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)
(StriderTol Bot change)
 
Line 15: Line 15:
}}
}}
{{#Wiki_filter:KJ~
{{#Wiki_filter:KJ~
                                          UNITED STATES


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


OFFICE OF NUCLEAR REACTOR REGULATION
===OFFICE OF NUCLEAR REACTOR REGULATION===
WASHINGTON, D.C. 20555-0001


WASHINGTON, D.C. 20555-0001 December 10, 1996 NRC INFORMATION NOTICE 96-64: MODIFICATIONS TO CONTAINMENT BLOWOUT
===December 10, 1996===
 
NRC INFORMATION NOTICE 96-64: MODIFICATIONS TO CONTAINMENT BLOWOUT
PANELS WITHOUT APPROPRIATE DESIGN


===PANELS WITHOUT APPROPRIATE DESIGN===
CONTROLS
CONTROLS


Line 74: Line 75:
allow a vent path to the Turbine Building, thereby preventing compartment overpressurization.
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
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
blowout panels in 1985 to cover them with fiberglass. As a result, the blowout panels would
Line 80: Line 83:
rupture at a higher pressure than credited in the High Energy Line Break analysis. This was
rupture at a higher pressure than credited in the High Energy Line Break analysis. This was


9612060222n               POR           tE     0 it r-te
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
IN 96-64 December 10, 1996 apparently attributable to an inadequate investigation of the blowout panels' design basis
Line 104: Line 111:
damaged by either a pressure load or by ineffective work practices.
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
===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
Unit I turbine and reactor buildings would not blow out at the design pressure of 2.15 kph
Line 114: Line 122:
erroneously determined that the turbine and reactor building panels would blow out at
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
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
prior to structural failure of the buildings, and the panels were declared operable. On
Line 124: Line 134:
internal building pressure exceeded the minimum documented building structural design of
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
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.
initial construction which resulted in oversize bolts being installed in the relief panels.
Line 174: Line 184:
References
References


1.     NRC Inspection Report 50-338/96-01 & 501339/96-01, dated March 21, 1996, (Accession Number 9604090115)
1.
2.     Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated
 
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)
May 31, 1996, (Accession Number 9606110378)
3.     Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
3.
        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
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
Office of Nuclear Reactor Regulation


Line 191: Line 208:
(540) 984-5421 E-mail: drt@nrc.gov
(540) 984-5421 E-mail: drt@nrc.gov


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


Line 198: Line 214:


K>
K>
                                                                      Attachment
Attachment


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


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


Information                                       Date of
Information
 
Date of
 
Notice No.
 
Subject
 
Issuance
 
Issued to
 
96-63
96-62
96-61
 
===Potential Safety Issue===
Regarding the Shipment
 
of Fissile Material


Notice No.            Subject                      Issuance    Issued to
===Potential Failure of the===
Instantaneous Trip Function


96-63          Potential Safety Issue            12/05/96    All U.S. Nuclear
of General Electric RMS-9 Programmers


Regarding the Shipment                        Regulatory Commission
===Failure of a Main Steam Safety===
Valve to Reseat Caused by an


of Fissile Material                            licensees authorized
===Improperly Installed Release===
Nut


to possess special
Potential Common-Mode Post-


nuclear material in
===Accident Failure of Residual===
Heat Removal Heat Exchangers


unsealed quantities
===Potential Degradation of===
Post Loss-of-Coolant


greater than a critical
===Recirculation Capability===
as a Result of Debris


mass
===RCP Seal Replacement with===
Pump on Backseat


96-62          Potential Failure of the          11/20/96   All holders of OLs
12/05/96
11/20/96
11/20/96
11/14/96
10/30/96
10/30/96


Instantaneous Trip Function                    and CPs for nuclear
===All U.S. Nuclear===
Regulatory Commission


of General Electric RMS-9                      power plants
licensees authorized


Programmers
to possess special


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


Valve to Reseat Caused by an                  CPs for nuclear power
unsealed quantities


Improperly Installed Release                  reactors
greater than a critical


Nut
mass


96-60          Potential Common-Mode Post-        11/14/96    All holders of OLs or
===All holders of OLs===
and CPs for nuclear


Accident Failure of Residual                  CPs for nuclear power
power plants


Heat Removal Heat Exchangers                  reactors
===All holders of OLs or===
CPs for nuclear power


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


Post Loss-of-Coolant                          CPs for nuclear power
===All holders of OLs or===
CPs for nuclear power


Recirculation Capability                      reactors
reactors


as a Result of Debris
===All holders of OLs or===
CPs for nuclear power


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


Pump on Backseat                              CPs for pressurized-water
===All holders of OLs or===
CPs for pressurized-water


reactors
reactors


OL = Operating License
96-60
96-59
96-58 OL = Operating License


CP = Construction Permit
CP = Construction Permit


IN 96-64
IN 96-64
            *   -                                                                     K'         December 10, 1996 adequately consider the design assumptions used for analyzing containment structures and
*  
-
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
supports. The modifications were not recognized as having the potential to place the
Line 271: Line 330:
structures outside of their design bases.
structures outside of their design bases.


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


Line 285: Line 343:
References
References


1.       NRC Inspection Report 50-338/96-01 & 50/339/96-01, dated March 21, 1996, (Accession Number 9604090115)
1.
            2.       Cooper Nuclear Station Licensee Event Report 50-298/95-018-01, dated
 
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)
May 31, 1996, (Accession Number 9606110378)
            3.       Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
3.
                    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)
Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
                                                                            original signed by D.B. Matthews
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
hLhomas T. Martin, Director


Division of Reactor Program Management
===Division of Reactor Program Management===
 
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Line 304: Line 369:
(540) 984-5421 E-mail: drt@nrc.gov
(540) 984-5421 E-mail: drt@nrc.gov


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


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


Tech Editor has reviewed and concurred on
===Tech Editor has reviewed and concurred on===
 
DOCUMENT NAME: 96-64.IN
DOCUMENT NAME: 96-64.IN


* See previous concurrence
* See previous concurrence


E Copy wqtpcdures "N" - No copy
To receive a copy of this document, Indicate In the box: "C" a Copy without enclosures "EN'
E


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


NAME        INHunemuller                CBerlinger              AChaffee*                TMartW    fI
OFFICE


DATE          12/    /96                11/18/96                11/22/96                  12/ /96 OFFICIAL RECORD COPY
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
IN 96-xx


K-,              November xx, 1996 adequately consider the design assumptions used for analyzing containment struct sand
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
containment structures and supports. The modifications were not recognized a aving the
Line 333: Line 424:
potential to place the structures outside of their design bases.
potential to place the structures outside of their design bases.


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


NRC Information Notice 96-17, "Reactor Operations Inconsistenth the Updated Final
Safety Analysis Report," dated March 18, 1996, (Accession N .9603150213).


Safety Analysis Report," dated March 18, 1996, (Accession N                    .9603150213).
This information notice requires no written response. If


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


information in this notice, please contact the technical ontacts listed below or the appropriate
information in this notice, please contact the technical ontacts listed below or the appropriate
Line 347: Line 439:
References
References


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


Number 9604090115)
Number 9604090115)
          2. Cooper Nuclear Station License vent Report 50-298/95-018-01, dated
2. Cooper Nuclear Station License
 
vent Report 50-298/95-018-01, dated


May 31, 1996, (Accession Num er 9606110378)
May 31, 1996, (Accession Num er 9606110378)
          3. Quad Cities Nuclear Power tation Licensee Event Report 50-254 &
3. Quad Cities Nuclear Power tation Licensee Event Report 50-254 &
            50-265/96-016, dated Se ember 20, 1996, (Accession Number 9609300009)
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
4. Nine Mile Point Nule Station Unit 1 Licensee Event Report 50-220/95-005-01, dated


June 26, 1996, (A           sion Number 9607010370)
June 26, 1996, (A
                                                                Thomas T. Martin, Director


sion Number 9607010370)
===Thomas T. Martin, Director===
Division of Reactor Program Management
Division of Reactor Program Management


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


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


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


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


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


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


OYFICE    PECB                      C:SCSB          I      C:PECB                  D:DR            r
CBerlinger *
AChaffee*
TMartfn 1n!
DATE


NAME      NHunemuller                CBerlinger *            AChaffee*                TMartfn 1n!
11/ /96  
DATE      11/     /96               11/18/96                 11/22/96                     / /96D
11/18/96  
11/22/96  
/ /96D


OFFICIAL RECORD COPY-
OFFICIAL RECORD COPY-


v>
K>~
IN 96-xx
IN 96-xx


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


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


Modifications made to satisfy apparently valid concerns did not adequa                                   evaluate
Modifications made to satisfy apparently valid concerns did not adequa
 
evaluate


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


assumptions used for analyzing containment structures and suppo . The
assumptions used for analyzing containment structures and suppo


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


outside of their design bases.
outside of their design bases.


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


Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).
Safety Analysis Report," dated March 18, 1996, cession No. 9603150213).
Line 409: Line 545:
This information notice requires no written r ponse. If you have any questions about
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
the information in this notice, please con
 
t the technical contacts listed below or the


appropriate Office of Nuclear Reactor R ulation Project Manager.
appropriate Office of Nuclear Reactor R ulation Project Manager.
Line 415: Line 553:
References
References


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


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


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
Division of Reactor Program Management


Office of Nuclear Reactor Regulation
===Office of Nuclear Reactor Regulation===
Donald R. Taylor, RH


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


(540) 984-5421 E-mall: drt@nrc.gov
===Neal K. Hunemuller, NRR===
(301) 415-1152 E-mall: nkh@nrc.gov


Neal K. Hunemuller, NRR
Attachment: List of Recently Issued Information Notices


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


Attachment: List of Recently Issued Information Notices                                              TACt        q4 2 6°
q4 2 6°
DOCUMENT NAME: G:INKHRBLWTPNLS.IN
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 wE" - Copy with enclosures "N" n No copy
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


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


NAME          NHunemullert              CBerlinger        *      AChaffee      Ok& ITMartin
C:PECB


DATE         11/L/96                   11/18/96                 11/L/96           '       11/   /96 OFFICIAL RECORD COPY
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
v
Line 453: Line 634:
IN 96-xx
IN 96-xx


November xx, 1996 for analyzing containment structures and supports: The modifications were not
===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
recognized as having the potential to place the structures outside of their
Line 459: Line 641:
design bases.
design bases.


Previous Similar Generic Communications
===Previous Similar Generic Communications===
 
NRC Information Notice 96-17, "Reactor Operations Inconsistent with
NRC Information Notice 96-17, "Reactor Operations Inconsistent with


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


9603150213).
9603150213).


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


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


contacts listed below or the appropriate Office of Nuci r Reactor IRegulation
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.
Project Manager.
ion No.
any
technical
Regulation


References
References


1.       NRC Inspection Report 50-338/96-01 & 50/                         -01, dated March 21, 1996, (Accession Number 9604090115)
1.
            2.       Cooper Nuclear Station Licensee Eve Report 50-298/95-018-01, dated
 
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)
May 31. 1996, (Accession Number 96 110378)
            3.       Quad Cities Nuclear Power Stati                   Licensee Event Report 50-254 &
3.
                    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-
Quad Cities Nuclear Power Stati
                    005-01, dated June 26, 19 , (Accession Number 9607010370)
 
                                                                Thomas T. Martin, Director
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
Division of Reactor Program Management


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


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


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


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


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


* See previous concurrence
* See previous concurrence


To ecelve a copy of                                                                                           N No copy
To ecelve a copy of


Isdocument, Indicate In the box: "C"- Copy without encosures "E"- Copy with enclosures "N"
Is
OFFICE      1PEV            l. 1C:SCSB                        C:PECB                D:DRPM


NAME        N nemuller %M CBerlinger *                        AChaffee              TMartin
document, Indicate In the box: "C" - Copy without encosures "E"
- Copy with enclosures "N"
N


DATE          1/f?/96                11/18/96                11/ /96                11/ /96
No copy
          /                                            Ukt lIAL KtLUKU L Y


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
A . '4 L


IN 96-xx
IN 96-xx


*.November                                                                                         xx. 1996 This information notice requires no written response. If you have any
* .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
questions about the information in this notice, please contact the technical
Line 529: Line 762:
References
References


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


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


May 31. 1996, (Accession Number 9606110378)
May 31. 1996, (Accession Number 9606110378)
            3.       Quad Cities Nuclear Power Station Licensee Event Report 50-254 &
3.
                    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


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
Division of Reactor Program Management


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


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


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


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


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


To receive a copy of this document, Indicate In tlh-  ")
IAChaffee
                                                        "  Copy without enclosures "En - Copy with enclosures "NW - No copy


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


NAME          NHunemullerm/' CBerlinger                    IAChaffee                MTartin
DATE


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


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