Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure.ML031060266 |
Person / Time |
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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, Three Mile Island, 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 |
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Issue date: |
09/22/1995 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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DG-1008, GI-023, GI-130, GI-153, GL-91-007, SECY-94-225 IN-95-042, NUDOCS 9509200232 |
Download: ML031060266 (12) |
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Similar Documents at 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, Three Mile Island, 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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
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
in
(GI) 23, "Reactor Coolant Pump Seal Failure." This decision was documented
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 preliminaryleak
results of NRC studies suggested that reactor coolant pump (RCP) seal
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 the
Issue 23: Reactor Coolant Pump Seal Failure," April 1991, which contains
RCP
NRC model for RCP seal failure. The report identifies several modes of
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 q-yn
9S_0q qoq
9,70mt
- ._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 ( J7ar
'
K..Achment
IN 95-42 September 22, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-41 Degradation of Ventilation 09/22/95 All holders of OLs or CPs
System Charcoal Resulting for nuclear power reactors.
from Chemical Cleaning of
Steam Generators
95-40 Supplemental Information 09/20/95 All holders of OLs or CPs
to Generic Letter 95-03, for nuclear power reactors.
Circumferential Cracking
of Steam Generator Tubesm
95-39 Brachytherapy Incidents 09/19/95 All U.S. Nuclear Regulatory
Involving Treatment Commission Medical
Planning Errors Licensees.
95-38 Degradation of Boraflex 09/08/95 All holders of OLs or CPs
Neutron Absorber in for nuclear power reactors.
Spent Fuel Storage Racks
95-37 Inadequate Offsite Power 09/07/95 All holders of OLs or CPs
System Voltages during for nuclear power reactors.
Design-Basis Events
95-36 Potential Problems with 08/29/95 All holders of OLs or CPs
Post-Flre Emergency for nuclear power reactors.
Lighting
95-35 Degraded Ability of 08/28/95 All holders of OLs or CPs
Steam Generators to for pressurized water
Remove Decay Heat by reactors (PWRs).
Natural Circulation
95-34 Air Actuator and Supply 08/25/95 All holders of OLs or CPs
Air Regulator Problems in for nuclear power reactors.
Copes-Vulcan Pressurizer
Power-Operated Relief Valves
93-83, Potential Loss of Spent 08/24/95 All holders of OLs or CPs
Fuel Pool Cooling After a for nuclear power reactors.
Supp. 1 Loss-of-Coolant Accident
or a Loss of Offsite Power
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
1AEChaffee* field
NAME TKoshy* EFGoodwin* RJKiessel*
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 ADM:PUB* I SRXB:DSSA* I RES:DET* 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.RPM 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 Syed K. Shaukat, RES
(301) 415-2878 (301) 415-6592 Christopher Jackson, NRR
(301) 415-2947
111?lq5 I.Xkf //ct
Lead project manager: Linh N.Tran, NRR qfl9/q9//dh'6 '9 Z
(301) 415-1361
- See previous concurrence page
DOCUMENT NAME : G:\IN\INGE23.TK
To recohre a CODY af this document. indicate In the box: 'C' = Copy without enclosures E' - Copy with enclosures 'N- No copy
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 I :DRPM I P l C:PECB:DRPM
CECB:DRPM D:DRPM
NAME TKoshy jt, EFGoodwin* RJKfessel vAEChaffee
/95 DMCrutchfield
09/ /95 DATE 09/19/95 09/15/95 og09L/g5 " I 109/
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 thWdocument, Indicate inthe 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 PECB:DRPM E E l 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
- see previous concurrence page
te
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
DISTRIBUTION
Central File
PDR
SRXB R/F (Wits 9200243)
FMiraglia
RZimmerman
BGrimes
AThadani
GHolahan
LTran
LShao
JShapaker
RJones
OGC
CLiang
CLiang R/F
SShaukat
PMagnanelli (Wits 9200243)
KBohrer
NRR Mailroom (Wits 9200243)
DCrutchfield
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
... further results |
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