Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures: Difference between revisions

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{{#Wiki_filter:9. '5 UN.TED STATES NUCLEAR REGULATORY
{{#Wiki_filter:9. '5 UN.TED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 July 9, 1997 NRC INFORMATION


NOTICE 97-48: INADEQUATE
WASHINGTON, D.C. 20555-0001 July 9, 1997 NRC INFORMATION NOTICE 97-48: INADEQUATE OR INAPPROPRIATE INTERIM FIRE


OR INAPPROPRIATE
PROTECTION COMPENSATORY MEASURES


INTERIM FIRE PROTECTION
All holders of operating licenses or construction permits for nuclear power reactors.
 
COMPENSATORY
 
MEASURES All holders of operating
 
licenses or construction
 
permits for nuclear power reactors.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) Is Issuing this Information notice to alert
 
Commission (NRC) Is Issuing this Information
 
notice to alert addressees
 
to potential
 
problems associated
 
with the Implementation
 
of interim compensatory


measures for degraded or Inoperable
addressees to potential problems associated with the Implementation of interim compensatory


plant fire protection
measures for degraded or Inoperable plant fire protection features or degraded or Inoperable


features or degraded or Inoperable
conditions associated with post-fire safe-shutdown capability. It is expected that recipients


conditions
will review the informatioit for applicability to their facilities and consider actions, as


associated
appropriate, to avoid similar problems. However, suggestions contained In this information


with post-fire
notice are not NRC requiremnents; therefore, no specific action or wdtten response is


safe-shutdown
required.


capability.
==Description of Circumstances==
The NRC foresaw cases in which fire protection features would be inoperable and allowed


===It is expected that recipients===
licensees, through plant technical specifications (TS) or approved fire protection plans
will review the informatioit


for applicability
controlled by license conditions, to implement alternative actions to compensate for the


to their facilities
inoperable condition or component until permanent corrective actions are implemented. In


and consider actions, as appropriate, to avoid similar problems.
general, the combination of appropriate compensatory measures and the defense-in-depth


However, suggestions
fire protection features provides an adequate level of fire protection until the licensees


contained
complete the corrective actions, For common types of deficiencies (e.g., an Inoperable fire


===In this information===
suppression system), the specific compensatory measures are generally noted in either the
notice are not NRC requiremnents;
therefore, no specific action or wdtten response is required.Description


of Circumstances
TS or in the NRC-approved fire protection program. For unique plant-specific situations (e.g.,
        Inadequate cable separation), the appropriate compensatory measures are determined by the


The NRC foresaw cases in which fire protection
licensee on a case-by-case basis. (This is discussed further later in the information notice.)
        NRC reviews of licensees' corrective actions to address degraded or Inoperable conditions


features would be inoperable
associated with a plant's abilities to achieve and maintain post-fire safe shutdown have noted


and allowed licensees, through plant technical
some weaknesses in the interim compensatory measures. For example, some licensees


specifications (TS) or approved fire protection
have relied exclusivoly on the 1-hour roving fire watch as an interim compensatory measure


plans controlled
for deficiencies that affect their abilities to achieve and maintain post-fire safe shutdown and


by license conditions, to implement
have not considered or Implemented other appropriate interim compensatory measures, such


alternative
as briefing operators on degraded post-fire, safe-shutdown-system conditions; temporary


actions to compensate
repair procedures; temporary fire barriers; or detection or suppression systems. In addition, A


for the inoperable
____              ?DE q=TE 91-011                                      911o(
      (9707020308          dQV


condition
11111111111111111011


or component
IN07.48 July 9, 197o MC kIspectlons of fire protection programs have found weaknesses In kliensees' fle watch


until permanent
t'Org programs and In the conduct of fire watch dutiee. Specific examples documented In


corrective
NRC Inspection reports Include the following:
    ODutig a November 1996 Inspection at Waterford Generating Station (Inspection Report


actions are implemented.
W0-382/95-020, Accession No. 9603260040), NRC Inspectors found that the licensee's


In general, the combination
procedures redefined the
 
of appropriate
 
compensatory
 
measures and the defense-in-depth
 
fire protection
 
features provides an adequate level of fire protection
 
until the licensees complete the corrective
 
actions, For common types of deficiencies (e.g., an Inoperable
 
fire suppression
 
system), the specific compensatory
 
measures are generally
 
noted in either the TS or in the NRC-approved
 
fire protection
 
program. For unique plant-specific
 
situations (e.g., Inadequate
 
cable separation), the appropriate
 
compensatory
 
measures are determined
 
by the licensee on a case-by-case
 
basis. (This is discussed
 
further later in the information
 
notice.)NRC reviews of licensees'
corrective
 
actions to address degraded or Inoperable
 
conditions
 
associated
 
with a plant's abilities
 
to achieve and maintain post-fire
 
safe shutdown have noted some weaknesses
 
in the interim compensatory
 
measures.
 
For example, some licensees have relied exclusivoly
 
on the 1-hour roving fire watch as an interim compensatory
 
measure for deficiencies
 
that affect their abilities
 
to achieve and maintain post-fire
 
safe shutdown and have not considered
 
or Implemented
 
other appropriate
 
interim compensatory
 
measures, such as briefing operators
 
on degraded post-fire, safe-shutdown-system
 
conditions;
temporary repair procedures;
temporary
 
fire barriers;
or detection
 
or suppression
 
systems. In addition,____ ?DE q=TE 91-011 911o(A (9707020308 dQV 11111111111111111011 IN 07.48 July 9, 197o MC kIspectlons
 
of fire protection
 
programs have found weaknesses
 
In kliensees'
fle watch t'Org programs and In the conduct of fire watch dutiee. Specific examples documented
 
In NRC Inspection
 
reports Include the following:
ODutig a November 1996 Inspection
 
at Waterford
 
Generating
 
Station (Inspection
 
Report W0-382/95-020, Accession
 
No. 9603260040), NRC Inspectors
 
found that the licensee's
 
procedures
 
redefined
 
the


==Intent==
==Intent==
of a continuous
of a continuous fire watch. The licensees' procedure


fire watch. The licensees'
required a 15-minute roving fire watch, with a margin of 5 minutes, In lieu of a continuous
procedure required a 15-minute


roving fire watch, with a margin of 5 minutes, In lieu of a continuous
fir watch. In addition, required fire watches were not performed in areas In which fire


fir watch. In addition, required fire watches were not performed
detection equipment was out of service and In areas In which fire barriers were degraded.


in areas In which fire detection
This Issue Is currently under review by the NRC for disposition.


equipment
*  During an April 1996 Inspection at Palisades Nuclear Plant (Inspection Report 60-255/
    96-004, Accession No. 9805290105). the NRC Inspector noted that the licensee relied on


was out of service and In areas In which fire barriers were degraded.This Issue Is currently
fire watches as compensatory measures for a number of post-fire, safe-shutdown-design


under review by the NRC for disposition.
deficiencies Identified by the licensee pursuant to Appendix R to Part 50 of T ", 10 of the


* During an April 1996 Inspection
Code f Federal Regulations (10 CFR Part 50) while long-term corrective actlukns were


at Palisades
being evaluated. The licensee did not alert the operators to these deficient conditions nor


Nuclear Plant (Inspection
did It provide interim shutdown strategies to operators on how to ouccossfully deal with


Report 60-255/96-004, Accession
potential fire damage to required safe-shutdown components. The potential conse- quences could have been extensive since placing and maintaining the plant in post-fire


No. 9805290105).
hot standby could only have bean achieved by significant operator actions, trouble- shooting, and repair activities to compensate for the post-fire, safe-shutdown-design


the NRC Inspector
deficiencies. The sole use of a fire watch for a safe shutdown function which Is not


noted that the licensee relied on fire watches as compensatory
adequately protected against fire damage is an Inappropriate application of a


measures for a number of post-fire, safe-shutdown-design
compensatory measure. This problem resulted in a Severity Level III Violation.


deficiencies
* On October 17, 1998, Arkansas Nuclear One had an event involving a fire in a reactor


Identified
coolant pump (RCP) and inadequacies associated with the RCP oil collection system.


by the licensee pursuant to Appendix R to Part 50 of T ", 10 of the Code f Federal Regulations
The licensee's initial compensatory measures placed the lift olK pumps in the "stop"
    condition. This action enhanced the fire protection annunciator procedures by giving


(10 CFR Part 50) while long-term
additional guidance to the operators when responding to the RCP smoke detector alarm.


corrective
However, the licensee did not propose Interim plant operational measures which would


actlukns were being evaluated.
help operators identify and mitigate the consequence of potential oil leakage from the


The licensee did not alert the operators
RCP oil system sites not protected by the RCP oil collection system. This problem


to these deficient
resulted in a Severity Level III Violation.
 
conditions
 
nor did It provide interim shutdown strategies
 
to operators
 
on how to ouccossfully
 
deal with potential
 
fire damage to required safe-shutdown
 
components.
 
The potential
 
conse-quences could have been extensive
 
since placing and maintaining
 
the plant in post-fire hot standby could only have bean achieved by significant
 
operator actions, trouble-shooting, and repair activities
 
to compensate
 
for the post-fire, safe-shutdown-design
 
deficiencies.
 
The sole use of a fire watch for a safe shutdown function which Is not adequately
 
protected
 
against fire damage is an Inappropriate
 
application
 
of a compensatory
 
measure. This problem resulted in a Severity Level III Violation.
 
* On October 17, 1998, Arkansas Nuclear One had an event involving
 
a fire in a reactor coolant pump (RCP) and inadequacies
 
associated
 
with the RCP oil collection
 
system.The licensee's
 
initial compensatory
 
measures placed the lift olK pumps in the "stop" condition.
 
This action enhanced the fire protection
 
annunciator
 
procedures
 
by giving additional
 
guidance to the operators
 
when responding
 
to the RCP smoke detector alarm.However, the licensee did not propose Interim plant operational
 
measures which would help operators
 
identify and mitigate the consequence
 
of potential
 
oil leakage from the RCP oil system sites not protected
 
by the RCP oil collection
 
system. This problem resulted in a Severity Level III Violation.


Discussion]
Discussion]
In accordance
In accordance with 10 CFR 50.48, "Fire protection," each operating nuclear power plant must


with 10 CFR 50.48, "Fire protection," each operating
have a fire protection plan that satisfies Criterion 3 of Appendix A to 10 CFR Part 50.


nuclear power plant must have a fire protection
Licensees of plants licensed to operate before January 1, 1979, are required to satisfy the


plan that satisfies
provisions of Appendix R to 10 CFR Part 50, Section Ill.G, "Fire protection of safe shutdown


Criterion
I'  .


3 of Appendix A to 10 CFR Part 50.Licensees
IN 97-48 July 9, 1997 capability;" Section Ill.J, "Emergency lighting;" and Section 111.0, "Oil collection system for


of plants licensed to operate before January 1, 1979, are required to satisfy the provisions
reactor coolant pump;" and the provisions of Appendix A to the Branch Technical Position of


of Appendix R to 10 CFR Part 50, Section Ill.G, "Fire protection
the Auxiliary Power Conversion Systems Branch (BTP APCSB) 9.5-1, "Guidelines for Fire


of safe shutdown I' .
Protection for Nuclear Power Plants Docketed Prior to July 1, 1978." Licensees of plants


IN 97-48 July 9, 1997 capability;" Section Ill.J, "Emergency
licensed to operate after January 1, 1979, are required to satisfy the fire protection provisions


lighting;" and Section 111.0, "Oil collection
of their operating licenses. Generally, these plants have fire protection programs that satisfy


system for reactor coolant pump;" and the provisions
the provisions of NUREG-0800, "Standard Review Plan (SRP)," Section 9.5.1; "Fire


of Appendix A to the Branch Technical
Protection Program," July 1981.


Position of the Auxiliary
Appendix A to BTP APCSB 9.5-1 specifies that licensees should establish administrative


Power Conversion
controls for normal and abnormal conditions or such other anticipated operations as


Systems Branch (BTP APCSB) 9.5-1, "Guidelines
modifications (e.g., breaking fire stops/penetration seals, Impairment of fire dete,'tion and


for Fire Protection
suppression systems) and refueling activities. The controls should be reviewed by


for Nuclear Power Plants Docketed Prior to July 1, 1978." Licensees
appropriate levels of licensee management, and appropriate special actions and procedures, such as fire watches or temporary fire barriers, should be implemented to ensure adequate


of plants licensed to operate after January 1, 1979, are required to satisfy the fire protection
fire protection and reactor safety.


provisions
On November 7, 1991, the NRC issued Generic Letter 91-18, "Information to Licensees


of their operating
Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and


licenses.
Nonconforming Conditions and on Operability" (Accession No. 9111040293). This generic


Generally, these plants have fire protection
letter contained two sections, "Resolution of Degraded and Nonconforming Conditions" and


programs that satisfy the provisions
"Operable/Operability: Ensuring the Functional Capability of a System or Component," to be


of NUREG-0800, "Standard
included in Part 9900, "Technical Guidance," of the NRC Inspection Manual. These additions


Review Plan (SRP)," Section 9.5.1; "Fire Protection
are based upon previously issued guidance.


Program," July 1981.Appendix A to BTP APCSB 9.5-1 specifies
With respect to fire protection and post-fire, safe-shutdown capability, the licensee may


that licensees
discover a previously unanalyzed condition. Under these conditions, Part 9900, "Technical


should establish
Guidance: Resolution of Degraded and Nonconforming Conditions," Section 4.4, "Discovery


administrative
of an Existing But Previously Unanalyzed Condition or Accident," notes that the licensee, upon discovering an existing but previously unanalyzed condition that significantly


controls for normal and abnormal conditions
compromises plant safety, shall report that condition in accordance with 10 CFR 50.72 and


or such other anticipated
shall place the plant in a safe condition. Once a degraded or nonconforming condition of


operations
specific structures, systems, or components (SSCs) is Identified, an operability determination


as modifications (e.g., breaking fire stops/penetration
should be made as soon as possible, consistent with the safety Importance of the SSC


seals, Impairment
affected. For SSCs that are outside plant TS, engineering judgment must be used to


of fire dete,'tion
determine safety significance.


and suppression
Part 9900, "Technical Guidance: Resolution of Degraded and Nonconforming Conditions,"
Section 4.8, "Reasonable Assurance of Safety," states that for SSCs which are not expressly


systems) and refueling
subject to TS and which are determined to be Inoperable, the licensee should assess the


activities.
reasonable assurance of safety. Ifthe assessment assures safety, then the facility may


The controls should be reviewed by appropriate
continue to operate while prompt corrective action is taken. As stated in Part 9900, the


levels of licensee management, and appropriate
following items are to be considered for such assessments: the availability of redundant or


special actions and procedures, such as fire watches or temporary
backup equipment, compensatory measures (including limited administrative controls), and


fire barriers, should be implemented
the conservatism and margins.


to ensure adequate fire protection
U


and reactor safety.On November 7, 1991, the NRC issued Generic Letter 91-18, "Information
IN 97-48 July 9, 1997 This Information notice requires no specific action or written response. Ifyou have any


to Licensees Regarding
questions about the Information In this notice, please contact one of the technical contacts


Two NRC Inspection
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


Manual Sections on Resolution
"Mi ee M. solosson, Acting Director


of Degraded and Nonconforming
Division of Reactor Program Management


Conditions
Office of Nuclear Reactor Regulation


and on Operability" (Accession
Technical contacts:  Darrell Schrum, Rill


No. 9111040293).
(630) 828-9741 E-mail: dls3@nrc.gov


This generic letter contained
Rogello Mendez, Rill


two sections, "Resolution
(630) 829-9745 E-mail: rxm@nrc.gov


of Degraded and Nonconforming
Patrick Madden, NRR


Conditions" and"Operable/Operability:  
301-415-2854 E-mail: pmmMnrc.gov
Ensuring the Functional


Capability
Attachment: List of Recently Issued NRC Information Notices


of a System or Component," to be included in Part 9900, "Technical
Attachment
 
Guidance," of the NRC Inspection
 
Manual. These additions are based upon previously
 
issued guidance.With respect to fire protection
 
and post-fire, safe-shutdown
 
capability, the licensee may discover a previously
 
unanalyzed
 
condition.
 
Under these conditions, Part 9900, "Technical
 
Guidance:
Resolution
 
of Degraded and Nonconforming
 
Conditions," Section 4.4, "Discovery


of an Existing But Previously
IN 97-48 July 9, 1997 LIST OF RECENTLY ISSUED


Unanalyzed
NRC INFORMATION NOTICES


Condition
Information                                      Date of


or Accident," notes that the licensee, upon discovering
Notice No.            Subject                    Issuance  Issued to


an existing but previously
97-47          Inadequate Puncture              06/27/97  All "users and fabricators"
                Tests for Type B                            of type B transportation


unanalyzed
Packages Under 10 CFR                        packages [as defined In


condition
71.73(c)(3)                                  10 CFR 171.11(60)(8)]
97-46          Unisolable Crack in              07/09/97  All holders of OLs or CPs


that significantly
High-Pressure                                for nuclear power reactors


compromises
Injection Piping


plant safety, shall report that condition
96-44,         Failure of Reactor                07/02/97  All holders of OL permits


in accordance
Supp. 1        Trip Breaker from                            for nuclear power reactors


with 10 CFR 50.72 and shall place the plant in a safe condition.
Cracking of Phenolic


Once a degraded or nonconforming
Material In Secondary


condition
Contact Assembly


of specific structures, systems, or components (SSCs) is Identified, an operability
97-45          Environmental                    07/02/97  All holders of OLs or CPs


determination
Qualification                                for nuclear power reactors


should be made as soon as possible, consistent
Deficiency for


with the safety Importance
Cables and Contain- ment Penetration


of the SSC affected.
Pigtails


For SSCs that are outside plant TS, engineering
97-44          Failures of Gamma                07/01/97    All holders of OLs or CPs


judgment must be used to determine
Metrics Wide-Range                            for test and research


safety significance.
Linear Neutron Flux                          reactors


Part 9900, "Technical
Channels


Guidance:
97-43          License Condition                07/01/97    All holders of OLs or CPs
Resolution


of Degraded and Nonconforming
Compliance                                    for nuclear power reactors


Conditions," Section 4.8, "Reasonable
97-42          Management Weaknesses            06/27/97    All fuel cycle conversion, Resulting In Failure                          enrichment, and fabrication


Assurance
to Comply with Shipping                      facilities


of Safety," states that for SSCs which are not expressly subject to TS and which are determined
Requirements for Special


to be Inoperable, the licensee should assess the reasonable
Nuclear Material


assurance
OL - Operating License


of safety. If the assessment
CP - Construction Permit


assures safety, then the facility may continue to operate while prompt corrective
IN 97-48 July 9, 1997 This information notice requires no specific action or written response. Ifyou have any


action is taken. As stated in Part 9900, the following
questions about the Information In this notice, please contact one of the technical contacts


items are to be considered
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


for such assessments:
original signed by S.H. Weiss for
the availability


of redundant
Marylee M. Slosson, Acting Director


or backup equipment, compensatory
Division of Reactor Program Management


measures (including
Office of Nuclear Reactor Regulation


limited administrative
Technical contacts:        Darrell Schrum, RIIl


controls), and the conservatism
(630) 828-9741 E-mail: dis3@nrc.gov
 
and margins.
 
U IN 97-48 July 9, 1997 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."Mi ee M. solosson, Acting Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts:
Darrell Schrum, Rill (630) 828-9741 E-mail: dls3@nrc.gov
 
Rogello Mendez, Rill (630) 829-9745 E-mail: rxm@nrc.gov
 
Patrick Madden, NRR 301-415-2854 E-mail: pmmMnrc.gov
 
Attachment:
List of Recently Issued NRC Information
 
Notices
 
Attachment


IN 97-48 July 9, 1997 LIST OF RECENTLY ISSUED NRC INFORMATION
Rogelio Mendez, RIIl


===NOTICES Information===
(630) 829-9745 E-mail: rxmonrc.gov
Notice No.Date of Issuance Subject Issued to 97-47 97-46 96-44, Supp. 1 97-45 97-44 97-43 97-42 Inadequate


Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3)
Patrick Madden, NRR
Unisolable


Crack in High-Pressure
301-415-2854 E-mail: pmm@nrc.gov


Injection
Attachment: List of Recently Issued NRC Information Notices


Piping Failure of Reactor Trip Breaker from Cracking of Phenolic Material In Secondary Contact Assembly Environmental
Tech Editor has reviewed and concurred on 01/28/97
              * - See pervious concurrence


===Qualification===
DOCUMENT NAME:          97-48.1N
Deficiency


for Cables and Contain-ment Penetration
To Ituveasm pof      Agocufm k otsInbam born T, a Copy W~o


Pigtails Failures of Gamma Metrics Wide-Range
utischment/.ncioswe *I a Copy w/o IIchment/ancdoeure N" a No Copy


Linear Neutron Flux Channels License Condition Compliance
I


Management
OFFICE


Weaknesses
NAME


Resulting
TECH CONTS


In Failure to Comply with Shipping Requirements
TGreen*
                PMadden*
                                        IC/PECB:DRPM


for Special Nuclear Material 06/27/97 07/09/97 07/02/97 07/02/97 07/01/97 07/01/97 06/27/97 All "users and fabricators" of type B transportation
AChaffee*
                                                                  AD:DRPM


packages [as defined In 10 CFR 171.11(60)(8)]
MSIosson*
All holders of OLs or CPs for nuclear power reactors All holders of OL permits for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for test and research reactors All holders of OLs or CPs for nuclear power reactors All fuel cycle conversion, enrichment, and fabrication
  DTF            02/03/97                    062397              0/      97
                02/04/97                  .................      Z              "II


facilities
UNI!LIAL KLLUXU LUPY


OL -Operating
IN 97- June ,1997 This information notice requires no specific action or written response. If you have any


License CP -Construction
questions about the Information in this notice, please contact one of the technical contacts


Permit
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


IN 97-48 July 9, 1997 This information
Marylee M. Slosson, Acting Director


notice requires no specific action or written response.
Division of Reactor Program Management


If you have any questions
Office of Nuclear Reactor Regulation


about the Information
Technical contacts:  Darrell Schrum, Rill


In this notice, please contact one of the technical
(630) 828-9741 E-mail: dls3@nrc.gov


contacts listed below or the appropriate
Rogello Mendez, Rill


Office of Nuclear Reactor Regulation (NRR) project manager.original signed by S.H. Weiss for Marylee M. Slosson, Acting Director Division of Reactor Program Management
(630) 829-9745 E-mail: rxm@nrc.gov


===Office of Nuclear Reactor Regulation===
Patrick Madden, NRR
Technical


contacts: Darrell Schrum, RIIl (630) 828-9741 E-mail: dis3@nrc.gov
301-415-2854 E-mail: pmm@nrc.gov


Rogelio Mendez, RIIl (630) 829-9745 E-mail: rxmonrc.gov
Attachment: List of Recently Issued NRC Information Notices


Patrick Madden, NRR 301-415-2854 E-mail: pmm@nrc.gov
'- See pervious concurrence


Attachment:
LOFC
List of Recently Issued NRC Information


Notices Tech Editor has reviewed and concurred
NAME


on 01/28/97* -See pervious concurrence
DATE


DOCUMENT NAME: 97-48.1N To Ituveasm pof Agocufm k ot s Inb am born T, a Copy W~o utischment/.ncioswe
T. Greene*
              2/03/97 PECB:DRPM


*I a Copy w/o I Ichment/ancdoeure
P. Madden*
                                2/04/97 SPLB:DSSA


N" a No Copy OFFICE TECH CONTS IC/PECB:DRPM
G. Holahan'
                                                  5/25/97 DIDSSA


AD:DRPM I NAME TGreen* AChaffee*
Chaffee C4
MSIosson*PMadden*DTF 02/03/97 062397 0/ 97 02/04/97 .................
                                                                      "97 C/PECB:DRPM


Z "II UNI!LIAL KLLUXU LUPY
I'll      -
                                                                                          I,
                                                                                      -)(0/0?W


IN 97-June ,1997 This information
OFC      D/DRPM


notice requires no specific action or written response.
NAME    M. Slosson


If you have any questions
DATE      6/ 197


about the Information
IN97- June ,1997 This Information notice requires no specific action or written response. Ifyou have any


in this notice, please contact one of the technical
question about the Information In this notice, please contact one of the technical contacts


contacts listed below or the appropriate
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting Director Division of Reactor Program Management
Marylee M. Slosson, Director


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


contacts: Darrell Schrum, Rill (630) 828-9741 E-mail: dls3@nrc.gov
Office of Nuclear Reactor Regulation


Rogello Mendez, Rill (630) 829-9745 E-mail: rxm@nrc.gov
Technical contacts: Darrell Schrum, Rill


Patrick Madden, NRR 301-415-2854 E-mail: pmm@nrc.gov
(630) 828-9741 E-mail: dls3@nrc.gov


Attachment:
Rogello Mendez, Rill
List of Recently Issued NRC Information


Notices'- See pervious concurrence
(630) 829-9745 E-mail: rxmanrc.gov


LOFC PECB:DRPM
Patrick Madden, NRR


SPLB:DSSA
(301) 415-2854 E-mail: pmm@nrc.gov


DIDSSA C/PECB:DRPM
Attachment: List of Recently Issued NRC Information Notices


NAME T. Greene* P. Madden* G. Holahan' Chaffee C4 DATE 2/03/97 2/04/97 5/25/97 "97 I, OFC D/DRPM NAME M. Slosson DATE 6/ 197 I'll --) (0/0? W
- See pervious concurrence


IN 97-June ,1997 This Information
OFC      PECB:DRPM          SPLB:DSSA        DIDSSA            C/PECB:DRPM


notice requires no specific action or written response.
NAME      T. Greene*        P. Madden*        G. Holahan*      A. Chaffee


If you have any question about the Information
DATE        2/03/97          2/04/97            5/25/97          61 /97
                                                                                      01ý
  OFC      D/DRPM


In this notice, please contact one of the technical
NAME      M. Slosson


contacts listed below or the appropriate
DATE        8/ /97 (OFFICIAL RECORD COPY)
DOCUMENT NAME: G:\TAGYINFIRE.TAG


Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Director Division of Reactor Program Management
IN97- May ,1997 This Information notice requires no specific action or written response. Ifyou have any


===Office of Nuclear Reactor Regulation===
question about the Information In this notice, please contact one of the technical contacts
Technical


contacts: Darrell Schrum, Rill (630) 828-9741 E-mail: dls3@nrc.gov
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


Rogello Mendez, Rill (630) 829-9745 E-mail: rxmanrc.gov
Marylee M. Slosson, Director


Patrick Madden, NRR (301) 415-2854 E-mail: pmm@nrc.gov
Division of Reactor Program Management


Attachment:
Mece of Nuclear Reactor Regulation
List of Recently Issued NRC Information


Notices-See pervious concurrence
Technical contacts: Darrell Schrum, Rill


OFC PECB:DRPM
(630) 828-9741 E-mail: dls3@nrc.gov


SPLB:DSSA
Rogelio Mendez, RIII


DIDSSA C/PECB:DRPM
(630) 829-9745 E-mail: rxm@nrc.gov


NAME T. Greene* P. Madden* G. Holahan* A. Chaffee DATE 2/03/97 2/04/97 5/25/97 61 /97 01ýOFC D/DRPM NAME M. Slosson DATE 8/ /97 (OFFICIAL
Patrick Madden, NRR


RECORD COPY)DOCUMENT NAME: G:\TAGYINFIRE.TAG
(301) 415-2854 E-mail: pmm@nrc.gov


IN 97-May ,1997 This Information
Attachment: List of Recently Issued NRC Information Notices


notice requires no specific action or written response.
- See pervious concurrence


If you have any question about the Information
OFC    PECB:DRPM            SPLB:DSSA          D/DSSA            C/PECB:DRPM


In this notice, please contact one of the technical
NAM    T. Greene*          P. Madden*          G. Holahan*        A. Chaffee


contacts listed below or the appropriate
E


Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Director Division of Reactor Program Management
DATE      2/03/97            2/04/97            4125197            5/ /97
                                                                                        ,n I


===Mece of Nuclear Reactor Regulation===
OFC      D/DRPM
Technical


contacts: Darrell Schrum, Rill (630) 828-9741 E-mail: dls3@nrc.gov
4q 4,         //'3V,7 NAM    M. Slosson


Rogelio Mendez, RIII (630) 829-9745 E-mail: rxm@nrc.gov
E


Patrick Madden, NRR (301) 415-2854 E-mail: pmm@nrc.gov
DATE      5/ 197
[OFFICIAL RECORD COPY)
DOCUMENT NAME: G:\TAG\INFIRE.TAG


Attachment:
IN 97- April .1997 This Information notice requires no specific action or written response. If you have any
List of Recently Issued NRC Information


Notices-See pervious concurrence
question about the information In this notice, please contact one of the technical contacts


OFC PECB:DRPM
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


SPLB:DSSA
Thomas T. Martin, Director


D/DSSA C/PECB:DRPM
Division of Reactor Program Management


NAM T. Greene* P. Madden* G. Holahan* A. Chaffee E DATE 2/03/97 2/04/97 4125197 5/ /97 ,n I OFC D/DRPM NAM M. Slosson E DATE 5/ 197 4q 4 , //'3V,7[OFFICIAL
Office of Nuclear Reactor Regulation


RECORD COPY)DOCUMENT NAME: G:\TAG\INFIRE.TAG
Technical contacts: Darrell Schrum, Rill


IN 97-April .1997 This Information
(630) 828-9741 E-mail: dls3@nrc.gov


notice requires no specific action or written response.
Rogello Mendez, Rill


If you have any question about the information
(630) 829-9745 E-mail: rxm~nrc.gov


In this notice, please contact one of the technical
Patrick Madden, NRR


contacts listed below or the appropriate
(301) 415-2854 E-mail: pmm@nrc.gov


Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, Director Division of Reactor Program Management
Attachment: List of Recently Issued NRC Information Notlc as


===Office of Nuclear Reactor Regulation===
* - See pervious concurrence
Technical


contacts: Darrell Schrum, Rill (630) 828-9741 E-mail: dls3@nrc.gov
OFC      PECB:DRPM          SPLB:DSSA          DqW '          '      C/PECB:DRPM


Rogello Mendez, Rill (630) 829-9745 E-mail: rxm~nrc.gov
NAM      T. Greene*          P. Madden*              lahan          A. Chaffee


Patrick Madden, NRR (301) 415-2854 E-mail: pmm@nrc.gov
E            -__-
  DATE      2/03/97            2104/97            1    7              2/ /97 OFC      D/DRPM


Attachment:
NAM    -rh~n
List of Recently Issued NRC Information


Notlc as* -See pervious concurrence
E


OFC PECB:DRPM
DATE      2/ /97
[OFFICIAL RECORD COPY)
DOCUMENT NAME: G:ATAG\INFIRETAG


SPLB:DSSA
*,4r*I.'    IN97- febre      , 1997 This Information notice requires no specific action or wdtten response. If you have any


DqW ' ' C/PECB:DRPM
question about the Information In this notice, please contact one of the technical contacts


NAM T. Greene* P. Madden* lahan A. Chaffee E -__-DATE 2/03/97 2104/97 1 7 2/ /97 OFC D/DRPM NAM -rh~n E DATE 2/ /97[OFFICIAL
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


RECORD DOCUMENT NAME: COPY)G:ATAG\INFIRETAG
Thomas T. Martin, Director


IN 97-febre , 1997 This Information
Division of Reactor Program Management


notice requires no specific action or wdtten response.
Office of Nuclear Reactor Regulation


If you have any question about the Information
Technical contacts: Darrell Schrum, Rill


In this notice, please contact one of the technical
(630) 828-9741 E-mail: dls3@nrc.gov


contacts listed below or the appropriate
Rogelio Mendez, Rill


Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, Director Division of Reactor Program Management
(630) 829-9745 E-mail: rxm@nrc.gov


===Office of Nuclear Reactor Regulation===
Patrick Madden, NRR
Technical


contacts: Darrell Schrum, Rill (630) 828-9741 E-mail: dls3@nrc.gov
(301) 415-2854 E-mail: pmm@nrc.gov


Rogelio Mendez, Rill (630) 829-9745 E-mail: rxm@nrc.gov
Attachment: List of Recently Issued NRC Information Notices


Patrick Madden, NRR (301) 415-2854 E-mail: pmm@nrc.gov
OFC      PECB:DRPM          SPLB:DSSA          DIDSSA              CIPECB:DRPM


Attachment:
NAT.        Green@          P      en          . Holahan',        A. Chaffee
List of Recently Issued NRC Information


Notices OFC PECB:DRPM
E


SPLB:DSSA
DATE 12/3/97                F/1197                21 /97            j2/ /97 OFC      D/DRPM


DIDSSA CIPECB:DRPM
NAM      T. Martin


NAT. Green@ P en .Holahan', A. Chaffee E DATE 12/3/97 F/1197 21 /97 j2/ /97 OFC D/DRPM NAM T. Martin E 7 DATE 12/ /97[OFFICIAL
E


RECORD COPY]DOCUMENT NAME: G:\TAG\INFIRE.TAG}}
7 DATE 12/ /97
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\TAG\INFIRE.TAG}}


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

Latest revision as of 11:27, 23 November 2019

Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML070180068
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, 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  Entergy icon.png
Issue date: 07/09/1997
From: Slosson M
Office of Nuclear Reactor Regulation
To:
References
IN-97-048, NUDOCS 9707020308
Download: ML070180068 (11)
v • d • e


9. '5 UN.TED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 July 9, 1997 NRC INFORMATION NOTICE 97-48: INADEQUATE OR INAPPROPRIATE INTERIM FIRE

PROTECTION COMPENSATORY MEASURES

All holders of operating licenses or construction permits for nuclear power reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) Is Issuing this Information notice to alert

addressees to potential problems associated with the Implementation of interim compensatory

measures for degraded or Inoperable plant fire protection features or degraded or Inoperable

conditions associated with post-fire safe-shutdown capability. It is expected that recipients

will review the informatioit for applicability to their facilities and consider actions, as

appropriate, to avoid similar problems. However, suggestions contained In this information

notice are not NRC requiremnents; therefore, no specific action or wdtten response is

required.

Description of Circumstances

The NRC foresaw cases in which fire protection features would be inoperable and allowed

licensees, through plant technical specifications (TS) or approved fire protection plans

controlled by license conditions, to implement alternative actions to compensate for the

inoperable condition or component until permanent corrective actions are implemented. In

general, the combination of appropriate compensatory measures and the defense-in-depth

fire protection features provides an adequate level of fire protection until the licensees

complete the corrective actions, For common types of deficiencies (e.g., an Inoperable fire

suppression system), the specific compensatory measures are generally noted in either the

TS or in the NRC-approved fire protection program. For unique plant-specific situations (e.g.,

Inadequate cable separation), the appropriate compensatory measures are determined by the

licensee on a case-by-case basis. (This is discussed further later in the information notice.)

NRC reviews of licensees' corrective actions to address degraded or Inoperable conditions

associated with a plant's abilities to achieve and maintain post-fire safe shutdown have noted

some weaknesses in the interim compensatory measures. For example, some licensees

have relied exclusivoly on the 1-hour roving fire watch as an interim compensatory measure

for deficiencies that affect their abilities to achieve and maintain post-fire safe shutdown and

have not considered or Implemented other appropriate interim compensatory measures, such

as briefing operators on degraded post-fire, safe-shutdown-system conditions; temporary

repair procedures; temporary fire barriers; or detection or suppression systems. In addition, A

____  ?DE q=TE 91-011 911o(

(9707020308 dQV

11111111111111111011

IN07.48 July 9, 197o MC kIspectlons of fire protection programs have found weaknesses In kliensees' fle watch

t'Org programs and In the conduct of fire watch dutiee. Specific examples documented In

NRC Inspection reports Include the following:

ODutig a November 1996 Inspection at Waterford Generating Station (Inspection Report

W0-382/95-020, Accession No. 9603260040), NRC Inspectors found that the licensee's

procedures redefined the

Intent

of a continuous fire watch. The licensees' procedure

required a 15-minute roving fire watch, with a margin of 5 minutes, In lieu of a continuous

fir watch. In addition, required fire watches were not performed in areas In which fire

detection equipment was out of service and In areas In which fire barriers were degraded.

This Issue Is currently under review by the NRC for disposition.

  • During an April 1996 Inspection at Palisades Nuclear Plant (Inspection Report 60-255/

96-004, Accession No. 9805290105). the NRC Inspector noted that the licensee relied on

fire watches as compensatory measures for a number of post-fire, safe-shutdown-design

deficiencies Identified by the licensee pursuant to Appendix R to Part 50 of T ", 10 of the

Code f Federal Regulations (10 CFR Part 50) while long-term corrective actlukns were

being evaluated. The licensee did not alert the operators to these deficient conditions nor

did It provide interim shutdown strategies to operators on how to ouccossfully deal with

potential fire damage to required safe-shutdown components. The potential conse- quences could have been extensive since placing and maintaining the plant in post-fire

hot standby could only have bean achieved by significant operator actions, trouble- shooting, and repair activities to compensate for the post-fire, safe-shutdown-design

deficiencies. The sole use of a fire watch for a safe shutdown function which Is not

adequately protected against fire damage is an Inappropriate application of a

compensatory measure. This problem resulted in a Severity Level III Violation.

  • On October 17, 1998, Arkansas Nuclear One had an event involving a fire in a reactor

coolant pump (RCP) and inadequacies associated with the RCP oil collection system.

The licensee's initial compensatory measures placed the lift olK pumps in the "stop"

condition. This action enhanced the fire protection annunciator procedures by giving

additional guidance to the operators when responding to the RCP smoke detector alarm.

However, the licensee did not propose Interim plant operational measures which would

help operators identify and mitigate the consequence of potential oil leakage from the

RCP oil system sites not protected by the RCP oil collection system. This problem

resulted in a Severity Level III Violation.

Discussion]

In accordance with 10 CFR 50.48, "Fire protection," each operating nuclear power plant must

have a fire protection plan that satisfies Criterion 3 of Appendix A to 10 CFR Part 50.

Licensees of plants licensed to operate before January 1, 1979, are required to satisfy the

provisions of Appendix R to 10 CFR Part 50, Section Ill.G, "Fire protection of safe shutdown

I' .

IN 97-48 July 9, 1997 capability;" Section Ill.J, "Emergency lighting;" and Section 111.0, "Oil collection system for

reactor coolant pump;" and the provisions of Appendix A to the Branch Technical Position of

the Auxiliary Power Conversion Systems Branch (BTP APCSB) 9.5-1, "Guidelines for Fire

Protection for Nuclear Power Plants Docketed Prior to July 1, 1978." Licensees of plants

licensed to operate after January 1, 1979, are required to satisfy the fire protection provisions

of their operating licenses. Generally, these plants have fire protection programs that satisfy

the provisions of NUREG-0800, "Standard Review Plan (SRP)," Section 9.5.1; "Fire

Protection Program," July 1981.

Appendix A to BTP APCSB 9.5-1 specifies that licensees should establish administrative

controls for normal and abnormal conditions or such other anticipated operations as

modifications (e.g., breaking fire stops/penetration seals, Impairment of fire dete,'tion and

suppression systems) and refueling activities. The controls should be reviewed by

appropriate levels of licensee management, and appropriate special actions and procedures, such as fire watches or temporary fire barriers, should be implemented to ensure adequate

fire protection and reactor safety.

On November 7, 1991, the NRC issued Generic Letter 91-18, "Information to Licensees

Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and

Nonconforming Conditions and on Operability" (Accession No. 9111040293). This generic

letter contained two sections, "Resolution of Degraded and Nonconforming Conditions" and

"Operable/Operability: Ensuring the Functional Capability of a System or Component," to be

included in Part 9900, "Technical Guidance," of the NRC Inspection Manual. These additions

are based upon previously issued guidance.

With respect to fire protection and post-fire, safe-shutdown capability, the licensee may

discover a previously unanalyzed condition. Under these conditions, Part 9900, "Technical

Guidance: Resolution of Degraded and Nonconforming Conditions," Section 4.4, "Discovery

of an Existing But Previously Unanalyzed Condition or Accident," notes that the licensee, upon discovering an existing but previously unanalyzed condition that significantly

compromises plant safety, shall report that condition in accordance with 10 CFR 50.72 and

shall place the plant in a safe condition. Once a degraded or nonconforming condition of

specific structures, systems, or components (SSCs) is Identified, an operability determination

should be made as soon as possible, consistent with the safety Importance of the SSC

affected. For SSCs that are outside plant TS, engineering judgment must be used to

determine safety significance.

Part 9900, "Technical Guidance: Resolution of Degraded and Nonconforming Conditions,"

Section 4.8, "Reasonable Assurance of Safety," states that for SSCs which are not expressly

subject to TS and which are determined to be Inoperable, the licensee should assess the

reasonable assurance of safety. Ifthe assessment assures safety, then the facility may

continue to operate while prompt corrective action is taken. As stated in Part 9900, the

following items are to be considered for such assessments: the availability of redundant or

backup equipment, compensatory measures (including limited administrative controls), and

the conservatism and margins.

U

IN 97-48 July 9, 1997 This Information notice requires no specific action or written response. Ifyou 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.

"Mi ee M. solosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, Rill

(630) 828-9741 E-mail: dls3@nrc.gov

Rogello Mendez, Rill

(630) 829-9745 E-mail: rxm@nrc.gov

Patrick Madden, NRR

301-415-2854 E-mail: pmmMnrc.gov

Attachment: List of Recently Issued NRC Information Notices

Attachment

IN 97-48 July 9, 1997 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

97-47 Inadequate Puncture 06/27/97 All "users and fabricators"

Tests for Type B of type B transportation

Packages Under 10 CFR packages [as defined In

71.73(c)(3) 10 CFR 171.11(60)(8)]

97-46 Unisolable Crack in 07/09/97 All holders of OLs or CPs

High-Pressure for nuclear power reactors

Injection Piping

96-44, Failure of Reactor 07/02/97 All holders of OL permits

Supp. 1 Trip Breaker from for nuclear power reactors

Cracking of Phenolic

Material In Secondary

Contact Assembly

97-45 Environmental 07/02/97 All holders of OLs or CPs

Qualification for nuclear power reactors

Deficiency for

Cables and Contain- ment Penetration

Pigtails

97-44 Failures of Gamma 07/01/97 All holders of OLs or CPs

Metrics Wide-Range for test and research

Linear Neutron Flux reactors

Channels

97-43 License Condition 07/01/97 All holders of OLs or CPs

Compliance for nuclear power reactors

97-42 Management Weaknesses 06/27/97 All fuel cycle conversion, Resulting In Failure enrichment, and fabrication

to Comply with Shipping facilities

Requirements for Special

Nuclear Material

OL - Operating License

CP - Construction Permit

IN 97-48 July 9, 1997 This information notice requires no specific action or written response. Ifyou 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.

original signed by S.H. Weiss for

Marylee M. Slosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, RIIl

(630) 828-9741 E-mail: dis3@nrc.gov

Rogelio Mendez, RIIl

(630) 829-9745 E-mail: rxmonrc.gov

Patrick Madden, NRR

301-415-2854 E-mail: pmm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

Tech Editor has reviewed and concurred on 01/28/97

  • - See pervious concurrence

DOCUMENT NAME: 97-48.1N

To Ituveasm pof Agocufm k otsInbam born T, a Copy W~o

utischment/.ncioswe *I a Copy w/o IIchment/ancdoeure N" a No Copy

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OFFICE

NAME

TECH CONTS

TGreen*

PMadden*

IC/PECB:DRPM

AChaffee*

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MSIosson*

DTF 02/03/97 062397 0/ 97

02/04/97 ................. Z "II

UNI!LIAL KLLUXU LUPY

IN 97- June ,1997 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.

Marylee M. Slosson, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, Rill

(630) 828-9741 E-mail: dls3@nrc.gov

Rogello Mendez, Rill

(630) 829-9745 E-mail: rxm@nrc.gov

Patrick Madden, NRR

301-415-2854 E-mail: pmm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

'- See pervious concurrence

LOFC

NAME

DATE

T. Greene*

2/03/97 PECB:DRPM

P. Madden*

2/04/97 SPLB:DSSA

G. Holahan'

5/25/97 DIDSSA

Chaffee C4

"97 C/PECB:DRPM

I'll -

I,

-)(0/0?W

OFC D/DRPM

NAME M. Slosson

DATE 6/ 197

IN97- June ,1997 This Information notice requires no specific action or written response. Ifyou have any

question 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.

Marylee M. Slosson, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, Rill

(630) 828-9741 E-mail: dls3@nrc.gov

Rogello Mendez, Rill

(630) 829-9745 E-mail: rxmanrc.gov

Patrick Madden, NRR

(301) 415-2854 E-mail: pmm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

- See pervious concurrence

OFC PECB:DRPM SPLB:DSSA DIDSSA C/PECB:DRPM

NAME T. Greene* P. Madden* G. Holahan* A. Chaffee

DATE 2/03/97 2/04/97 5/25/97 61 /97

01ý

OFC D/DRPM

NAME M. Slosson

DATE 8/ /97 (OFFICIAL RECORD COPY)

DOCUMENT NAME: G:\TAGYINFIRE.TAG

IN97- May ,1997 This Information notice requires no specific action or written response. Ifyou have any

question 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.

Marylee M. Slosson, Director

Division of Reactor Program Management

Mece of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, Rill

(630) 828-9741 E-mail: dls3@nrc.gov

Rogelio Mendez, RIII

(630) 829-9745 E-mail: rxm@nrc.gov

Patrick Madden, NRR

(301) 415-2854 E-mail: pmm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

- See pervious concurrence

OFC PECB:DRPM SPLB:DSSA D/DSSA C/PECB:DRPM

NAM T. Greene* P. Madden* G. Holahan* A. Chaffee

E

DATE 2/03/97 2/04/97 4125197 5/ /97

,n I

OFC D/DRPM

4q 4, //'3V,7 NAM M. Slosson

E

DATE 5/ 197

[OFFICIAL RECORD COPY)

DOCUMENT NAME: G:\TAG\INFIRE.TAG

IN 97- April .1997 This Information notice requires no specific action or written response. If you have any

question 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.

Thomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, Rill

(630) 828-9741 E-mail: dls3@nrc.gov

Rogello Mendez, Rill

(630) 829-9745 E-mail: rxm~nrc.gov

Patrick Madden, NRR

(301) 415-2854 E-mail: pmm@nrc.gov

Attachment: List of Recently Issued NRC Information Notlc as

  • - See pervious concurrence

OFC PECB:DRPM SPLB:DSSA DqW ' ' C/PECB:DRPM

NAM T. Greene* P. Madden* lahan A. Chaffee

E -__-

DATE 2/03/97 2104/97 1 7 2/ /97 OFC D/DRPM

NAM -rh~n

E

DATE 2/ /97

[OFFICIAL RECORD COPY)

DOCUMENT NAME: G:ATAG\INFIRETAG

  • ,4r*I.' IN97- febre , 1997 This Information notice requires no specific action or wdtten response. If you have any

question 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.

Thomas T. Martin, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Darrell Schrum, Rill

(630) 828-9741 E-mail: dls3@nrc.gov

Rogelio Mendez, Rill

(630) 829-9745 E-mail: rxm@nrc.gov

Patrick Madden, NRR

(301) 415-2854 E-mail: pmm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

OFC PECB:DRPM SPLB:DSSA DIDSSA CIPECB:DRPM

NAT. Green@ P en . Holahan', A. Chaffee

E

DATE 12/3/97 F/1197 21 /97 j2/ /97 OFC D/DRPM

NAM T. Martin

E

7 DATE 12/ /97

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TAG\INFIRE.TAG


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