July 9, 1987, the staff

asked licensees and applicants to inform the NRC about their programs for monitoring the wall

thickness of carbon steel piping (Accession No. 8707020018).

In NRC Generic Letter 89-08, "Erosion/Corrosion Induced Pipe Wall Thinning," May 2,1989, the staff asked licensees and applicants to Implement long-term erosion/corrosion monitoring

programs (Accession No. 8905040276).

IN 97-84 December 11, 1997 Additionally, the following NRC information notices (INs) provide information about similar

events related to FAC:

IN 82-22, "Failures in Turbine Exhaust Lines," July 9, 1982 (Accession No. 8204210392).

IN 86-106, nFeedwater Line Break," December 16, 1986 (Accession No. 8612160250).

IN 87-36, "Significant Unexpected Erosion of Feedwater Lines," August 4, 1987 (Accession

No. 8707290264).

IN 88-17, "Summary of Responses to NRC Bulletin 87-01, 'Thinning of Pipe Walls In Nuclear

Power Plants," April 22, 1988 (Accession No. 8804180039).

IN 89-53, "Rupture of Extraction Steam Line on High Pressure Turbine," June 13, 1989 (Accession No. 8906070273).

IN 91-18, "High Energy Pipe Failures Caused by Wall Thinning," March 12, 1991 (Accession No. 9103060153).

IN 91 -18, Supplement 1, "High Energy Pipe Failures Caused by Wall Thinning," December 18,

1991 (Accession No. 9112120218).

IN 93-21, "Summary of NRC Staff Observations Compiled During Engineering Audits or

Inspections of Licensee Erosion/Corrosion Programs," March 25, 1993 (Accession

No. 9303190051).

IN 95-11, "Failure of Condensate Piping Because of Erosion/Corrosion at a Flow-Straightening

Device," February 24, 1995 (Accession No. 9502210050).

IN 97-84 December 11, 1997 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under Section 50.65, Requirement for monitoring the effectiveness of maintenance at nuclear

power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any

questions about the information in this notice, please contact the technical contact listed below

or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

J.). RoActing Director

Pi ision of Reactor Program Management

ice of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

(817) 860-8144 E-mail: jIs2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

Attachment

IN 97-84 December 11, 1997 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-49, Seismic Adequacy of 12/10/97 All holders of OLs for nuclear

Sup. 1 Thermo-Lag Panels power reactors

97-83 Recent Events Involving 12/05/97 All holders of OLs for pressurized- Reactor Coolant System water reactors, except those

Inventory Control During licensees who have permanently

Shutdown ceased operations and have

certified that fuel has been

permanently removed from the

reactor vessel

97-82 Inadvertent Control Room 11/28/97 All holders of OLs for nuclear

Halon Actuation Due to a power reactors

Camera Flash

97-81 Deficiencies in Failure 11/24197 All holders of OLs for nuclear

Modes and Effects Analyses power reactors except those

for Instrumentation and Control who have ceased operations

Systems and have certified that fuel

has been permanently removed

from the vessel

97-80 Licensee Technical 11/21197 All holders of OLs for

Specifications nuclear power reactors

Interpretations

OL = Operating License

CP = Construction Permit

e e

  • e *

i' ,E' KY

IN97-84 December 11, 1997 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear

power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any

questions about the information in this notice, please contact the technical contact listed below

or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

(817) 860-8144 E-mail: jls2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC TECH EDITOR* RIV/DRS*by email RIV/DRS*by email PECB:DRPM*

NAME R. Sanders J. Shackelford D. Chamberlain T. Greene

l DATE 09/11/97 09/16/97 109/16/97 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE* D:DE* SUPECB:DRPM*

NAME K. Parczewski E. Sullivan B. Sheron R. Dennig

DATE 9/23/97 9/23/97 9/23/97 11/21/97 I OFC

NAME

I C/PECB:DRPM*

S. Richards

l(AED9RPM

J. &

DATE 11/26/97 12/6197 j

  • See previous concurrence

[OFFICIAL RECORD COPY]

DOCUMENT NAME: 97-84.IN

I

IN 97-XX

November XX, 1997 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under Section 50.65, "Requirement for monitoring the effectiveness of maintenance at nuclear

power plants," to Part 50 of Title 10 of the Code of Federal Regulations. If you have any

questions about the information in this notice, please contact the technical contact listed below

or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

(817) 860-8144 E-mail: jis2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC l TECH EDITOR* RlV/DRS*by email RIV/DRS*by email PECB:DRPM*

NAME R. Sanders J. Shackelford D. Chamberlain T. Greene

DATE j 09/11/97 09/16/97 09/16/97 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE* D:DE* SL/PECB:DRPM*

NAME K. Parczewski E. Sullivan B. Sheron R. Dennig

DATE __9/23/97 9/23/97 j_9/23/97 j_11/21/971

, 1^_

AN I/,b(7 OFC lC/PECB:DRPM*1 (A)D/DF3PM

NAME S. Richards J.

DATE %ItZ697 <1/897U7

  • See previous concurrence

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TAG\INFAC

IJ I oA

IN 97-XX

November XX, 1997 This information notice requires no specific action or written response. However, recipients

are reminded that they are required to consider industry-wide operating experience (including

NRC information notices) where practical, when setting goals and performing periodic

evaluations under Section 50.65, "Requirement for monitoring the effectiveness of

maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal

Regulations. If you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation

(NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

(817) 860-8144 E-mail: jIs2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC TECH EDITOR* RIV/DRS*by email RIVIDRS*by email PECB:DRPM*

NAME R. Sanders J. Shackelford D. Chamberlain T. Greene

DATE 09/11197 09/16/97 09116197 09/20/97 OFC EMCB:DE* C(A)/EMCB:DE* D:DE* SUPECB:DRPM

IOFC

NAME K. Parczewski E. Sullivan B. Sheron R. DennigI

DATE 9/23/97 9/23/97 9/23/97 11/21/97 NAME

DATE

C/PECB:DRPM*

S. Richards

I /97 f (A)D/DRPM

J. Roe

[__ /97

  • See previous cocrence/

[OFFICIAL RECORD COPY]a Y/y7/

DOCUMENT NAME: G:\TAG\INFAC

IN 97-XX

November XX, 1997 This information notice requires no specific action or written response. However, recipients

are reminded that they are required to consider industry-wide operating experience (including

NRC information notices) where practical, when setting goals and performing periodic

evaluations under Section 50.65, "Requirement for monitoring the effectiveness of

maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal

Regulations. If you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation

(NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

817-860-8144 E-mail: jls2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC TECH EDITOR* RIV/DRS*by email RIV/DRS*by email PECB:DRPM*

NAME R. Sanders J. Shackelford D. Chamberlain T. Greene

D 09/11/97 09/16/97 09/16/97 09/17/97 111,0111 OFC EMCB:DE* jC(A)IEMCB:DE* D:DE* S1IPA PM

NAME K. Parczewski E. Sullivan B. Sheron .FLenn/ig

lDATE 9/23/97 9/23/97 9123197 n 197 OFC C/PECB:DRPM (A)D/DRPM

NAME S. Richards J. Roe

DATE / /97 / /97 lj

See previous concurrence

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:NTAGIINFAC

e 4 t

IN 97-XX

October XX, 1997 This information notice requires no specific action or written response. However, recipients

are reminded that they are required to consider industry-wide operating experience (including

NRC information notices) where practical, when setting goals and performing periodic

evaluations under Section 50.65, "Requirement for monitoring the effectiveness of.

maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of Federal

Regulations. If you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation

(NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

817-8604144 E-mail: jls2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC TECH EDITOR RIVIDRSa s - /:$Aq PECB:DRPM

NAME R. Sanders* J. Shackelford i D. ChamberlainO)T. Greene ) (i

DATE 09111/97 09/16/97 09/16/97 09/17/97 OFC EMCB:DE C(A)/EMCB:DE :DE Si.

SLIPECB:DRPM

NAME K. Parczewski E. Sullivan _. Dennig

DATE /S3197 19 4A7(97;)J41 110/974J31;};3 1/97l

lOFC C(A)/PECB:DRPM D/DRPYA

NAME E. Goodwin J. Roe

DATE / /97 1 /97

  • See previous concurrence

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TAG\INFAC

W . I a. I

K) IN 97-XX

September XX, 1997 This information notice requires no specifi action or written response. However, recipients

are reminded that they are required to industry-wide operating experience (including

NRC information notices) where practical, when setting goals and

performing periodic evaluations under Section 50.65, "Requirement for monitoring the

effectiveness of maintenance at nuclear power plants," to Part 50 of Title 10 of the Code of

Federal Regulations. If you have any questions about the information in this notice, please

contact the technical contact listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: J. Shackelford, RIV

(7817-860-8144

_ E-mail: jls2@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC TECH EDITOR RIV/DRS RIV/DRS l PECB:DRPM

NAME R. Sanders 0 J. Shackelford D. Chamberlain T. Greene

l DATE ljul11/97 //97 1 //97 1 /97 OFC C/EMCB:DE D:DE SL(A)/PECB:DRPM C(A)/PECB:DRPM

NAME J. Strosnider B. Sheron C. Petrone R. Dennig

DATE I /97 _ I/197 //97 1 /97 I OFC

NAME

DIDRPM

J. Roe

DATE l /97

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:%TAGINFAC


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