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 STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001December 10, 1996NRC INFORMATION NOTICE 96-64: MODIFICATIONS TO CONTAINMENT BLOWOUTPANELS WITHOUT APPROPRIATE DESIGNCONTROLS
{{#Wiki_filter: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==
==Addressees==
All holders of operating licenses or construction permits for nuclear powerreactors.
All holders of operating
 
licenses or construction
 
permits for nuclear power reactors.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alertaddressees to the potential for operating outside of the design basis as a result of modifyingstructures without appropriate design controls. It is expected that recipients will review theinformation for applicability to their facilities and consider actions, as appropriate, to avoidsimilar problems. However, suggestions contained in this information notice are not NRCrequirements; therefore, no specific action or written response is required.
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 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
 
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)
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


==Description of Circumstances==
Number 9606110378)
North Anna, Units 1 & 2On February 13, 1996, it was identified that six blowout panels for both units' incoreinstrument tunnels had been modified by installing hasps and locks without appropriatedesign controls. Additionally, several steam generator and reactor coolant loop containmentcubicle door panels had been modified by tack welding their sheet metal covers to the doorframes and adding stiffener plates around the door handles. These modifications were notreviewed prior to installation to assure their compliance with design bases assumptionscontained in the Updated Final Safety Analysis Report (UFSAR), and existed for an extendedtime period during past operating cycles.CooperOn November 21, 1995, it was recognized that the accident analysis for High Energy LineBreak outside Primary Containment contained a key assumption that had been renderedinvalid. For a postulated High Energy Line Break inside the Reactor Building Main SteamTunnel (Steam Tunnel), the Steam Tunnel blowout panels had been credited with rupturing toallow a vent path to the Turbine Building, thereby preventing compartment overpressurization.In an effort to reduce Secondary Containment leakage, maintenance was performed on the DfPblowout panels in 1985 to cover them with fiberglass. As a result, the blowout panels wouldrupture at a higher pressure than credited in the High Energy Line Break analysis. This was9612060222n POR tE 0 it r-te
3. Quad Cities Nuclear Power Station Licensee Event Report 50-254 &50-265/96-016, dated September


IN 96-64December 10, 1996 apparently attributable to an inadequate investigation of the blowout panels' design basisfunctions prior to the initiation of the maintenance.Quad CitiesOn May 10, 1996, a tornado caused structural damage to the metal siding that forms thesecondary containment barrier for the refueling floors on both Units. Subsequentdocumented 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. OnAugust 23, 1996, it was concluded, through calculations, that not all of the designrequirements for the siding would have been met and this would have placed secondarycontainment In an inoperable condition. The previously damaged explosion bolts weredamaged by either a pressure load or by ineffective work practices.Nine Mile Point, Unit 1On October 25, 1993, i was determined that the relief (blowout) panels in the Nine Mile PointUnit 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 ahigher ultimate strength than designed. The initial engineering evaluation of this conditionerroneously determined that the turbine and reactor building panels would blow out at2.87 kph (60 VIWf2) and 2.54 kph (53 VbWt2), respectively, to relieve internal building pressureprior to structural failure of the buildings, and the panels were declared operable. OnMarch 27, 1995, i was determined that there was an error in the design assumptions for loaddistribution. Revised calculations confirmed that the relief panels would not blow out until theinternal building pressure exceeded the minimum documented building structural design of3.83 kph (80 VIW2). The cause of this event was inadequate quality control measures duringinitial construction which resulted in oversize bolts being installed in the relief panels.DiscussionThe purpose of blowout panels is to prevent overpressure or overtemperature conditions in acompartment or other enclosure that could be structurally damaged due to a high energy linebreak inside the compartment, or that contains equipment that would be damaged by theoverpressure 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 anaccident in which a high energy line break is postulated to occur as a passive orconsequential additional failure. In addition to the overpressure "active" function, blowoutpanels may also have a passive function such as tornado missile protection.Blowout panels are designed to open at specific design differential pressures. Licenseesdiscovered that as-found configurations either would not allow the panels to open until afterexceeding the design pressure, or in the Quad Cities example, did not meet all of secondarycontainment design bases described in the UFSAR. Modifications made to satisfy apparentlyvalid concerns did not adequately evaluate the effects on the panels' design bases or
20. 1996. (Accession


IN 96-64December 10, 1996 adequately consider the design assumptions used for analyzing containment structures andsupports. The modifications were not recognized as having the potential to place thestructures outside of their design bases.Previous Similar Generic CommunicationNRC Information Notice 96-17, "Reactor Operations Inconsistent with the Updated FinalSafety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).This information notice requires no written response. If you have any questions about theinformation in this notice, please contact the technical contacts listed below or the appropriateOffice of Nuclear Reactor Regulation Project Manager.References1. 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, datedMay 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) r Thomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Donald R. Taylor, RHI(540) 984-5421E-mail: drt@nrc.govNeal K. Hunemuller, NRR(301) 415-1152E-mail: nkh@nrc.govAttachment: List of Recently Issued Information Notices
Number 9609300009)
4. Nine Mile Point Nuclear Station Unit 1 Licensee Event Report 50-220/95-
005-01, dated June 26. 1996. (Accession


K>AttachmentIN 96-64December 10, 1996 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to96-6396-6296-61Potential Safety IssueRegarding the Shipmentof Fissile MaterialPotential Failure of theInstantaneous Trip Functionof General Electric RMS-9ProgrammersFailure of a Main Steam SafetyValve to Reseat Caused by anImproperly Installed ReleaseNutPotential Common-Mode Post-Accident Failure of ResidualHeat Removal Heat ExchangersPotential Degradation ofPost Loss-of-CoolantRecirculation Capabilityas a Result of DebrisRCP Seal Replacement withPump on Backseat12/05/9611/20/9611/20/9611/14/9610/30/9610/30/96All U.S. NuclearRegulatory Commissionlicensees authorizedto possess specialnuclear material inunsealed quantitiesgreater than a criticalmassAll holders of OLsand CPs for nuclearpower plantsAll holders of OLs orCPs for nuclear powerreactorsAll holders of OLs orCPs for nuclear powerreactorsAll holders of OLs orCPs for nuclear powerreactorsAll holders of OLs orCPs for pressurized-waterreactors96-6096-5996-58OL = Operating LicenseCP = Construction Permit
Number 9607010370)
Thomas T. Martin. Director Division of Reactor Program Management


IN 96-64* -K' December 10, 1996 adequately consider the design assumptions used for analyzing containment structures andsupports. The modifications were not recognized as having the potential to place thestructures outside of their design bases.Previous Similar Generic CommunicationNRC Information Notice 96-17, "Reactor Operations Inconsistent with the Updated FinalSafety Analysis Report," dated March 18, 1996, (Accession No. 9603150213).This information notice requires no written response. If you have any questions about theinformation in this notice, please contact the technical contacts listed below or the appropriateOffice of Nuclear Reactor Regulation Project Manager.References1. 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, datedMay 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. MatthewshLhomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Donald R. Taylor, RII(540) 984-5421E-mail: drt@nrc.govNeal K. Hunemuller, NRR(301) 415-1152E-mail: nkhenrc.govAttachment: List of Recently Issued Information NoticesTech Editor has reviewed and concurred onDOCUMENT NAME: 96-64.IN
===Office of Nuclear Reactor Regulation===
Technical


* See previous concurrenceTo receive a copy of this document, Indicate In the box: "C" a Copy without enclosures "EN' E Copy wqtpcdures "N" -No copyOFFICE PECB C:SCSB C:PECB D:DRP9 O/1 INAME INHunemuller CBerlinger AChaffee* TMartW f IDATE 12/ /96 11/18/96 11/22/96 12/ /96OFFICIAL RECORD COPY
contacts:
Donald R. Taylor, RII (540) 984-5421 E-mail drt@nrc.gov


K-,IN 96-xxNovember xx, 1996 -
Neal K. Hunemuller, NRR (301) 415-1152 E-mail nkh@nrc.gov
v>K>~IN 96-xxNovember xx, 1996Pane% 3 nf Rmeet all of the secondary containment design bases described In the UFSAModifications made to satisfy apparently valid concerns did not adequa evaluatethe effects on the panels' design bases or adequately consider the de gnassumptions used for analyzing containment structures and suppo .Themodifications were not recognized as having the potential to pia the structuresoutside of their design bases.Previous Similar Generic Communications /NRC Information Notice 96-17, "Reactor Operations consistent with the Updated FinalSafety Analysis Report," dated March 18, 1996, cession No. 9603150213).This information notice requires no written r ponse. If you have any questions aboutthe information in this notice, please con t the technical contacts listed below or theappropriate Office of Nuclear Reactor R ulation Project Manager.References1. 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, datedMay 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, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationDonald R. Taylor, RH(540) 984-5421E-mall: drt@nrc.govNeal K. Hunemuller, NRR(301) 415-1152E-mall: nkh@nrc.govAttachment: List of Recently Issued Information Notices TACt q4 2 6°DOCUMENT NAME: G:INKHRBLWTPNLS.IN


* See previous concurrenceTo receive a copy of this document, Indicate In the box: "C" = Copy without enclosures wE" -Copy with enclosures "N" n No copyOFFICE PECB J .C:SCSB I C:PECB D:DRPM lNAME NHunemullert CBerlinger
Attachment:List


* AChaffee Ok& ITMartinDATE 11/L/96 11/18/96 11/L/96 ' 11/ /96OFFICIAL RECORD COPY
of Recently Issued Information


vIN 96-xxNovember xx, 996for analyzing containment structures and supports: The modifications were notrecognized as having the potential to place the structures outside of theirdesign bases.Previous Similar Generic CommunicationsNRC Information Notice 96-17, "Reactor Operations Inconsistent withUpdated Final Safety Analysis Report," dated March 18, 1996, (Acc9603150213).This information notice requires no written response. If y havequestions about the information in this notice, please cotact the 1contacts listed below or the appropriate Office of Nuci r Reactor IProject Manager.ion No.anytechnicalRegulationReferences1. 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, datedMay 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, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: onald R. Taylor. RII(540) 984-5421E-mail drt@nrc.govNeal K. Hunemuller, NRR(301) 415-1152E-mail nkh@nrc.govAttachment. ist of Recently Issued Information NoticesDOCUMENT NAME: :\NKH\BLWTPNLS.IN
Notices DOCUMENT NAME: G:\NKH\BLWTPNLS.IN


* See previous concurrenceTo ecelve a copy of Is document, Indicate In the box: "C" -Copy without encosures "E" -Copy with enclosures "N" N No copyOFFICE 1PEV l. 1C:SCSB C:PECB D:DRPMNAME N nemuller %M CBerlinger
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


* AChaffee TMartinDATE 1/f?/96 11/18/96 11/ /96 11/ /96/Ukt lIAL KtLUKU L YA .'4 L
IAChaffee


IN 96-xx* .November xx. 1996 This information notice requires no written response. If you have anyquestions about the information in this notice, please contact the technicalcontacts listed below or the appropriate Office of Nuclear Reactor RegulationProject Manager.References1. 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. datedMay 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. DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Donald R. Taylor, RII(540) 984-5421E-mail drt@nrc.govNeal K. Hunemuller, NRR(301) 415-1152E-mail nkh@nrc.govAttachment:List of Recently Issued Information NoticesDOCUMENT NAME: G:\NKH\BLWTPNLS.INTo 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 lNAME NHunemullerm/ ' CBerlinger IAChaffee MTartinDATE 11//5/96 111/ 96 &I11/ /96 11/ /96OFFICIAXL RECORD COPY
MTartin DATE 11//5/96 111/ 96 &I11/ /96 11/ /96 OFFICIAXL


}}
RECORD COPY}}


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

Revision as of 13:08, 31 August 2018

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 T
Office of Nuclear Reactor Regulation
To:
References
IN-96-064, NUDOCS 9612060222
Download: ML031050506 (9)


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 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

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)

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