Inadequate or Inappropriate Interim Fire Protection Compensatory MeasuresML070180068 |
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 |
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Issue date: |
07/09/1997 |
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From: |
Slosson M Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-97-048, NUDOCS 9707020308 |
Download: ML070180068 (11) |
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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>. |
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,____ ?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
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. If the 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.
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
NOTICES Information
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)
Unisolable
Crack in High-Pressure
Injection
Piping Failure of Reactor Trip Breaker from Cracking of Phenolic Material In Secondary Contact Assembly Environmental
Qualification
Deficiency
for Cables and Contain-ment Penetration
Pigtails Failures of Gamma Metrics Wide-Range
Linear Neutron Flux Channels License Condition Compliance
Management
Weaknesses
Resulting
In Failure to Comply with Shipping Requirements
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
packages [as defined In 10 CFR 171.11(60)(8)]
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
facilities
OL -Operating
License CP -Construction
Permit
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.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 ot s Inb am born T, a Copy W~o utischment/.ncioswe
- I a Copy w/o I Ichment/ancdoeure
N" a No Copy OFFICE TECH CONTS IC/PECB:DRPM
AD:DRPM I NAME TGreen* AChaffee*
MSIosson*PMadden*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 PECB:DRPM
SPLB:DSSA
DIDSSA C/PECB:DRPM
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
IN 97-June ,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.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 01ýOFC D/DRPM NAME M. Slosson DATE 8/ /97 (OFFICIAL
RECORD COPY)DOCUMENT NAME: G:\TAGYINFIRE.TAG
IN 97-May ,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.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 NAM M. Slosson E DATE 5/ 197 4q 4 , //'3V,7[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 DOCUMENT NAME: COPY)G:ATAG\INFIRETAG
IN 97-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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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings, Intergranular Stress Corrosion Cracking)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid, Thermal fatigue)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake, Uranium Hexafluoride)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Eddy Current Testing, Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Operability Determination, Continuous fire watch, Fire Protection Program, Fire Watch)
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