View source for Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure.

{{Adams
| number = ML031060266
| issue date = 09/22/1995
| title = Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure.
| author name = Crutchfield D
| author affiliation = NRC/NRR
| addressee name = 
| addressee affiliation = 
| docket = 05000003, 05000010, 05000029, 05000133, 05000155, 05000171, 05000206, 05000213, 05000219, 05000220, 05000237, 05000244, 05000245, 05000247, 05000249, 05000250, 05000251, 05000254, 05000255, 05000259, 05000260, 05000261, 05000263, 05000265, 05000266, 05000267, 05000269, 05000270, 05000271, 05000272, 05000275, 05000277, 05000278, 05000280, 05000281, 05000282, 05000285, 05000286, 05000287, 05000289, 05000293, 05000295, 05000296, 05000298, 05000301, 05000302, 05000304, 05000305, 05000306, 05000309, 05000311, 05000312, 05000313, 05000315, 05000316, 05000317, 05000318, 05000320, 05000321, 05000322, 05000323, 05000324, 05000325, 05000327, 05000328, 05000329, 05000330, 05000331, 05000333, 05000334, 05000335, 05000336, 05000338, 05000339, 05000341, 05000344, 05000346, 05000348, 05000352, 05000353, 05000354, 05000361, 05000362, 05000364, 05000366, 05000368, 05000369, 05000370, 05000373, 05000374, 05000382, 05000387, 05000388, 05000389, 05000390, 05000391, 05000395, 05000397, 05000400, 05000409, 05000410, 05000412, 05000413, 05000414, 05000416, 05000423, 05000424, 05000425, 05000437, 05000438, 05000439, 05000440, 05000441, 05000443, 05000444, 05000445, 05000446, 05000454, 05000455, 05000456, 05000457, 05000458, 05000461, 05000482, 05000483, 05000498, 05000499, 05000508, 05000528, 05000529, 05000530
| license number = 
| contact person = 
| case reference number = DG-1008, GI-023, GI-130, GI-153, GL-91-007, SECY-94-225
| document report number = IN-95-042, NUDOCS 9509200232
| document type = NRC Information Notice
| page count = 12
}}
{{#Wiki_filter: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)
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