Information Notice 1996-64, Modifications to Containment Blowout Panels Without Appropriate Design Controls: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 14: Line 14:
| page count = 9
| page count = 9
}}
}}
{{#Wiki_filter:KJ~UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:KJ~
                                          UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 December 10, 1996 NRC INFORMATION


NOTICE 96-64: MODIFICATIONS
WASHINGTON, D.C. 20555-0001 December 10, 1996 NRC INFORMATION NOTICE 96-64: MODIFICATIONS TO CONTAINMENT BLOWOUT


TO CONTAINMENT
PANELS WITHOUT APPROPRIATE DESIGN


BLOWOUT PANELS WITHOUT APPROPRIATE
CONTROLS
 
DESIGN CONTROLS


==Addressees==
==Addressees==
All holders of operating
All holders of operating licenses or construction permits for nuclear power


licenses or construction
reactors.
 
permits for nuclear power reactors.


==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
addressees to the potential for operating outside of the design basis as a result of modifying


notice to alert addressees
structures without appropriate design controls. It is expected that recipients will review the


to the potential
information for applicability to their facilities and consider actions, as appropriate, to avoid


for operating
similar problems. However, suggestions contained in this information notice are not NRC


outside of the design basis as a result of modifying structures
requirements; therefore, no specific action or written response is required.


without appropriate
==Description of Circumstances==
North Anna, Units 1 & 2 On February 13, 1996, it was identified that six blowout panels for both units' incore


design controls.
instrument tunnels had been modified by installing hasps and locks without appropriate


It is expected that recipients
design controls. Additionally, several steam generator and reactor coolant loop containment


will review the information
cubicle door panels had been modified by tack welding their sheet metal covers to the door


for applicability
frames and adding stiffener plates around the door handles. These modifications were not


to their facilities
reviewed prior to installation to assure their compliance with design bases assumptions


and consider actions, as appropriate, to avoid similar problems.
contained in the Updated Final Safety Analysis Report (UFSAR), and existed for an extended


However, suggestions
time period during past operating cycles.


contained
Cooper


in this information
On November 21, 1995, it was recognized that the accident analysis for High Energy Line


notice are not NRC requirements;
Break outside Primary Containment contained a key assumption that had been rendered
therefore, no specific action or written response is required.Description


of Circumstances
invalid. For a postulated High Energy Line Break inside the Reactor Building Main Steam


North Anna, Units 1 & 2 On February 13, 1996, it was identified
Tunnel (Steam Tunnel), the Steam Tunnel blowout panels had been credited with rupturing to


that six blowout panels for both units' incore instrument
allow a vent path to the Turbine Building, thereby preventing compartment overpressurization.


tunnels had been modified by installing
In an effort to reduce Secondary Containment leakage, maintenance was performed on the          DfP


hasps and locks without appropriate
blowout panels in 1985 to cover them with fiberglass. As a result, the blowout panels would


design controls.
rupture at a higher pressure than credited in the High Energy Line Break analysis. This was


Additionally, several steam generator
9612060222n              POR            tE    0 it r-te


and reactor coolant loop containment
IN 96-64 December 10, 1996 apparently attributable to an inadequate investigation of the blowout panels' design basis


cubicle door panels had been modified by tack welding their sheet metal covers to the door frames and adding stiffener
functions prior to the initiation of the maintenance.


plates around the door handles. These modifications
Quad Cities


were not reviewed prior to installation
On May 10, 1996, a tornado caused structural damage to the metal siding that forms the


to assure their compliance
secondary containment barrier for the refueling floors on both Units. Subsequent


with design bases assumptions
documented inspections revealed approximately 270 (out of 1496) damaged explosion bolts.


contained
It was observed that not all of the damaged bolts were a result of this tornado. On


in the Updated Final Safety Analysis Report (UFSAR), and existed for an extended time period during past operating
August 23, 1996, it was concluded, through calculations, that not all of the design


cycles.Cooper On November 21, 1995, it was recognized
requirements for the siding would have been met and this would have placed secondary


that the accident analysis for High Energy Line Break outside Primary Containment
containment In an inoperable condition. The previously damaged explosion bolts were


contained
damaged by either a pressure load or by ineffective work practices.


a key assumption
Nine Mile Point, Unit 1 On October 25, 1993, i was determined that the relief (blowout) panels in the Nine Mile Point


that had been rendered invalid. For a postulated
Unit I turbine and reactor buildings would not blow out at the design pressure of 2.15 kph


High Energy Line Break inside the Reactor Building Main Steam Tunnel (Steam Tunnel), the Steam Tunnel blowout panels had been credited with rupturing
(45 lbfft2) because the bolt fasteners for the panels were larger than designed and had a


to allow a vent path to the Turbine Building, thereby preventing
higher ultimate strength than designed. The initial engineering evaluation of this condition


compartment
erroneously determined that the turbine and reactor building panels would blow out at


overpressurization.
2.87 kph (60 VIWf  2) and 2.54 kph (53 VbWt  2), respectively, to relieve internal building pressure


In an effort to reduce Secondary
prior to structural failure of the buildings, and the panels were declared operable. On


Containment
March 27, 1995, i was determined that there was an error in the design assumptions for load


leakage, maintenance
distribution. Revised calculations confirmed that the relief panels would not blow out until the


was performed
internal building pressure exceeded the minimum documented building structural design of


on the DfP blowout panels in 1985 to cover them with fiberglass.
3.83 kph (80 VIW 2 ). The cause of this event was inadequate quality control measures during


As a result, the blowout panels would rupture at a higher pressure than credited in the High Energy Line Break analysis.
initial construction which resulted in oversize bolts being installed in the relief panels.


This was 9612060222n
Discussion


POR tE 0 it r-te
The purpose of blowout panels is to prevent overpressure or overtemperature conditions in a


IN 96-64 December 10, 1996 apparently
compartment or other enclosure that could be structurally damaged due to a high energy line


attributable
break inside the compartment, or that contains equipment that would be damaged by the


to an inadequate
overpressure or overtemperature condition. This function may or may not be a "safety- related" function depending on whether the high energy line break could result in loss of (1)
the capability to reach and maintain safe shutdown, or (2) the capability to mitigate an


investigation
accident in which a high energy line break is postulated to occur as a passive or


of the blowout panels' design basis functions
consequential additional failure. In addition to the overpressure "active" function, blowout


prior to the initiation
panels may also have a passive function such as tornado missile protection.


of the maintenance.
Blowout panels are designed to open at specific design differential pressures. Licensees


Quad Cities On May 10, 1996, a tornado caused structural
discovered that as-found configurations either would not allow the panels to open until after


damage to the metal siding that forms the secondary
exceeding the design pressure, or in the Quad Cities example, did not meet all of secondary


containment
containment design bases described in the UFSAR. Modifications made to satisfy apparently


barrier for the refueling
valid concerns did not adequately evaluate the effects on the panels' design bases or


floors on both Units. Subsequent
IN 96-64 December 10, 1996 adequately consider the design assumptions used for analyzing containment structures and


documented
supports. The modifications were not recognized as having the potential to place the


inspections
structures outside of their design bases.


revealed approximately
===Previous Similar Generic Communication===
NRC Information Notice 96-17, "Reactor Operations Inconsistent with the Updated Final


270 (out of 1496) damaged explosion
Safety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).


bolts.It was observed that not all of the damaged bolts were a result of this tornado. On August 23, 1996, it was concluded, through calculations, that not all of the design requirements
This information notice requires no written response. If you have any questions about the


for the siding would have been met and this would have placed secondary containment
information in this notice, please contact the technical contacts listed below or the appropriate


In an inoperable
Office of Nuclear Reactor Regulation Project Manager.


condition.
References
 
The previously
 
damaged explosion
 
bolts were damaged by either a pressure load or by ineffective
 
work practices.
 
Nine Mile Point, Unit 1 On October 25, 1993, i was determined
 
that the relief (blowout)
panels in the Nine Mile Point Unit I turbine and reactor buildings
 
would not blow out at the design pressure of 2.15 kph (45 lbfft 2) because the bolt fasteners
 
for the panels were larger than designed and had a higher ultimate strength than designed.
 
The initial engineering
 
evaluation
 
of this condition erroneously
 
determined
 
that the turbine and reactor building panels would blow out at 2.87 kph (60 VIWf 2) and 2.54 kph (53 VbWt 2), respectively, to relieve internal building pressure prior to structural
 
failure of the buildings, and the panels were declared operable.
 
On March 27, 1995, i was determined
 
that there was an error in the design assumptions
 
for load distribution.
 
Revised calculations
 
confirmed
 
that the relief panels would not blow out until the internal building pressure exceeded the minimum documented
 
building structural
 
design of 3.83 kph (80 VIW 2). The cause of this event was inadequate
 
quality control measures during initial construction
 
which resulted in oversize bolts being installed
 
in the relief panels.Discussion
 
The purpose of blowout panels is to prevent overpressure
 
or overtemperature
 
conditions
 
in a compartment
 
or other enclosure
 
that could be structurally
 
damaged due to a high energy line break inside the compartment, or that contains equipment
 
that would be damaged by the overpressure
 
or overtemperature
 
condition.
 
This function may or may not be a "safety-related" function depending
 
on whether the high energy line break could result in loss of (1)the capability
 
to reach and maintain safe shutdown, or (2) the capability
 
to mitigate an accident in which a high energy line break is postulated
 
to occur as a passive or consequential
 
additional
 
failure. In addition to the overpressure "active" function, blowout panels may also have a passive function such as tornado missile protection.
 
Blowout panels are designed to open at specific design differential
 
pressures.
 
Licensees discovered
 
that as-found configurations
 
either would not allow the panels to open until after exceeding
 
the design pressure, or in the Quad Cities example, did not meet all of secondary containment
 
design bases described
 
in the UFSAR. Modifications
 
made to satisfy apparently
 
valid concerns did not adequately
 
evaluate the effects on the panels' design bases or
 
IN 96-64 December 10, 1996 adequately
 
consider the design assumptions
 
used for analyzing
 
containment
 
structures
 
and supports.
 
The modifications
 
were not recognized
 
as having the potential
 
to place the structures
 
outside of their design bases.Previous Similar Generic Communication


NRC Information
1.      NRC Inspection Report 50-338/96-01 & 501339/96-01, dated March 21, 1996, (Accession Number 9604090115)
2.      Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated


Notice 96-17, "Reactor Operations
May 31, 1996, (Accession Number 9606110378)
3.      Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
        50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)
4.      Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220195-005-01, dated June 26, 1996, (Accession Number 9607010370)
                                      Ž r Thomas T. Martin, Director


Inconsistent
Division of Reactor Program Management
 
with the Updated Final Safety Analysis Report," dated March 18, 1996, (Accession
 
No. 9603150213).
 
This information
 
notice requires no written response.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contacts listed below or the appropriate


Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


===Project Manager.References===
Technical contacts: Donald R. Taylor, RHI
1. NRC Inspection


Report 50-338/96-01
(540) 984-5421 E-mail: drt@nrc.gov
& 501339/96-01, dated March 21, 1996, (Accession


Number 9604090115)
Neal K. Hunemuller, NRR
2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated May 31, 1996, (Accession


Number 9606110378)
(301) 415-1152 E-mail: nkh@nrc.gov
3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &50-265/96-016, dated September


20, 1996, (Accession
Attachment: List of Recently Issued Information Notices


Number 9609300009)
K>
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220195-005-01, dated June 26, 1996, (Accession
                                                                      Attachment


Number 9607010370)
IN 96-64 December 10, 1996 LIST OF RECENTLY ISSUED
r Thomas T. Martin, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
NRC INFORMATION NOTICES
Technical


contacts:
Information                                        Date of
Donald R. Taylor, RHI (540) 984-5421 E-mail: drt@nrc.gov


Neal K. Hunemuller, NRR (301) 415-1152 E-mail: nkh@nrc.gov
Notice No.           Subject                      Issuance    Issued to


Attachment:
96-63          Potential Safety Issue            12/05/96    All U.S. Nuclear
List of Recently Issued Information


Notices
Regarding the Shipment                        Regulatory Commission


K>Attachment
of Fissile Material                            licensees authorized


IN 96-64 December 10, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
to possess special


NOTICES Information
nuclear material in


Date of Notice No. Subject Issuance Issued to 96-63 96-62 96-61 Potential
unsealed quantities


Safety Issue Regarding
greater than a critical


the Shipment of Fissile Material Potential
mass


Failure of the Instantaneous
96-62          Potential Failure of the           11/20/96    All holders of OLs


Trip Function of General Electric RMS-9 Programmers
Instantaneous Trip Function                   and CPs for nuclear


Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly
of General Electric RMS-9                      power plants


Installed
Programmers


Release Nut Potential
96-61          Failure of a Main Steam Safety    11/20/96    All holders of OLs or


Common-Mode
Valve to Reseat Caused by an                  CPs for nuclear power


Post-Accident Failure of Residual Heat Removal Heat Exchangers
Improperly Installed Release                  reactors


Potential
Nut


Degradation
96-60          Potential Common-Mode Post-        11/14/96    All holders of OLs or


of Post Loss-of-Coolant
Accident Failure of Residual                  CPs for nuclear power


Recirculation
Heat Removal Heat Exchangers                  reactors


Capability
96-59          Potential Degradation of          10/30/96    All holders of OLs or


as a Result of Debris RCP Seal Replacement
Post Loss-of-Coolant                          CPs for nuclear power


with Pump on Backseat 12/05/96 11/20/96 11/20/96 11/14/96 10/30/96 10/30/96 All U.S. Nuclear Regulatory
Recirculation Capability                      reactors


Commission
as a Result of Debris


licensees
96-58          RCP Seal Replacement with          10/30/96    All holders of OLs or


authorized
Pump on Backseat                              CPs for pressurized-water


to possess special nuclear material in unsealed quantities
reactors


greater than a critical mass All holders of OLs and CPs for nuclear power plants 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 nuclear power reactors All holders of OLs or CPs for pressurized-water
OL = Operating License


reactors 96-60 96-59 96-58 OL = Operating
CP = Construction Permit


License CP = Construction
IN 96-64
            *    -                                                                      K'        December 10, 1996 adequately consider the design assumptions used for analyzing containment structures and


Permit
supports. The modifications were not recognized as having the potential to place the


IN 96-64* -K' December 10, 1996 adequately
structures outside of their design bases.


consider the design assumptions
Previous Similar Generic Communication


used for analyzing
NRC Information Notice 96-17, "Reactor Operations Inconsistent with the Updated Final


containment
Safety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).


structures
This information notice requires no written response. If you have any questions about the


and supports.
information in this notice, please contact the technical contacts listed below or the appropriate


The modifications
Office of Nuclear Reactor Regulation Project Manager.


were not recognized
References
 
as having the potential
 
to place the structures
 
outside of their design bases.Previous Similar Generic Communication
 
NRC Information
 
Notice 96-17, "Reactor Operations


Inconsistent
1.      NRC Inspection Report 50-338/96-01 & 50/339/96-01, dated March 21, 1996, (Accession Number 9604090115)
            2.      Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated


with the Updated Final Safety Analysis Report," dated March 18, 1996, (Accession
May 31, 1996, (Accession Number 9606110378)
            3.      Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
                    50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)
            4.      Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-005-01, dated June 26, 1996, (Accession Number 9607010370)
                                                                            original signed by D.B. Matthews


No. 9603150213).
hLhomas T. Martin, Director


This information
Division of Reactor Program Management
 
notice requires no written response.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contacts listed below or the appropriate


Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


===Project Manager.References===
Technical contacts: Donald R. Taylor, RII
1. NRC Inspection
 
Report 50-338/96-01
& 50/339/96-01, dated March 21, 1996, (Accession
 
Number 9604090115)
2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated May 31, 1996, (Accession
 
Number 9606110378)
3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &50-265/96-016, dated September
 
20, 1996, (Accession
 
Number 9609300009)
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-005-01, dated June 26, 1996, (Accession
 
Number 9607010370)
original signed by D.B. Matthews hLhomas T. Martin, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
(540) 984-5421 E-mail: drt@nrc.gov
Technical


contacts:
Neal K. Hunemuller, NRR
Donald R. Taylor, RII (540) 984-5421 E-mail: drt@nrc.gov


Neal K. Hunemuller, NRR (301) 415-1152 E-mail: nkhenrc.gov
(301) 415-1152 E-mail: nkhenrc.gov


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


Notices Tech Editor has reviewed and concurred
Tech Editor has reviewed and concurred on


on DOCUMENT NAME: 96-64.IN
DOCUMENT NAME: 96-64.IN


* See previous concurrence
* See previous concurrence


To receive a copy of this document, Indicate In the box: "C" a Copy without enclosures "EN' E Copy wqtpcdures "N" -No copy OFFICE PECB C:SCSB C:PECB D:DRP9 O/1 I NAME INHunemuller
E Copy wqtpcdures "N" - No copy


CBerlinger
To receive a copy of this document, Indicate In the box: "C" a Copy without enclosures "EN'
OFFICE        PECB                      C:SCSB                  C:PECB                    D:DRP9 O/1I


AChaffee*  
NAME        INHunemuller                CBerlinger              AChaffee*                 TMartW   fI
TMartW f I DATE 12/ /96 11/18/96 11/22/96 12/ /96 OFFICIAL RECORD COPY


K-, IN 96-xx November xx, 1996 adequately
DATE          12/    /96               11/18/96                11/22/96                  12/ /96 OFFICIAL RECORD COPY


consider the design assumptions
IN 96-xx


used for analyzing
K-,              November xx, 1996 adequately consider the design assumptions used for analyzing containment struct sand


containment
containment structures and supports. The modifications were not recognized a aving the


struct sand containment
potential to place the structures outside of their design bases.


structures
Previous Similar Generic Communication


and supports.
NRC Information Notice 96-17, "Reactor Operations Inconsistenth the Updated Final


The modifications
Safety Analysis Report," dated March 18, 1996, (Accession N                    .9603150213).


were not recognized
This information notice requires no written response. If u have any questions about the


a aving the potential
information in this notice, please contact the technical ontacts listed below or the appropriate


to place the structures
Office of Nuclear Reactor Regulation Project Managr.


outside of their design bases.Previous Similar Generic Communication
References


NRC Information
1. NRC Inspection Report 50-338/96-01                  0/339/96-01, dated March 21, 1996, (Accession


Notice 96-17, "Reactor Operations
Number 9604090115)
 
          2. Cooper Nuclear Station License vent Report 50-298/95-018-01, dated
Inconsistenth
 
the Updated Final Safety Analysis Report," dated March 18, 1996, (Accession
 
N .9603150213).
 
This information


notice requires no written response.
May 31, 1996, (Accession Num er 9606110378)
          3. Quad Cities Nuclear Power tation Licensee Event Report 50-254 &
            50-265/96-016, dated Se ember 20, 1996, (Accession Number 9609300009)
          4. Nine Mile Point Nule Station Unit 1 Licensee Event Report 50-220/95-005-01, dated


If u have any questions
June 26, 1996, (A            sion Number 9607010370)
                                                                Thomas T. Martin, Director


about the information
Division of Reactor Program Management
 
in this notice, please contact the technical
 
ontacts listed below or the appropriate


Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


===Project Managr.References===
Technica contacts: Donald R. Taylor, RII
1. NRC Inspection


Report 50-338/96-01
(540) 984-5421 E-mail: drt@nrc.gov
0/339/96-01, dated March 21, 1996, (Accession


Number 9604090115)
Neal K. Hunemuller, NRR
2. Cooper Nuclear Station License vent Report 50-298/95-018-01, dated May 31, 1996, (Accession


Num er 9606110378)
(301) 415-1152 E-mail: nkh@nrc.gov
3. Quad Cities Nuclear Power tation Licensee Event Report 50-254 &50-265/96-016, dated Se ember 20, 1996, (Accession


Number 9609300009)
Attachment: List of Recently Issued Information Notices
4. Nine Mile Point Nule Station Unit 1 Licensee Event Report 50-220/95-005-01, dated June 26, 1996, (A sion Number 9607010370)
Thomas T. Martin, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
DOC    ENT NAME: G:INKHXBLWTPNLS.IN                                    See previous concurren
Technica contacts:  
Donald R. Taylor, RII (540) 984-5421 E-mail: drt@nrc.gov


Neal K. Hunemuller, NRR (301) 415-1152 E-mail: nkh@nrc.gov
To rle  a copy of this document, Indicate In the box: "C"
* Copy without enclosures "E"- copy w igsures "N" No copy


Attachment:  
OYFICE    PECB                      C:SCSB          I      C:PECB                  D:DR            r
List of Recently Issued Information


Notices DOC ENT NAME: G:INKHXBLWTPNLS.IN
NAME       NHunemuller                CBerlinger *            AChaffee*                TMartfn 1n!
DATE      11/    /96                11/18/96                11/22/96                      / /96D


See previous concurren To rle a copy of this document, Indicate In the box: "C"
OFFICIAL RECORD COPY-
* Copy without enclosures "E" -copy w igsures "N" No copy OYFICE PECB C:SCSB I C:PECB D:DR r NAME NHunemuller


CBerlinger
IN 96-xx


* AChaffee*
v>                                               K>~           November xx, 1996 Pane%3 nf R
TMartfn 1n!DATE 11/ /96 11/18/96 11/22/96 / /96D OFFICIAL RECORD COPY-
v>K>~IN 96-xx November xx, 1996 Pane% 3 nf R meet all of the secondary


containment
meet all of the secondary containment design bases described In the UFSA


design bases described
Modifications made to satisfy apparently valid concerns did not adequa                                  evaluate


In the UFSA Modifications
the effects on the panels' design bases or adequately consider the de gn


made to satisfy apparently
assumptions used for analyzing containment structures and suppo . The


valid concerns did not adequa evaluate the effects on the panels' design bases or adequately
modifications were not recognized as having the potential to pia the structures


consider the de gn assumptions
outside of their design bases.


used for analyzing
Previous Similar Generic Communications                                    /
            NRC Information Notice 96-17, "Reactor Operations consistent with the Updated Final


containment
Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).


structures
This information notice requires no written r ponse. If you have any questions about


and suppo .The modifications
the information in this notice, please con t the technical contacts listed below or the


were not recognized
appropriate Office of Nuclear Reactor R ulation Project Manager.


as having the potential
References


to pia the structures
1.      NRC Inspection Report                              & 601339196-01, dated March 21, 1996, i38196-01 (Accession Number 96 090115)
            2.      Cooper Nuclear Staon Licensee Event Report 60-298195-018-01, dated


outside of their design bases.Previous Similar Generic Communications
May 31, 1996, (Ac sslon Number 9606110378)
            3.       Quad Cities N lear Power Station Licensee Event Report 50-254 &
                    60-265196-01 dated September20, 1996, (Accession Number9609300009)
            4.      Nine Mile Iont Nuclear Station Unit I Licensee Event Report 50-220195-005-01, dated Jue 26, 1996, (Accession Number 9607010370)
                                                                  Thomas T. Martin, Director


/NRC Information
Division of Reactor Program Management


Notice 96-17, "Reactor Operations
Office of Nuclear Reactor Regulation
 
consistent
 
with the Updated Final Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).


This information
contacts: Donald R. Taylor, RH


notice requires no written r ponse. If you have any questions
(540) 984-5421 E-mall: drt@nrc.gov


about the information
Neal K. Hunemuller, NRR


in this notice, please con t the technical
(301) 415-1152 E-mall: nkh@nrc.gov


contacts listed below or the appropriate
Attachment: List of Recently Issued Information Notices                                             TACt       q4 2 6°
 
DOCUMENT NAME: G:INKHRBLWTPNLS.IN
Office of Nuclear Reactor R ulation Project Manager.References
 
1. NRC Inspection
 
Report i38196-01
& 601339196-01, dated March 21, 1996, (Accession
 
Number 96 090115)2. Cooper Nuclear Staon Licensee Event Report 60-298195-018-01, dated May 31, 1996, (Ac sslon Number 9606110378)
3. Quad Cities N lear Power Station Licensee Event Report 50-254 &60-265196-01 dated September20, 1996, (Accession
 
Number9609300009)
4. Nine Mile Iont Nuclear Station Unit I Licensee Event Report 50-220195-005-01, dated Jue 26, 1996, (Accession
 
Number 9607010370)
contacts: Thomas T. Martin, Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Donald R. Taylor, RH (540) 984-5421 E-mall: drt@nrc.gov
 
Neal K. Hunemuller, NRR (301) 415-1152 E-mall: nkh@nrc.gov
 
Attachment:  
List of Recently Issued Information
 
Notices TACt q4 2 6°DOCUMENT NAME: G:INKHRBLWTPNLS.IN


* See previous concurrence
* See previous concurrence


To receive a copy of this document, Indicate In the box: "C" = Copy without enclosures
To receive a copy of this document, Indicate In the box: "C" = Copy without enclosures wE" - Copy with enclosures "N" n No copy
 
wE" -Copy with enclosures "N" n No copy OFFICE PECB J .C:SCSB I C:PECB D:DRPM l NAME NHunemullert
 
CBerlinger
 
* AChaffee Ok& ITMartin DATE 11/L/96 11/18/96 11/L/96 ' 11/ /96 OFFICIAL RECORD COPY
 
v IN 96-xx November xx, 1996 for analyzing
 
containment


structures
OFFICE        PECB            J . C:SCSB                  I      C:PECB                    D:DRPM l


and supports:
NAME          NHunemullert              CBerlinger        *      AChaffee      Ok& ITMartin
The modifications


were not recognized
DATE        11/L/96                    11/18/96                  11/L/96          '        11/  /96 OFFICIAL RECORD COPY


as having the potential
v


to place the structures
IN 96-xx


outside of their design bases.Previous Similar Generic Communications
November xx, 1996 for analyzing containment structures and supports: The modifications were not


NRC Information
recognized as having the potential to place the structures outside of their


Notice 96-17, "Reactor Operations
design bases.


Inconsistent
Previous Similar Generic Communications


with Updated Final Safety Analysis Report," dated March 18, 1996, (Acc 9603150213).
NRC Information Notice 96-17, "Reactor Operations Inconsistent with


This information
Updated Final Safety Analysis Report," dated March 18, 1996, (Acc                                  ion No.


notice requires no written response.
9603150213).


If y have questions
This information notice requires no written response. If y have any


about the information
questions about the information in this notice, please cotact the 1technical


in this notice, please cotact the 1 contacts listed below or the appropriate
contacts listed below or the appropriate Office of Nuci r Reactor IRegulation


Office of Nuci r Reactor I Project Manager.ion No.any technical Regulation
Project Manager.


References
References


1. NRC Inspection
1.       NRC Inspection Report 50-338/96-01 & 50/                          -01, dated March 21, 1996, (Accession Number 9604090115)
            2.      Cooper Nuclear Station Licensee Eve Report 50-298/95-018-01, dated


Report 50-338/96-01
May 31. 1996, (Accession Number 96 110378)
& 50/(Accession
            3.      Quad Cities Nuclear Power Stati                  Licensee Event Report 50-254 &
                    50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)
            4.      Nine Mile Point Nuclear St ion Unit 1 Licensee Event Report 50-220/95-
                    005-01, dated June 26, 19 , (Accession Number 9607010370)
                                                                Thomas T. Martin, Director


Number 9604090115)
Division of Reactor Program Management
-01, dated March 21, 1996, 2. Cooper Nuclear Station Licensee Eve Report 50-298/95-018-01, dated May 31. 1996, (Accession


Number 96 110378)3. Quad Cities Nuclear Power Stati Licensee Event Report 50-254 &50-265/96-016, dated September
Office of Nuclear Reactor Regulation
 
20, 1996, (Accession
 
Number 9609300009)
4. Nine Mile Point Nuclear St ion Unit 1 Licensee Event Report 50-220/95-
005-01, dated June 26, 19 , (Accession
 
Number 9607010370)
Thomas T. Martin, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
Technical contacts:            onald R. Taylor. RII
Technical


contacts:
(540) 984-5421 E-mail drt@nrc.gov
onald R. Taylor. RII (540) 984-5421 E-mail drt@nrc.gov


Neal K. Hunemuller, NRR (301) 415-1152 E-mail nkh@nrc.gov
Neal K. Hunemuller, NRR


Attachment.
(301) 415-1152 E-mail nkh@nrc.gov


ist of Recently Issued Information
Attachment. ist of Recently Issued Information Notices


Notices DOCUMENT NAME: :\NKH\BLWTPNLS.IN
DOCUMENT NAME:         :\NKH\BLWTPNLS.IN


* See previous concurrence
* See previous concurrence


To ecelve a copy of Is document, Indicate In the box: "C" -Copy without encosures "E" -Copy with enclosures "N" N No copy OFFICE 1PEV l. 1C:SCSB C:PECB D:DRPM NAME N nemuller %M CBerlinger
To ecelve a copy of                                                                                           N No copy


* AChaffee TMartin DATE 1/f?/96 11/18/96 11/ /96 11/ /96/Ukt lIAL KtLUKU L Y A .'4 L
Isdocument, Indicate In the box: "C"- Copy without encosures "E"- Copy with enclosures "N"
OFFICE      1PEV            l. 1C:SCSB                        C:PECB                D:DRPM


IN 96-xx* .November
NAME        N nemuller %M CBerlinger *                       AChaffee              TMartin


xx. 1996 This information
DATE          1/f?/96                11/18/96                11/ /96                11/ /96
          /                                            Ukt lIAL KtLUKU L Y


notice requires no written response.
A . '4 L


If you have any questions
IN 96-xx


about the information
*.November                                                                                          xx. 1996 This information notice requires no written response. If you have any


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


===Office of Nuclear Reactor Regulation===
contacts listed below or the appropriate Office of Nuclear Reactor Regulation
Project Manager.References


1. NRC Inspection
Project Manager.


Report 50-338/96-01
References
& 50/339/96-01.


dated March 21. 1996.(Accession
1.      NRC Inspection Report 50-338/96-01 & 50/339/96-01. dated March 21. 1996.


Number 9604090115)
(Accession Number 9604090115)
2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01.
            2.       Cooper Nuclear Station Licensee Event Report 50-298/95-018-01. dated


dated May 31. 1996, (Accession
May 31. 1996, (Accession Number 9606110378)
            3.      Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
                    50-265/96-016, dated September 20. 1996. (Accession Number 9609300009)
            4.        Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-
                      005-01, dated June 26. 1996. (Accession Number 9607010370)
                                                              Thomas T. Martin. Director


Number 9606110378)
Division of Reactor Program Management
3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &50-265/96-016, dated September


20. 1996. (Accession
Office of Nuclear Reactor Regulation
 
Number 9609300009)
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-
005-01, dated June 26. 1996. (Accession
 
Number 9607010370)
Thomas T. Martin. Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
Technical contacts:              Donald R. Taylor, RII
Technical


contacts:
(540) 984-5421 E-mail drt@nrc.gov
Donald R. Taylor, RII (540) 984-5421 E-mail drt@nrc.gov


Neal K. Hunemuller, NRR (301) 415-1152 E-mail nkh@nrc.gov
Neal K. Hunemuller, NRR


Attachment:List
(301) 415-1152 E-mail nkh@nrc.gov


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


Notices DOCUMENT NAME: G:\NKH\BLWTPNLS.IN
DOCUMENT NAME:         G:\NKH\BLWTPNLS.IN


To receive a copy of this document, Indicate In tlh- ") " Copy without enclosures "En -Copy with enclosures "NW -No copy (OFFICE PECB l C:SCS6 A CPECB l D:DRPM l NAME NHunemullerm/
To receive a copy of this document, Indicate In tlh- ")
' CBerlinger
                                                        " Copy without enclosures "En - Copy with enclosures "NW - No copy


IAChaffee
(OFFICE        PECB            l        C:SCS6 A            CPECBl                  D:DRPM l


MTartin DATE 11//5/96 111/ 96 &I11/ /96 11/ /96 OFFICIAXL
NAME          NHunemullerm/' CBerlinger                    IAChaffee                MTartin


RECORD COPY}}
DATE          11//5/96                  111/ 96        &I11/      /96              11/ /96 OFFICIAXL RECORD COPY}}


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

Revision as of 03:40, 24 November 2019

Modifications to Containment Blowout Panels Without Appropriate Design Controls
ML031050506
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: 12/10/1996
From: Martin T
Office of Nuclear Reactor Regulation
To:
References
IN-96-064, NUDOCS 9612060222
Download: ML031050506 (9)
v • d • e


KJ~

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 December 10, 1996 NRC INFORMATION NOTICE 96-64: MODIFICATIONS TO CONTAINMENT BLOWOUT

PANELS WITHOUT APPROPRIATE DESIGN

CONTROLS

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

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

addressees to the potential for operating outside of the design basis as a result of modifying

structures without appropriate design controls. 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

North Anna, Units 1 & 2 On February 13, 1996, it was identified that six blowout panels for both units' incore

instrument tunnels had been modified by installing hasps and locks without appropriate

design controls. Additionally, several steam generator and reactor coolant loop containment

cubicle door panels had been modified by tack welding their sheet metal covers to the door

frames and adding stiffener plates around the door handles. These modifications were not

reviewed prior to installation to assure their compliance with design bases assumptions

contained in the Updated Final Safety Analysis Report (UFSAR), and existed for an extended

time period during past operating cycles.

Cooper

On November 21, 1995, it was recognized that the accident analysis for High Energy Line

Break outside Primary Containment contained a key assumption that had been rendered

invalid. For a postulated High Energy Line Break inside the Reactor Building Main Steam

Tunnel (Steam Tunnel), the Steam Tunnel blowout panels had been credited with rupturing to

allow a vent path to the Turbine Building, thereby preventing compartment overpressurization.

In an effort to reduce Secondary Containment leakage, maintenance was performed on the DfP

blowout panels in 1985 to cover them with fiberglass. As a result, the blowout panels would

rupture at a higher pressure than credited in the High Energy Line Break analysis. This was

9612060222n POR tE 0 it r-te

IN 96-64 December 10, 1996 apparently attributable to an inadequate investigation of the blowout panels' design basis

functions prior to the initiation of the maintenance.

Quad Cities

On May 10, 1996, a tornado caused structural damage to the metal siding that forms the

secondary containment barrier for the refueling floors on both Units. Subsequent

documented inspections revealed approximately 270 (out of 1496) damaged explosion bolts.

It was observed that not all of the damaged bolts were a result of this tornado. On

August 23, 1996, it was concluded, through calculations, that not all of the design

requirements for the siding would have been met and this would have placed secondary

containment In an inoperable condition. The previously damaged explosion bolts were

damaged by either a pressure load or by ineffective work practices.

Nine Mile Point, Unit 1 On October 25, 1993, i was determined that the relief (blowout) panels in the Nine Mile Point

Unit I turbine and reactor buildings would not blow out at the design pressure of 2.15 kph

(45 lbfft2) because the bolt fasteners for the panels were larger than designed and had a

higher ultimate strength than designed. The initial engineering evaluation of this condition

erroneously determined that the turbine and reactor building panels would blow out at

2.87 kph (60 VIWf 2) and 2.54 kph (53 VbWt 2), respectively, to relieve internal building pressure

prior to structural failure of the buildings, and the panels were declared operable. On

March 27, 1995, i was determined that there was an error in the design assumptions for load

distribution. Revised calculations confirmed that the relief panels would not blow out until the

internal building pressure exceeded the minimum documented building structural design of

3.83 kph (80 VIW 2 ). The cause of this event was inadequate quality control measures during

initial construction which resulted in oversize bolts being installed in the relief panels.

Discussion

The purpose of blowout panels is to prevent overpressure or overtemperature conditions in a

compartment or other enclosure that could be structurally damaged due to a high energy line

break inside the compartment, or that contains equipment that would be damaged by the

overpressure or overtemperature condition. This function may or may not be a "safety- related" function depending on whether the high energy line break could result in loss of (1)

the capability to reach and maintain safe shutdown, or (2) the capability to mitigate an

accident in which a high energy line break is postulated to occur as a passive or

consequential additional failure. In addition to the overpressure "active" function, blowout

panels may also have a passive function such as tornado missile protection.

Blowout panels are designed to open at specific design differential pressures. Licensees

discovered that as-found configurations either would not allow the panels to open until after

exceeding the design pressure, or in the Quad Cities example, did not meet all of secondary

containment design bases described in the UFSAR. Modifications made to satisfy apparently

valid concerns did not adequately evaluate the effects on the panels' design bases or

IN 96-64 December 10, 1996 adequately consider the design assumptions used for analyzing containment structures and

supports. The modifications were not recognized as having the potential to place the

structures outside of their design bases.

Previous Similar Generic Communication

NRC Information Notice 96-17, "Reactor Operations Inconsistent with the Updated Final

Safety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).

This information notice requires no written response. If you have any questions about the

information in this notice, please contact the technical contacts listed below or the appropriate

Office of Nuclear Reactor Regulation Project Manager.

References

1. NRC Inspection Report 50-338/96-01 & 501339/96-01, dated March 21, 1996, (Accession Number 9604090115)

2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated

May 31, 1996, (Accession Number 9606110378)

3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &

50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)

4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220195-005-01, dated June 26, 1996, (Accession Number 9607010370)

Ž r Thomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Donald R. Taylor, RHI

(540) 984-5421 E-mail: drt@nrc.gov

Neal K. Hunemuller, NRR

(301) 415-1152 E-mail: nkh@nrc.gov

Attachment: List of Recently Issued Information Notices

K>

Attachment

IN 96-64 December 10, 1996 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

96-63 Potential Safety Issue 12/05/96 All U.S. Nuclear

Regarding the Shipment Regulatory Commission

of Fissile Material licensees authorized

to possess special

nuclear material in

unsealed quantities

greater than a critical

mass

96-62 Potential Failure of the 11/20/96 All holders of OLs

Instantaneous Trip Function and CPs for nuclear

of General Electric RMS-9 power plants

Programmers

96-61 Failure of a Main Steam Safety 11/20/96 All holders of OLs or

Valve to Reseat Caused by an CPs for nuclear power

Improperly Installed Release reactors

Nut

96-60 Potential Common-Mode Post- 11/14/96 All holders of OLs or

Accident Failure of Residual CPs for nuclear power

Heat Removal Heat Exchangers reactors

96-59 Potential Degradation of 10/30/96 All holders of OLs or

Post Loss-of-Coolant CPs for nuclear power

Recirculation Capability reactors

as a Result of Debris

96-58 RCP Seal Replacement with 10/30/96 All holders of OLs or

Pump on Backseat CPs for pressurized-water

reactors

OL = Operating License

CP = Construction Permit

IN 96-64

  • - K' December 10, 1996 adequately consider the design assumptions used for analyzing containment structures and

supports. The modifications were not recognized as having the potential to place the

structures outside of their design bases.

Previous Similar Generic Communication

NRC Information Notice 96-17, "Reactor Operations Inconsistent with the Updated Final

Safety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).

This information notice requires no written response. If you have any questions about the

information in this notice, please contact the technical contacts listed below or the appropriate

Office of Nuclear Reactor Regulation Project Manager.

References

1. NRC Inspection Report 50-338/96-01 & 50/339/96-01, dated March 21, 1996, (Accession Number 9604090115)

2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated

May 31, 1996, (Accession Number 9606110378)

3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &

50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)

4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-005-01, dated June 26, 1996, (Accession Number 9607010370)

original signed by D.B. Matthews

hLhomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Donald R. Taylor, RII

(540) 984-5421 E-mail: drt@nrc.gov

Neal K. Hunemuller, NRR

(301) 415-1152 E-mail: nkhenrc.gov

Attachment: List of Recently Issued Information Notices

Tech Editor has reviewed and concurred on

DOCUMENT NAME: 96-64.IN

  • See previous concurrence

E Copy wqtpcdures "N" - No copy

To receive a copy of this document, Indicate In the box: "C" a Copy without enclosures "EN'

OFFICE PECB C:SCSB C:PECB D:DRP9 O/1I

NAME INHunemuller CBerlinger AChaffee* TMartW fI

DATE 12/ /96 11/18/96 11/22/96 12/ /96 OFFICIAL RECORD COPY

IN 96-xx

K-, November xx, 1996 adequately consider the design assumptions used for analyzing containment struct sand

containment structures and supports. The modifications were not recognized a aving the

potential to place the structures outside of their design bases.

Previous Similar Generic Communication

NRC Information Notice 96-17, "Reactor Operations Inconsistenth the Updated Final

Safety Analysis Report," dated March 18, 1996, (Accession N .9603150213).

This information notice requires no written response. If u have any questions about the

information in this notice, please contact the technical ontacts listed below or the appropriate

Office of Nuclear Reactor Regulation Project Managr.

References

1. NRC Inspection Report 50-338/96-01 0/339/96-01, dated March 21, 1996, (Accession

Number 9604090115)

2. Cooper Nuclear Station License vent Report 50-298/95-018-01, dated

May 31, 1996, (Accession Num er 9606110378)

3. Quad Cities Nuclear Power tation Licensee Event Report 50-254 &

50-265/96-016, dated Se ember 20, 1996, (Accession Number 9609300009)

4. Nine Mile Point Nule Station Unit 1 Licensee Event Report 50-220/95-005-01, dated

June 26, 1996, (A sion Number 9607010370)

Thomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technica contacts: Donald R. Taylor, RII

(540) 984-5421 E-mail: drt@nrc.gov

Neal K. Hunemuller, NRR

(301) 415-1152 E-mail: nkh@nrc.gov

Attachment: List of Recently Issued Information Notices

DOC ENT NAME: G:INKHXBLWTPNLS.IN See previous concurren

To rle a copy of this document, Indicate In the box: "C"

  • Copy without enclosures "E"- copy w igsures "N" No copy

OYFICE PECB C:SCSB I C:PECB D:DR r

NAME NHunemuller CBerlinger * AChaffee* TMartfn 1n!

DATE 11/ /96 11/18/96 11/22/96 / /96D

OFFICIAL RECORD COPY-

IN 96-xx

v> K>~ November xx, 1996 Pane%3 nf R

meet all of the secondary containment design bases described In the UFSA

Modifications made to satisfy apparently valid concerns did not adequa evaluate

the effects on the panels' design bases or adequately consider the de gn

assumptions used for analyzing containment structures and suppo . The

modifications were not recognized as having the potential to pia the structures

outside of their design bases.

Previous Similar Generic Communications /

NRC Information Notice 96-17, "Reactor Operations consistent with the Updated Final

Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).

This information notice requires no written r ponse. If you have any questions about

the information in this notice, please con t the technical contacts listed below or the

appropriate Office of Nuclear Reactor R ulation Project Manager.

References

1. NRC Inspection Report & 601339196-01, dated March 21, 1996, i38196-01 (Accession Number 96 090115)

2. Cooper Nuclear Staon Licensee Event Report 60-298195-018-01, dated

May 31, 1996, (Ac sslon Number 9606110378)

3. Quad Cities N lear Power Station Licensee Event Report 50-254 &

60-265196-01 dated September20, 1996, (Accession Number9609300009)

4. Nine Mile Iont Nuclear Station Unit I Licensee Event Report 50-220195-005-01, dated Jue 26, 1996, (Accession Number 9607010370)

Thomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

contacts: Donald R. Taylor, RH

(540) 984-5421 E-mall: drt@nrc.gov

Neal K. Hunemuller, NRR

(301) 415-1152 E-mall: nkh@nrc.gov

Attachment: List of Recently Issued Information Notices TACt q4 2 6°

DOCUMENT NAME: G:INKHRBLWTPNLS.IN

  • See previous concurrence

To receive a copy of this document, Indicate In the box: "C" = Copy without enclosures wE" - Copy with enclosures "N" n No copy

OFFICE PECB J . C:SCSB I C:PECB D:DRPM l

NAME NHunemullert CBerlinger * AChaffee Ok& ITMartin

DATE 11/L/96 11/18/96 11/L/96 ' 11/ /96 OFFICIAL RECORD COPY

v

IN 96-xx

November xx, 1996 for analyzing containment structures and supports: The modifications were not

recognized as having the potential to place the structures outside of their

design bases.

Previous Similar Generic Communications

NRC Information Notice 96-17, "Reactor Operations Inconsistent with

Updated Final Safety Analysis Report," dated March 18, 1996, (Acc ion No.

9603150213).

This information notice requires no written response. If y have any

questions about the information in this notice, please cotact the 1technical

contacts listed below or the appropriate Office of Nuci r Reactor IRegulation

Project Manager.

References

1. NRC Inspection Report 50-338/96-01 & 50/ -01, dated March 21, 1996, (Accession Number 9604090115)

2. Cooper Nuclear Station Licensee Eve Report 50-298/95-018-01, dated

May 31. 1996, (Accession Number 96 110378)

3. Quad Cities Nuclear Power Stati Licensee Event Report 50-254 &

50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)

4. Nine Mile Point Nuclear St ion Unit 1 Licensee Event Report 50-220/95-

005-01, dated June 26, 19 , (Accession Number 9607010370)

Thomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: onald R. Taylor. RII

(540) 984-5421 E-mail drt@nrc.gov

Neal K. Hunemuller, NRR

(301) 415-1152 E-mail nkh@nrc.gov

Attachment. ist of Recently Issued Information Notices

DOCUMENT NAME:  :\NKH\BLWTPNLS.IN

  • See previous concurrence

To ecelve a copy of N No copy

Isdocument, Indicate In the box: "C"- Copy without encosures "E"- Copy with enclosures "N"

OFFICE 1PEV l. 1C:SCSB C:PECB D:DRPM

NAME N nemuller %M CBerlinger * AChaffee TMartin

DATE 1/f?/96 11/18/96 11/ /96 11/ /96

/ Ukt lIAL KtLUKU L Y

A . '4 L

IN 96-xx

  • .November xx. 1996 This information notice requires no written response. If you have any

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

contacts listed below or the appropriate Office of Nuclear Reactor Regulation

Project Manager.

References

1. NRC Inspection Report 50-338/96-01 & 50/339/96-01. dated March 21. 1996.

(Accession Number 9604090115)

2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01. dated

May 31. 1996, (Accession Number 9606110378)

3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &

50-265/96-016, dated September 20. 1996. (Accession Number 9609300009)

4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-

005-01, dated June 26. 1996. (Accession Number 9607010370)

Thomas T. Martin. Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Donald R. Taylor, RII

(540) 984-5421 E-mail drt@nrc.gov

Neal K. Hunemuller, NRR

(301) 415-1152 E-mail nkh@nrc.gov

Attachment:List of Recently Issued Information Notices

DOCUMENT NAME: G:\NKH\BLWTPNLS.IN

To receive a copy of this document, Indicate In tlh- ")

" Copy without enclosures "En - Copy with enclosures "NW - No copy

(OFFICE PECB l C:SCS6 A CPECBl D:DRPM l

NAME NHunemullerm/' CBerlinger IAChaffee MTartin

DATE 11//5/96 111/ 96 &I11/ /96 11/ /96 OFFICIAXL RECORD COPY


Retrieved from "https://kanterella.com/w/index.php?title=Information_Notice_1996-64,_Modifications_to_Containment_Blowout_Panels_Without_Appropriate_Design_Controls&oldid=2201361"