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

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| issue date = 12/10/1996
| issue date = 12/10/1996
| title = Modifications to Containment Blowout Panels Without Appropriate Design Controls
| title = Modifications to Containment Blowout Panels Without Appropriate Design Controls
| author name = Martin T T
| author name = Martin T
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 9
| page count = 9
}}
}}
{{#Wiki_filter:KJ~UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:KJ~


COMMISSION
===UNITED STATES===
NUCLEAR REGULATORY COMMISSION


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


NOTICE 96-64: MODIFICATIONS
===December 10, 1996===
NRC INFORMATION NOTICE 96-64: MODIFICATIONS TO CONTAINMENT BLOWOUT


TO CONTAINMENT
===PANELS WITHOUT APPROPRIATE DESIGN===
 
CONTROLS
BLOWOUT PANELS WITHOUT APPROPRIATE
 
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


hasps and locks without appropriate
DfP


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


Additionally, several steam generator
rupture at a higher pressure than credited in the High Energy Line Break analysis. This was


and reactor coolant loop containment
9612060222n


cubicle door panels had been modified by tack welding their sheet metal covers to the door frames and adding stiffener
POR


plates around the door handles. These modifications
tE 0 it r-te


were not reviewed prior to installation
IN 96-64 December 10, 1996 apparently attributable to an inadequate investigation of the blowout panels' design basis


to assure their compliance
functions prior to the initiation of the maintenance.


with design bases assumptions
Quad Cities


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


in the Updated Final Safety Analysis Report (UFSAR), and existed for an extended time period during past operating
secondary containment barrier for the refueling floors on both Units. Subsequent


cycles.Cooper On November 21, 1995, it was recognized
documented inspections revealed approximately 270 (out of 1496) damaged explosion bolts.


that the accident analysis for High Energy Line Break outside Primary Containment
It was observed that not all of the damaged bolts were a result of this tornado. On


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


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


that had been rendered invalid. For a postulated
containment In an inoperable condition. The previously damaged explosion bolts were


High Energy Line Break inside the Reactor Building Main Steam Tunnel (Steam Tunnel), the Steam Tunnel blowout panels had been credited with rupturing
damaged by either a pressure load or by ineffective work practices.


to allow a vent path to the Turbine Building, thereby preventing
===Nine Mile Point, Unit 1===
On October 25, 1993, i was determined that the relief (blowout) panels in the Nine Mile Point


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


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


In an effort to reduce Secondary
higher ultimate strength than designed. The initial engineering evaluation of this condition


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


leakage, maintenance
2.87 kph (60 VIWf


was performed
2) and 2.54 kph (53 VbWt2), respectively, to relieve internal building pressure


on the DfP blowout panels in 1985 to cover them with fiberglass.
prior to structural failure of the buildings, and the panels were declared operable. On


As a result, the blowout panels would rupture at a higher pressure than credited in the High Energy Line Break analysis.
March 27, 1995, i was determined that there was an error in the design assumptions for load


This was 9612060222n
distribution. Revised calculations confirmed that the relief panels would not blow out until the


POR tE 0 it r-te
internal building pressure exceeded the minimum documented building structural design of


IN 96-64 December 10, 1996 apparently
3.83 kph (80 VIW 2). The cause of this event was inadequate quality control measures during


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


to an inadequate
Discussion


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


of the blowout panels' design basis functions
compartment or other enclosure that could be structurally damaged due to a high energy line


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


of the maintenance.
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


Quad Cities On May 10, 1996, a tornado caused structural
accident in which a high energy line break is postulated to occur as a passive or


damage to the metal siding that forms the secondary
consequential additional failure. In addition to the overpressure "active" function, blowout


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


barrier for the refueling
Blowout panels are designed to open at specific design differential pressures. Licensees


floors on both Units. Subsequent
discovered that as-found configurations either would not allow the panels to open until after


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


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


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


270 (out of 1496) damaged explosion
IN 96-64 December 10, 1996 adequately consider the design assumptions used for analyzing containment structures and


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


for the siding would have been met and this would have placed secondary containment
structures outside of their design bases.


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


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


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


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


bolts were damaged by either a pressure load or by ineffective
Office of Nuclear Reactor Regulation Project Manager.


work practices.
References


Nine Mile Point, Unit 1 On October 25, 1993, i was determined
1.


that the relief (blowout)  
NRC Inspection Report 50-338/96-01 & 501339/96-01, dated March 21, 1996, (Accession Number 9604090115)
panels in the Nine Mile Point Unit I turbine and reactor buildings
2.


would not blow out at the design pressure of 2.15 kph (45 lbfft 2) because the bolt fasteners
Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated


for the panels were larger than designed and had a higher ultimate strength than designed.
May 31, 1996, (Accession Number 9606110378)
3.


The initial engineering
Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)
4.


evaluation
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


of this condition erroneously
===Division of Reactor Program Management===
Office of Nuclear Reactor Regulation


determined
Technical contacts: Donald R. Taylor, RHI


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


failure of the buildings, and the panels were declared operable.
===Neal K. Hunemuller, NRR===
(301) 415-1152 E-mail: nkh@nrc.gov


On March 27, 1995, i was determined
Attachment: List of Recently Issued Information Notices


that there was an error in the design assumptions
K>
Attachment


for load distribution.
IN 96-64


Revised calculations
===December 10, 1996 LIST OF RECENTLY ISSUED===
NRC INFORMATION NOTICES


confirmed
Information


that the relief panels would not blow out until the internal building pressure exceeded the minimum documented
Date of


building structural
Notice No.


design of 3.83 kph (80 VIW 2). The cause of this event was inadequate
Subject


quality control measures during initial construction
Issuance


which resulted in oversize bolts being installed
Issued to


in the relief panels.Discussion
96-63
96-62
96-61


The purpose of blowout panels is to prevent overpressure
===Potential Safety Issue===
Regarding the Shipment


or overtemperature
of Fissile Material


conditions
===Potential Failure of the===
Instantaneous Trip Function


in a compartment
of General Electric RMS-9 Programmers


or other enclosure
===Failure of a Main Steam Safety===
Valve to Reseat Caused by an


that could be structurally
===Improperly Installed Release===
Nut


damaged due to a high energy line break inside the compartment, or that contains equipment
Potential Common-Mode Post-


that would be damaged by the overpressure
===Accident Failure of Residual===
Heat Removal Heat Exchangers


or overtemperature
===Potential Degradation of===
Post Loss-of-Coolant


condition.
===Recirculation Capability===
as a Result of Debris


This function may or may not be a "safety-related" function depending
===RCP Seal Replacement with===
Pump on Backseat


on whether the high energy line break could result in loss of (1)the capability
12/05/96
11/20/96
11/20/96
11/14/96
10/30/96
10/30/96


to reach and maintain safe shutdown, or (2) the capability
===All U.S. Nuclear===
Regulatory Commission


to mitigate an accident in which a high energy line break is postulated
licensees authorized


to occur as a passive or consequential
to possess special


additional
nuclear material in


failure. In addition to the overpressure "active" function, blowout panels may also have a passive function such as tornado missile protection.
unsealed quantities


Blowout panels are designed to open at specific design differential
greater than a critical


pressures.
mass


Licensees discovered
===All holders of OLs===
and CPs for nuclear


that as-found configurations
power plants


either would not allow the panels to open until after exceeding
===All holders of OLs or===
CPs for nuclear power


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


design bases described
===All holders of OLs or===
CPs for nuclear power


in the UFSAR. Modifications
reactors


made to satisfy apparently
===All holders of OLs or===
CPs for nuclear power


valid concerns did not adequately
reactors


evaluate the effects on the panels' design bases or
===All holders of OLs or===
CPs for pressurized-water


IN 96-64 December 10, 1996 adequately
reactors


consider the design assumptions
96-60
96-59
96-58 OL = Operating License


used for analyzing
CP = Construction Permit


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


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


and supports.
structures outside of their design bases.


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


were not recognized
Safety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).


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


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


outside of their design bases.Previous Similar Generic Communication
Office of Nuclear Reactor Regulation Project Manager.


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


with the Updated Final Safety Analysis Report," dated March 18, 1996, (Accession
1.


No. 9603150213).
NRC Inspection Report 50-338/96-01 & 50/339/96-01, dated March 21, 1996, (Accession Number 9604090115)
2.


This information
Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated


notice requires no written response.
May 31, 1996, (Accession Number 9606110378)
3.


If you have any questions
Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)
4.


about the information
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


in this notice, please contact the technical
hLhomas T. Martin, Director
 
contacts listed below or the appropriate


===Division of Reactor Program Management===
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
(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
(301) 415-1152 E-mail: nkhenrc.gov


Number 9606110378)
Attachment: List of Recently Issued Information Notices
3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &50-265/96-016, dated September


20, 1996, (Accession
===Tech Editor has reviewed and concurred on===
DOCUMENT NAME: 96-64.IN


Number 9609300009)
* See previous concurrence
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220195-005-01, dated June 26, 1996, (Accession


Number 9607010370)
To receive a copy of this document, Indicate In the box: "C" a Copy without enclosures "EN'
r Thomas T. Martin, Director Division of Reactor Program Management
E


===Office of Nuclear Reactor Regulation===
Copy wqtpcdures "N" - No copy
Technical


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


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


Attachment:  
C:SCSB
List of Recently Issued Information


Notices
C:PECB


K>Attachment
D:DRP9 O/1 I


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


NOTICES Information
INHunemuller


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


Safety Issue Regarding
AChaffee*
TMartW f I


the Shipment of Fissile Material Potential
DATE


Failure of the Instantaneous
12/
/96
11/18/96
11/22/96
12/ /96


Trip Function of General Electric RMS-9 Programmers
===OFFICIAL RECORD COPY===


Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly
K-,
IN 96-xx


Installed
November xx, 1996 adequately consider the design assumptions used for analyzing containment struct


Release Nut Potential
sand


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


Post-Accident Failure of Residual Heat Removal Heat Exchangers
potential to place the structures outside of their design bases.


Potential
===Previous Similar Generic Communication===
NRC Information Notice 96-17, "Reactor Operations Inconsistenth the Updated Final


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


of Post Loss-of-Coolant
This information notice requires no written response. If


Recirculation
u have any questions about the


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


as a Result of Debris RCP Seal Replacement
Office of Nuclear Reactor Regulation Project Managr.


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
References


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


licensees
Number 9604090115)
2. Cooper Nuclear Station License


authorized
vent Report 50-298/95-018-01, dated


to possess special nuclear material in unsealed quantities
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


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
June 26, 1996, (A


reactors 96-60 96-59 96-58 OL = Operating
sion Number 9607010370)


License CP = Construction
===Thomas T. Martin, Director===
Division of Reactor Program Management


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


IN 96-64* -K' December 10, 1996 adequately
(540) 984-5421 E-mail: drt@nrc.gov


consider the design assumptions
===Neal K. Hunemuller, NRR===
(301) 415-1152 E-mail: nkh@nrc.gov


used for analyzing
Attachment: List of Recently Issued Information Notices


containment
DOC


structures
ENT NAME: G:INKHXBLWTPNLS.IN


and supports.
===See previous concurren===
To rle


The modifications
a copy of this document, Indicate In the box: "C"
* Copy without enclosures "E" - copy w igsures "N" No copy


were not recognized
OYFICE


as having the potential
PECB


to place the structures
C:SCSB


outside of their design bases.Previous Similar Generic Communication
I


NRC Information
C:PECB


Notice 96-17, "Reactor Operations
D:DR


Inconsistent
r


with the Updated Final Safety Analysis Report," dated March 18, 1996, (Accession
NAME


No. 9603150213).
NHunemuller


This information
CBerlinger *
AChaffee*
TMartfn 1n!
DATE


notice requires no written response.
11/ /96
11/18/96
11/22/96
/ /96D


If you have any questions
OFFICIAL RECORD COPY-


about the information
v>
K>~
IN 96-xx


in this notice, please contact the technical
===November xx, 1996===
Pane% 3 nf R


contacts listed below or the appropriate
meet all of the secondary containment design bases described In the UFSA


Office of Nuclear Reactor Regulation
Modifications made to satisfy apparently valid concerns did not adequa


===Project Manager.References===
evaluate
1. NRC Inspection


Report 50-338/96-01
the effects on the panels' design bases or adequately consider the de gn
& 50/339/96-01, dated March 21, 1996, (Accession


Number 9604090115)
assumptions used for analyzing containment structures and suppo
2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated May 31, 1996, (Accession


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


20, 1996, (Accession
modifications were not recognized as having the potential to pia


Number 9609300009)
the structures
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-005-01, dated June 26, 1996, (Accession


Number 9607010370)
outside of their design bases.
original signed by D.B. Matthews hLhomas T. Martin, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
Previous Similar Generic Communications
Technical


contacts:
/
Donald R. Taylor, RII (540) 984-5421 E-mail: drt@nrc.gov
NRC Information Notice 96-17, "Reactor Operations


Neal K. Hunemuller, NRR (301) 415-1152 E-mail: nkhenrc.gov
consistent with the Updated Final


Attachment:
Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).
List of Recently Issued Information


Notices Tech Editor has reviewed and concurred
This information notice requires no written r ponse. If you have any questions about


on DOCUMENT NAME: 96-64.IN
the information in this notice, please con


* See previous concurrence
t the technical contacts listed below or the


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
appropriate Office of Nuclear Reactor R ulation Project Manager.


CBerlinger
References


AChaffee*
1.
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
NRC Inspection Report


consider the design assumptions
i38196-01
& 601339196-01, dated March 21, 1996, (Accession Number 96 090115)
2.


used for analyzing
Cooper Nuclear Staon Licensee Event Report 60-298195-018-01, dated


containment
May 31, 1996, (Ac


struct sand containment
sslon Number 9606110378)
3.


structures
Quad Cities N lear Power Station Licensee Event Report 50-254 &
60-265196-01 dated September20, 1996, (Accession Number9609300009)
4.


and supports.
Nine Mile


The modifications
Iont Nuclear Station Unit I Licensee Event Report 50-220195-005-01, dated Jue 26, 1996, (Accession Number 9607010370)
contacts:


were not recognized
===Thomas T. Martin, Director===
Division of Reactor Program Management


a aving the potential
===Office of Nuclear Reactor Regulation===
Donald R. Taylor, RH


to place the structures
(540) 984-5421 E-mall: drt@nrc.gov


outside of their design bases.Previous Similar Generic Communication
===Neal K. Hunemuller, NRR===
(301) 415-1152 E-mall: nkh@nrc.gov


NRC Information
Attachment: List of Recently Issued Information Notices


Notice 96-17, "Reactor Operations
TACt


Inconsistenth
q4 2 6°
DOCUMENT NAME: G:INKHRBLWTPNLS.IN


the Updated Final Safety Analysis Report," dated March 18, 1996, (Accession
* See previous concurrence


N .9603150213).
To receive a copy of this document, Indicate In the box: "C" = Copy without enclosures wE" - Copy with enclosures "N" n No copy


This information
OFFICE


notice requires no written response.
PECB


If u have any questions
J .


about the information
C:SCSB


in this notice, please contact the technical
I


ontacts listed below or the appropriate
C:PECB


Office of Nuclear Reactor Regulation
D:DRPM l


===Project Managr.References===
NAME
1. NRC Inspection


Report 50-338/96-01
NHunemullert
0/339/96-01, dated March 21, 1996, (Accession


Number 9604090115)
CBerlinger *
2. Cooper Nuclear Station License vent Report 50-298/95-018-01, dated May 31, 1996, (Accession
AChaffee Ok& ITMartin


Num er 9606110378)
DATE
3. Quad Cities Nuclear Power tation Licensee Event Report 50-254 &50-265/96-016, dated Se ember 20, 1996, (Accession


Number 9609300009)
11/L/96
4. Nine Mile Point Nule Station Unit 1 Licensee Event Report 50-220/95-005-01, dated June 26, 1996, (A sion Number 9607010370)
11/18/96
Thomas T. Martin, Director Division of Reactor Program Management
11/L/96
'
11/ /96


===Office of Nuclear Reactor Regulation===
===OFFICIAL RECORD COPY===
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
v


Attachment:
IN 96-xx
List of Recently Issued Information


Notices DOC ENT NAME: G:INKHXBLWTPNLS.IN
===November xx, 1996===
for analyzing containment structures and supports: The modifications were not


See previous concurren To rle a copy of this document, Indicate In the box: "C"
recognized as having the potential to place the structures outside of their
* Copy without enclosures "E" -copy w igsures "N" No copy OYFICE PECB C:SCSB I C:PECB D:DR r NAME NHunemuller


CBerlinger
design bases.


* AChaffee*
===Previous Similar Generic Communications===
TMartfn 1n!DATE 11/ /96 11/18/96 11/22/96 / /96D OFFICIAL RECORD COPY-
NRC Information Notice 96-17, "Reactor Operations Inconsistent with
v>K>~IN 96-xx November xx, 1996 Pane% 3 nf R meet all of the secondary


containment
Updated Final Safety Analysis Report," dated March 18, 1996, (Acc


design bases described
9603150213).


In the UFSA Modifications
This information notice requires no written response. If y


made to satisfy apparently
have


valid concerns did not adequa evaluate the effects on the panels' design bases or adequately
questions about the information in this notice, please cotact the 1 contacts listed below or the appropriate Office of Nuci r Reactor I


consider the de gn assumptions
Project Manager.


used for analyzing
ion No.


containment
any


structures
technical


and suppo .The modifications
Regulation


were not recognized
References


as having the potential
1.


to pia the structures
NRC Inspection Report 50-338/96-01 & 50/
(Accession Number 9604090115)
-01, dated March 21, 1996,
2.


outside of their design bases.Previous Similar Generic Communications
Cooper Nuclear Station Licensee Eve


/NRC Information
Report 50-298/95-018-01, dated


Notice 96-17, "Reactor Operations
May 31. 1996, (Accession Number 96 110378)
3.


consistent
Quad Cities Nuclear Power Stati


with the Updated Final Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).
Licensee Event Report 50-254 &
50-265/96-016, dated September 20, 1996, (Accession Number 9609300009)
4.


This information
Nine Mile Point Nuclear St ion Unit 1 Licensee Event Report 50-220/95-
005-01, dated June 26, 19 , (Accession Number 9607010370)


notice requires no written r ponse. If you have any questions
===Thomas T. Martin, Director===
Division of Reactor Program Management


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


in this notice, please con t the technical
(540) 984-5421 E-mail drt@nrc.gov


contacts listed below or the appropriate
===Neal K. Hunemuller, NRR===
(301) 415-1152 E-mail nkh@nrc.gov


Office of Nuclear Reactor R ulation Project Manager.References
Attachment. ist of Recently Issued Information Notices


1. NRC Inspection
DOCUMENT NAME:  
 
:\\NKH\\BLWTPNLS.IN
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 ecelve a copy of
 
wE" -Copy with enclosures "N" n No copy OFFICE PECB J .C:SCSB I C:PECB D:DRPM l NAME NHunemullert


CBerlinger
Is


* AChaffee Ok& ITMartin DATE 11/L/96 11/18/96 11/L/96 ' 11/ /96 OFFICIAL RECORD COPY
document, Indicate In the box: "C" - Copy without encosures "E"
- Copy with enclosures "N"
N


v IN 96-xx November xx, 1996 for analyzing
No copy


containment
OFFICE 1PEV


structures
l. 1C:SCSB


and supports:  
C:PECB
The modifications


were not recognized
D:DRPM


as having the potential
NAME


to place the structures
N nemuller %M


outside of their design bases.Previous Similar Generic Communications
CBerlinger *
AChaffee


NRC Information
TMartin


Notice 96-17, "Reactor Operations
DATE


Inconsistent
1/f?/96
11/18/96
11/
/96
11/
/96
/


with Updated Final Safety Analysis Report," dated March 18, 1996, (Acc 9603150213).
===Ukt lIAL KtLUKU L Y===
A . '4 L


This information
IN 96-xx


notice requires no written response.
* .November


If y have questions
xx. 1996 This information notice requires no written response. If you have any


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


in this notice, please cotact the 1 contacts listed below or the appropriate
contacts listed below or the appropriate Office of Nuclear Reactor Regulation


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


References
References


1. NRC Inspection
1.
 
Report 50-338/96-01
& 50/(Accession
 
Number 9604090115)
-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
 
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)
NRC Inspection Report 50-338/96-01 & 50/339/96-01. dated March 21. 1996.
Thomas T. Martin, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
(Accession Number 9604090115)
Technical
2.


contacts:
Cooper Nuclear Station Licensee Event Report 50-298/95-018-01. dated
onald R. Taylor. RII (540) 984-5421 E-mail drt@nrc.gov


Neal K. Hunemuller, NRR (301) 415-1152 E-mail nkh@nrc.gov
May 31. 1996, (Accession Number 9606110378)
3.


Attachment.
Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
50-265/96-016, dated September 20. 1996. (Accession Number 9609300009)
4.


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


Notices DOCUMENT NAME: :\NKH\BLWTPNLS.IN
===Thomas T. Martin. Director===
 
Division of Reactor Program Management
* 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
 
* 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===
===Office of Nuclear Reactor Regulation===
Project Manager.References
Technical contacts:
 
1. NRC Inspection
 
Report 50-338/96-01
& 50/339/96-01.


dated March 21. 1996.(Accession
===Donald R. Taylor, RII===
(540) 984-5421 E-mail drt@nrc.gov


Number 9604090115)
===Neal K. Hunemuller, NRR===
2. Cooper Nuclear Station Licensee Event Report 50-298/95-018-01.
(301) 415-1152 E-mail nkh@nrc.gov


dated May 31. 1996, (Accession
Attachment:List of Recently Issued Information Notices


Number 9606110378)
DOCUMENT NAME: G:\\NKH\\BLWTPNLS.IN
3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &50-265/96-016, dated September


20. 1996. (Accession
To receive a copy of this document, Indicate In tlh-
")
"
Copy without enclosures "En - Copy with enclosures "NW - No copy


Number 9609300009)
(OFFICE
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-
005-01, dated June 26. 1996. (Accession


Number 9607010370)
PECB
Thomas T. Martin. Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
l
Technical


contacts:  
C:SCS6 A
Donald R. Taylor, RII (540) 984-5421 E-mail drt@nrc.gov


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


Attachment:List
l


of Recently Issued Information
D:DRPM l


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


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/  
NHunemullerm/ ' CBerlinger
' CBerlinger


IAChaffee
IAChaffee


MTartin DATE 11//5/96 111/ 96 &I11/ /96 11/ /96 OFFICIAXL
MTartin
 
DATE


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


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

Latest revision as of 10:54, 16 January 2025

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 VbWt2), 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

96-62

96-61

Potential Safety Issue

Regarding the Shipment

of Fissile Material

Potential Failure of the

Instantaneous Trip Function

of General Electric RMS-9 Programmers

Failure of a Main Steam Safety

Valve to Reseat Caused by an

Improperly Installed Release

Nut

Potential Common-Mode Post-

Accident Failure of Residual

Heat Removal Heat Exchangers

Potential Degradation of

Post Loss-of-Coolant

Recirculation Capability

as a Result of Debris

RCP Seal Replacement 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 Commission

licensees authorized

to possess special

nuclear material in

unsealed quantities

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

reactors

96-60

96-59

96-58 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

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

CBerlinger

AChaffee*

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 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-

v>

K>~

IN 96-xx

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

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

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

9603150213).

This information notice requires no written response. If y

have

questions about the information in this notice, please cotact the 1 contacts listed below or the appropriate Office of Nuci r Reactor I

Project Manager.

ion No.

any

technical

Regulation

References

1.

NRC Inspection Report 50-338/96-01 & 50/

(Accession Number 9604090115)

-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 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

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 *

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

CPECB

l

D:DRPM l

NAME

NHunemullerm/ ' CBerlinger

IAChaffee

MTartin

DATE

11//5/96

111/ 96

&I11/

/96

11/

/96 OFFICIAXL RECORD COPY


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