Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001
September 22, 1995
NRC INFORMATION NOTICE 95-42: COMMISSION DECISION ON THE RESOLUTION OF
GENERIC ISSUE 23, "REACTOR COOLANT PUMP SEAL
FAILUREO
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 notify addressees of the Commission's decision on Generic Issue
(GI) 23, "Reactor Coolant Pump Seal Failure." This decision was documented in
a staff requirements memorandum (SRM) from John C. Hoyle to James M. Taylor, dated March 31, 1995 (Accession Number 9504140300), written in response to
SECY-94-225, "Issuance of Proposed Rulemaking Package on GI-23, 'Reactor
Coolant Pump Seal Failure'." No specific action or written response is
required as a result of this information notice.
Background
On April 19, 1991, the NRC published a Federal Register notice (56 FR 16130)
requesting comments on the then-current understandings, findings, and
potential recommendations regarding GI-23, together with a draft Regulatory
Guide, DG-1008, "Reactor Coolant Pump Seals." On May 2, 1991, NRC issued
Generic Letter (GL) 91-07, wGI-23, 'Reactor Coolant Pump Seal Failures' and
Its Possible Effect on Station Blackout," which stated that preliminary
results of NRC studies suggested that reactor coolant pump (RCP) seal leak
rates could be substantially higher than those assumed in the coping analyses
for implementation of the station blackout (SBO) issue. The generic letter
reminded licensees that higher seal leak rates could affect licensee analyses
and actions addressing conformance to the SBO rule.
Staff studies and analyses concerning RCP seal leakage are documented in
Appendices A and B to NUREG/CR-5167, 'Cost/Benefit Analysis for Generic
Issue 23:
Reactor Coolant Pump Seal Failure," April 1991, which contains the
NRC model for RCP seal failure. The report identifies several modes of RCP
seal leakage which may be in excess of that assumed in licensee coping
analyses for implementing the requirements of 10 CFR 50.63, the SBO rule.
GI-23 is related to a number of other generic issues: GI-65, "Component
Cooling Water System Failure"; GI-130, "Essential Service Water (ESW) System
Failure at Multiplant Sites"; GI-153, "Loss of Essential Service Water in
LWRs"; GI-106, OPiping and the Use of Highly Combustible Gases in Vital
Areas'; and Three Mile Island (TMI) Actions II.K.2.16 and II.K.3.25.
In
addition, the Individual Plant Evaluation (IPE) Program, as described in
9509200232
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._J IN 95-42 September 22, 1995 GL 88-20, requests evaluation of plant vulnerabilities with respect to certain
generic issues, including GI-23.
Discussion
The Commission considered the proposed rulemaking as a method to resolve
GI-23. In SECY-94-225, dated August 26, 1994, a draft rule was proposed for
public comment that would resolve GI-23.
On March 31, 1995, the Commission voted against the publication of the
proposed rule on the resolution of GI-23, Reactor Coolant Pump Seal Failure."
The Commission concluded that the proposed rule did not provide sufficient
gain in safety to Justify its issuance. The Commission was also concerned
that inaccuracies in the NRC seal leakage evaluation model may exist.
Further, the wide range of plant-specific considerations with regard to
pressurized-water reactor (PWR) RCP seals would result in the spending of
excessive resources by some licensees without commensurate safety benefits;
also some licensees are addressing the issue by using the IPE program and
accident management strategies. Therefore, the NRC will not proceed with the
rulemaking effort described in SECY-94-225.
The staff is currently exploring
options to determine what, if any, further action will be taken regarding the
final disposition of GI-23.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
rector
Division of
acto
rogram Management
Office of Nuclear Reactor Regulation
Technical contacts: Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6592
Christopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
(301) 415-1361 AfK4
'
( J7a r
K..Achment
September 22, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
95-41
95-40
95-39
95-38
95-37
95-36
95-35
95-34
Degradation of Ventilation
System Charcoal Resulting
from Chemical Cleaning of
Steam Generators
Supplemental Information
Circumferential Cracking
of Steam Generator Tubesm
Brachytherapy Incidents
Involving Treatment
Planning Errors
Degradation of Boraflex
Neutron Absorber in
Spent Fuel Storage Racks
Inadequate Offsite Power
System Voltages during
Design-Basis Events
Potential Problems with
Post-Flre Emergency
Lighting
Degraded Ability of
Remove Decay Heat by
Natural Circulation
Air Actuator and Supply
Air Regulator Problems in
Copes-Vulcan Pressurizer
Power-Operated Relief Valves
Potential Loss of Spent
Fuel Pool Cooling After a
Loss-of-Coolant Accident
09/22/95
09/20/95
09/19/95
09/08/95
09/07/95
08/29/95
08/28/95
08/25/95
08/24/95
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for nuclear power reactors.
All U.S. Nuclear Regulatory
Commission Medical
Licensees.
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 (PWRs).
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for nuclear power reactors.
93-83, Supp. 1 OL - Operating License
CP - Construction Permit
K.2 IN 95-42 September 22, 1995 GL 88-20, requests evaluation of plant vulnerabilities with respect to certain
generic issues, including GI-23.
Discussion
The Commission considered the proposed rulemaking as a method to resolve
GI-23.
In SECY-94-225, dated August 26, 1994, a draft rule was proposed for
public comment that would resolve GI-23.
On March 31, 1995, the Commission voted against the publication of the
proposed rule on the resolution of GI-23, "Reactor Coolant Pump Seal Failure."
The Commission concluded that the proposed rule did not provide sufficient
gain in safety to justify its issuance.
The Commission was also concerned
that Inaccuracies in the NRC seal leakage evaluation model may exist.
Further, the wide range of plant-specific considerations with regard to
pressurized-water reactor (PWR) RCP seals would result in the spending of
excessive resources by some licensees without commensurate safety benefits;
also some licensees are addressing the issue by using the IPE program and
accident management strategies.
Therefore, the NRC will not proceed with the
rulemaking effort described in SECY-94-225.
The staff is currently exploring
options to determine what, if any, further action will be taken regarding the
final disposition of GI-23.
This information notice requires no specific action or written response. If
you have any. questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
orig /s/'d by DMCrutchfield
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6592
Christopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
(301) 415-1361
- See previous concurrence page DOCUMENT NAME: 95-42.IN
To receive a copy of this document, Indicate In the box: 'C' - Copy without enclosures 'E' - Copy with enclosures 'N' - No copy
OFFICE
SRXB:DSSA* I
ADMTPUB* I
SRXB:DSSA* I
RES:DET*
lO
D:DSSA*
A
NAME
EWEISS
TECH EDITOR
RJONES
LSHAO
GHOLAHAN
DATE
9/05/95
8/25/95
9/06/95
09/08/95
09/19/95 OFFICE
PECB:DRPM
I
PECB:DRPM I
P CB:DRPM
lI
C:PECB:DRPM
D:I
NAME
TKoshy*
EFGoodwin*
RJKiessel*
1AEChaffee*
field
DATE
09/19/95
09/15/95
09/19/95
09/19/95
09/2
/95
OFFICIAL RECORD COPY
IN 95-xx
September xx, 1995 requests evaluation of plant vulnerabilities with respect to certain generic
issues, including GI-23.
Discussion
The Commission considered the proposed rulemaking as a method to resolve GI-
23. In SECY-94-225, dated August 26, 1994, a draft rule was proposed for
public comment that would resolve GI-23.
On March 31, 1995, the Commission voted against the publication of the
proposed rule on the resolution of GI-23, Reactor Coolant Pump Seal Failure".
The Commission concluded that the proposed rule did not provide sufficient
gain in safety to justify its issuance. The Commission was also concerned
that inaccuracies in the NRC seal leakage evaluation model may exist.
Further, the wide range of plant-specific considerations with regard to
pressurized-water reactor (PWR) RCP seals would result in the spending of
excessive resources by some licensees without commensurate safety benefits;
also some licensees are addressing the issue by using the IPE program and
accident management strategies. Therefore, the NRC will not proceed with the
rulemaking effort described in SECY-94-225. The staff is currently exploring
options to determine what, if any, further action will be taken regarding the
final disposition of GI-23.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6592 Christopher Jackson, NRR
,
(301) 415-2947
5,4 M,4 S
i/'25~.
Lead project manager: Linh N. Tran, NRR
(301) 415-1361
- See previous concurrence page DOCUMENT NAME: G:\\IN\\INGE23.TK
To receive a copy of this document, hndicate In the box: 'C' - Copy without enclosures 'E' = Copy with enclosures N' - No copy
OFFICE
SRXB:DSSA* I
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I
D:DSSA*
I
NAME
EWEISS
= TECH EDITOR = RJONES
= LSHAO
GHOLAHAN
DATE
9/05/95
8/25/95
9/06/95
09/08/95
09/19/95 OFFICE
PECB:DRPM
I
PECB:DRPM I
PECBDRPM I
C:PUM.
D:DRPM
I
NAME
TKoshy*
EFGoodwin*
RJKiessel*
AEffffTee
DMCrutchfield
DATE
09/19/95
09/15/95
09/19195
09 /1/95
09/ /95
OFFICIAL RECORD COPY
IN 95-xx
September xx, 1995
requests evaluation of plant vulnerabilities with respect to certain generic
issues, Including GI-23.
Discussion
The Commission considered the proposed rulemaking as a method to resolve GI-
23. In SECY-94-225, dated August 26, 1994, a draft rule was proposed for
public comment that would resolve GI-23.
On March 31, 1995, the Commission voted against the publication of the
proposed rule on the resolution of GI-23, *Reactor Coolant Pump Seal Failure".
The Commission concluded that the proposed rule did not provide sufficient
gain in safety to justify its issuance. The Commission was also concerned
that inaccuracies in the NRC seal leakage evaluation model may exist.
Further, the wide range of plant-specific considerations with regard to
pressurized-water reactor (PWR) RCP seals would result in the spending of
excessive resources by some licensees without commensurate safety benefits;
also some licensees are addressing the issue by using the IPE program and
accident management strategies. Therefore, the NRC will not proceed with the
rulemaking effort described in SECY-94-225. The staff Is currently exploring
options to determine what, if any, further action will be taken regarding the
final disposition of GI-23.
This information notice requires no specific action or written. response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate NRC project
manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
Chu-yu Hang, NRR
(301) 415-2878
Christopher Jackson, NRR
(301) 415-2947
Syed K. Shaukat, RES
(301) 415-6592
111?lq5 I.Xkf
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'E' - Copy with enclosures 'N-
No copy
- See
DOCUMENT NAME
project manager: Linh N. Tran, NRR
(301) 415-1361 previous concurrence page
- G:\\IN\\INGE23.TK
To recohre a CODY af this document. indicate In the box: 'C' = Copy without enclosures '
OFFICE
SRXB:DSSA*
ADM:PUB*
SRXB:DSSA*
RES:DET*
D:DSSA*
NAME
EEISS
TECH EDITOR
RJONES
LSHAO
GHOLAHAN
[DATE
9/05/95
8/25/95
~
~9/06/95
09/08/95
09/19/95 -
OFFICE
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- DRPM I P
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CECB:DRPM
C:PECB:DRPM
D:DRPM
NAME
TKoshy
jt, EFGoodwin*
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DMCrutchfield
DATE
09/19/95
09/15/95 og09L/g5 " I 109/
/95
09/ /95
IN 95-xx
September xx, 1995 requests evaluation of plant vulnerabilities with respect to certain generic
issues, including GI-23.
Discussion
The Commission considered the proposed rulemaking as a method to resolve GI-
23. In SECY-94-225, dated August 26,
1994, a draft rule was proposed for
public comment that would resolve GI-23.
On March 31, 1995, the Commission
publication of the
proposed rule on the resolution oV GI-23, Reactor Coolant Pump Seal Failure".
The Commission concluded that the proposed rule did not provide sufficient
gain in safety to justify its issuance. The Commission was also concerned
that inaccuracies in the NRC seal leakage evaluation model may exist.
Further, the wide range of plant-specific considerations with regard to
pressurized-water reactor (PWR) RCP seals would result in the spending of
excessive resources by some licensees without commensurate safety benefits;
also some licensees are addressing the issue by using the IPE program and
accident management strategies. Therefore, the NRC will not proceed with the
rulemaking effort described in SECY-94-225. The staff is currently exploring
options to determine what, if any, further action will be taken regarding the
final disposition of GI-23. This information notice requires no specific
action or written response. If you have any questions about the information
in this notice, please contact one of the technical contacts listed below or
the appropriate NRC project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6592
Christopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
(301) 415-1361
IN 95-xx
September xx, 1995 requests evaluation of plant vulnerabilities with respect to certain generic
issues, including GI-23.
Discussion
The Commission considered the proposed rulemaking as a method to resolve GI-
23.
In SECY-94-225, dated August 26, 1994, a draft rule was proposed for
public comment that would resolve GI-23.
On March 31, 1995, the Commission did not approve the publication of the
proposed rule on the resolution of GI-23, 'Reactor Coolant Pump Seal Failure".
The Commission concluded that the proposed rule did not provide sufficient
gain in safety to justify its issuance. The Commission was also concerned
that inaccuracies in the NRC seal leakage evaluation model may exist.
Further, the wide range of plant-specific considerations with regard to
pressurized-water reactor (PWR) RCP seals would result in the spending of
excessive resources by some licensees without commensurate safety benefits;
also some licensees are addressing the issue by using the IPE program and
accident management strategies. Therefore, the NRC will not proceed with the
rulemaking effort described in SECY-94-225. The staff is currently exploring
options to determine what, if any, further action will be taken regarding the
final disposition of GI-23. This information notice requires no specific
action or written response. If you have any questions about the information
in this notice, please contact one of the technical contacts listed below or
the appropriate NRC project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6592
Christopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
(301) 415-1361
- See previous concurrence page
/
DOCUMENT NAME: G:\\IN\\INGE23.TK
To receive a copy of thW document, Indicate in the box:
C - Copy without enclosures
E
- Copy with enclosures 'N' - No cop
OFFICE
ISRXB:DSSA*
l ADM:PUB*
SRXB:DSSA*
l
RES:DET*
D:DSW
NAME
IEWEISS
TECH EDITOR
RJONES
LSHAO
GHOLAHAN
DATE
19/05/95
8/25/95
9/06/95
09/08/95
09/13/95 OFFICE
E
PECB:DRPM
l
E
PECB:DRPM I P C:PECB:DRPMl D:DRPM
I
NAME
TKoshy
EFGoodwin
RJKiessel
AEChaffee
DMCrutchfield
DATE
09/ig195
09//5t95
09/
/95
09/ /95
OFFICIAL RECORD COPY
GI-130, "Essential Service Water (ESW) System Failure at Multiplant Sites";
GI-153, 'Loss of Essential Service Water in LWRs"; GI-106, "Piping and the Use
of Highly Combustible Gases in Vital Areas"; and Three Mile Island (TMI)
Actions II.K.2.16 and II.K.3.25. In addition, the Individual Plant Evaluation
(IPE) Program, as described in GL 88-20, requests the evaluation of plant
vulnerabilities with respect to certain generic issues, including
GI-23.
Discussion
The staff proposed rulemaking to resolve GI-23. In SECY-94-225, dated August
26, 1994, the staff requested approval from the Commission to issue a draft
rule for public comment that would resolve GI-23. In response to SECY-94-225, the Commission transmitted an SRM on March 31, 1995.
In this SRM, the Commission declined to approve publication of a proposed rule
for comment on the resolution of GI-23, "Reactor Coolant Pump Seal Failure."
The Commission believes that the proposed rule provides an insufficient basis
for gains in safety and that concerns with the NRC seal leakage evaluation
model may exist. Also, the wide range of plant-specific considerations with
regard to pressurized-water reactor (PWR) RCP seals would result in the
spending of excessive resources by some licensees without commensurate safety
benefits. The Commission also stated in the SRM that some licensees appear to
be addressing the issue by using the IPE program and accident management
strategies. The staff will therefore not proceed with the rulemaking effort
described in SECY-94-225. The staff is currently exploring options to
determine what, if any, further action will be taken regarding the final
disposition of GI-23. This information notice requires no specific action or
written response. If you have any questions about the information in this
notice, please contact one of the technical contacts listed below or the
appropriate NRC project manager.
Alfred E. Chaffee, Chief
Events Assessment and Generic
Communications Branch
Office of Nuclear Reactor Regulation
Technical contacts: Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6592
Christopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
(301) 415-1361 EDITED BY: B. Calure
DATED: 8/25/95 Distribution: see next page
te
- see previous concurrence page
SRXB:DSSA*
SRXB:DSSA*
RES:DET*
EWEISS
RJONES
LSHAO
9/05/95
9/06/95
9/08/95
/l595 G:\\IN-GE23.TYP
2 GI-130, "Essential Service Water (ESW) System Failure at Multiplant Sites";
GI-153, 'Loss of Essential Service Water in LWRs"; GI-106, "Piping and the Use
of Highly Combustible Gases in Vital Areas"; and Three Mile Island (T141)
Actions II.K.2.16 and II.K.3.25. In addition, the Individual Plant Evaluation
(IPE) Program, as described in GL 88-20, requests the evaluation of plant
vulnerabilities with respect to certain generic issues, including
GI-23.
Discussion
The staff proposed rul making to resolve GI-23. In SECY-9 -225, dated August
26, 1994, the staff re uested approval from the Commissi
to issue a draft
rule for public comment that would resolve GI-23. In r sponse to SECY-94-225, the Commission transmit ed an SRM on March 31, 1995.
In this SRM, the Commissi n declined to approve pub ication of a proposed rule
for comment on the resolut on of GI-23, "Reactor $'oolant Pump Seal Failure."
The Commission believes tht the proposed rule pfovides an insufficient basis
for gains in safety and tha concerns with the ARC seal leakage evaluation
model may exist. Also, the ide range of pla -specific considerations with
regard to pressurized-water r actor (PWR) RCF seals would result in the
spending of excessive resource by some li ensees without commensurate safety
benefits. The Commission also tated in he SRM that some licensees appear to
be addressing the issue by using the IPE program and accident management
strategies. The staff will there ore p6t proceed with the rYlmaking effort
described in SECY-94-225.
,
the staff is
currently exploring options fr the inal disposition of GI-23.
ihe- pprp
at
neThis
information
notice requires no specific act o o0 written response. If you have any
questions about the information
th
notice, please contact one of the
technical contacts listed below r the
ppropriate NRC project manager.
st
A fred E. Chaffee, Chief
kee 4>
'
/
Ev nts Assessment and Generic
mmunications Branch
Off e of Nuclear Reactor Regulation
Technical contacts: Ch -yu Liang, NRR
Syed K. Shaukat, RES
1) 415-2878
\\
(301) 415-6592 hristopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
/
(301) 415-1361 EDITED BY: B. C ure
DATED: 8/25/95 Distribution: tsee next page
- see previo
Co
urrence page
SRXB:DSSA*
SRXB:DSSA*
REt -
D:DSSA
EWEISS
RJONES
LSHAO
GHOLAHAN
9/05/95
9/06/95
9/ 8/95
9/ /95 G:\\I GE23.TYP
GI-130, "Essential Service Water (ESW) System Failure at Multiplant Sites";
GI-153, "Loss of Essential Service Water in LWRs"; GI-106, "Piping and the Use
of Highly Combustible Gases in Vital Areas"; and Three Mile Island (TMI)
Actions II.K.2.16 and II.K.3.25. In addition, the Individual Plant Evaluation
(IPE) Program, as described in GL 88-20, requests the evaluation of plant
vulnerabilities with respect to certain generic issues, including
GI-23.
Discussion
The staff proposed rulemaking to resolve GI-23. In SECY-94-225, dated August
26, 1994, the staff requested approval from the Commission to issue a draft
rule for public comment that would resolve GI-23. In response to SECY-94-225, the Commission transmitted an SRM on March 31, 1995.
In this SRM, the Commission declined to approve publication of a proposed rule
for comment on the resolution of GI-23, "Reactor Coolant Pump Seal Failure."
The Commission believes that the proposed rule provides an insufficient basis
for gains in safety and that concerns with the NRC seal leakage evaluation
model may exist. Also, the wide range of plant-specific considerations with
regard to pressurized-water reactor (PWR) RCP seals would result in the
spending of excessive resources by some licensees without commensurate safety
benefits.
The Commission also stated in the SRM that some licensees appear to
be addressing the issue by using the IPE program and accident management
strategies. The staff will therefore not proceed with the rulemaking effort
described in SECY-94-225.
Considering the past NRC effort, the staff is
currently exploring options for the final disposition of GI-23. The
appropriate NRC action on the issue is being investigated. This information
notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the
technical contacts listed below or the appropriate NRC project manager.
Alfred E. Chaffee, Chief
Events Assessment and Generic
Communications Branch
Office of Nuclear Reactor Regulation
Technical contacts: Chu-yu Liang, NRR
Syed K. Shaukat, RES
(301) 415-2878
(301) 415-6593
Christopher Jackson, NRR
(301) 415-2947 Lead project manager:
Linh N. Tran, NRR
(301) 415-1361 EDITED BY: B. Calure
DATED: 8/25/95 Distribution:
see
xt page
S
a
'DSSA
RES:DET
D:DSSA
Eb!EIS
RJ0NES
LSHAO
GHOLAHAN
9/s /95
9/4/95
9/ /95
9/ /95 G:\\IN-GE23.TYP
NRC INFORMATION NOTICE 95-XX
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