Containment Inspection Rule ML031060003 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 , 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 , Crane Issue date:
05/30/1997 From:
Slosson M Office of Nuclear Reactor Regulation To:
References IN-97-029 , NUDOCS 9705290064Download: ML031060003 (9)
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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 ,
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 ,
Crane Category:NRC Information Notice
[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 [[: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]] OR [[:Crane]] </code>.
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Contents
1 UNITED STATES
2 OFFICE OF NUCLEAR REACTOR REGULATION
3 May 30, 1997
4 Addressees
5 Purpose
6 Description of Circumstances
6.1 Marylee M. Slosson, Acting Director
6.2 Office of Nuclear Reactor Regulation
6.3 Hans Ashar, NRR
6.4 May 30, 1997 0
6.5 NRC INFORMATION NOTICES
6.6 Elimination of Instrument
6.7 Under the Requirements of
6.8 Effect of Incorrect
6.9 Suction Head
6.10 All holders of OLs or CPs
6.11 All holders of OLs or CPs
6.12 Potential for Water
6.13 Residual Heat Removal
6.14 Level Instrumentation
6.15 All holders of OLs or CPs
6.16 All holders of OLs or CPs
6.17 Marylee M. Slosson, Acting Director
6.18 Office of Nuclear Reactor Regulation
6.19 Hans Ashar, NRR
6.20 OFFICIAL RECORD COPY
6.21 Marylee M. Slosson, Acting Director
6.22 Office of Nuclear Reactor Regulation
6.23 Hans Ashar, NRR
6.24 See previous concurrence
6.25 Thomas T. Martin, Director
6.26 Office of Nuclear Reactor Regulation
6.27 Hans Ashar, NRR
6.28 OFFICIAL RECORD COPY
6.29 Thomas T. Martin, Director
6.30 Office of Nuclear Reactor Regulation
6.31 Hans Ashar, NRR
6.32 OFFICIAL RECORD COPY
6.33 Thomas T. Martin, Director
6.34 Office of Nuclear Reactor Regulation
6.35 Seung Lee, NRR
6.36 Hans Ashar, NRR
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON , D.C. 20555-0001
May 30, 1997
NRC INFORMATION NOTICE 97-29: CONTAINMENT INSPECTION RULE
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 clarify
for addressees the containment inspection rule in accordance with 10 CFR 50.55a(a) , which
in part endorses Subsections IWE and IWL of Section Xl of the American Society of
Mechanical Engineers' Boiler and Pressure Vessel Code (ASME Code). The rule became
effective on September 9, 1996. It is expected that recipients will review the information for
applicability to their facilities and consider actions, as appropriate. However, suggestions
contained in this information notice are not NRC requirements; therefore, no specific action or
written response is required.
Description of Circumstances
In a Federal Register, dated August 8, 1996 (61 FR 41303 ), the NRC amended its
regulations (rule) to incorporate by reference the 1992 Edition and Addenda of
Subsections IWE and IWL of Section Xl of the ASME Code. Subsections IWE and IWL give
the requirements for inservice inspection (ISI ) of Class CC (concrete containments), and
Class MC (metallic containments) of light-water-cooled power plants. The amended rule
became effective on September 9, 1996; it requires the licensees to incorporate the new
requirements into their ISI plans and to complete the first containment inspection within five
years (i.e., no later than September 9, 2001). Any repair or replacement (RIR ) activity to be
performed on containments after the effective date of September 9, 1996, has to be carried
out in accordance with the respective requirements of Subsections IWE and IWL.
Recognizing the potential industry concern related to the immediate implementation of the
rule for R/R activities, the Nuclear Energy Institute (NEI) wrote a letter to NRC (Reference 1)
indicating a general industry interpretation of the rule that all containment ISI activities, including R/R activities should be effective from September 9, 2001. The NRC responded to
the NEI letter (Reference 2) stating that all R/R activities within the scope of Subsections IWE
and IWL of the code conducted after September 9, 1996, must be conducted in accordance
with these subsectio
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IN 97-29 May 30, 1997 Additionally, the staff stated (Reference 2) that 10 CFR 50.55a(3) permits the Director of the
Office of Nuclear Reactor Regulation at his discretion to grant relief from the requirements of
10 CFR 50.55a to licensees who submit a justifiable need to use an alternative that provides
an acceptable level of safety or who encounter extreme hardship or unusual difficulty without
a compensating increase in the level of quality or safety. In general, the staff stated that with
proper justification, relief requests from compliance with the RJR requirements of Subsections
IWE and IWL for a period of about one year from September 9, 1996, would appear to be
reasonable.
Although NEI sent the response from NRC to many of the addressees, the NRC staff is
issuing this information notice to inform all addressees about the NRC staff position.
Discussion
As discussed above, addressees are required to implement the rule for all containment- related R/R activities to be conducted after September 9, 1996. Even though a licensee is
able to demonstrate hardship or unusual difficulties in the immediate implementation of the
rule, the licensee has to demonstrate that other procedures utilized for R/R activities will
ensure adequate safety of the containments and that proper quality assurance requirements
have been implemented.
In some of the relief requests that the staff has reviewed, licensees have reported
appropriate "hardship and unusual difficulties" reasons for postponing the implementation of
the rule, but did not describe the effectiveness of the procedures they plan to use during the
relief period. Without such information, the staff has no way of concluding that the quality
and safety of containment RIR activities are adequate.
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IN 97-29 May 30, 1997 This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact 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: Seung Lee, NRR
301-415-2737 E-mail: sjl@nrc.gov
Hans Ashar, NRR
301-415-2851 E-mail: hgaenrc.gov
References
1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation of
Amended 10 CFR 50.55a, " dated 09119/96 (Accession No. 9704180074).
2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation of
Containment Inspection Rule," dated 11/06/96 (Accession No. 9611130161).
Attachment: List of Recently Issued NRC Information Notices
kit
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a
Attachment
IN 97-29
May 30, 1997 0
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
97-28
97-27
Elimination of Instrument
Response Time Testing
Under the Requirements of
10 CFR 50.59
Effect of Incorrect
Strainer Pressure Drop
on Available Net Positive
Suction Head
Degradation in Small- Radius U-Bend Regions
of Steam Generator Tubes
05/30/97
05/16/97
05/19/97
All holders of OLs or CPs
All holders of OLs or CPs
for light-water power
reactors, except those
licensees who have per- manently ceased operations
and have certified that
fuel has been permanently
removed from the reactor
vessel
All holders of OLs or CPs
for pressurized-water
reactors
97-26
87-10,
Sup. 1
Potential for Water
Hammer During Restart of
Residual Heat Removal
Pumps
Dynamic Range Uncertain- ties in the Reactor Vessel
Level Instrumentation
05/15/97
05/09/97
All holders of OLs or CPs
for boiling-water reactors
All holders of OLs or CPs
for Westinghouse pressurized- water reactors
97-25 OL = Operating License
CP = Construction Permit
IN 97-29 May 30, 1997 This information notice requires no specific action or writterd response. If you have any
questions about the information in this notice, please contact 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: Seung Lee, NRR
301-415-2737 E-mail: sjl@nrc.gov
Hans Ashar, NRR
301-415-2851 E-mail: hga@nrc.gov
References
1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation of
Amended 10 CFR 50.55a, " dated 09/19196 (Accession No. 9704180074).
2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation of
Containment Inspection Rule," dated 11/06/96 (Accession No. 9611130161).
Attachment: List of Recently Issued NRC Inforrnation Notices
Tech Editor has reviewed and concurred on 4/17/97 DOCUMENT NAME: 97-29.IN
To receive a copy of this document, kndlcata hI the box: *C' - Copy w/o
attachmentlenclosure 'E' - Copy wlattachmentlenclosure 'N'
- No copy
OFFICE
TECH CONTS
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NAME
SLee*
AChaffee*
MSos;
TGreene*
_
_
_
_
DATE
04/22/97
05/15/97
05/2.3/97 IV
OFFICIAL RECORD COPY
IN 97-XX
May XX, 1997 This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact 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: Seung Lee, NRR
(301) 415-2737 E-mail: sjl~nrc.gov
Hans Ashar, NRR
(301) 415-2851 E-mail: hga~nrc.gov
References
1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation of
Amended 10 CFR 50.55a, " dated 09/19/96 (Accession No. 9704180074).
2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation of
Containment Inspection Rule," dated 11/06/96 (Accession No. 9611130161).
Attachment: List of Recently Issued NRC Information Notices
OFC
PECB:DRPM
ECGB:DE
CIECGB:DE
OGC
NAME
T. Greene*
S. Lee*
G. Bagchi*
S. Treby*
DATE
04/22/97
04/22/97
04/24/97
05/06/97
See previous concurrence
OFC
CIPECB:DRPM
AD/DRPK 1 NAME
A. Chaffee6W
M. Slosson
X
DATE
ij/197
/97 OFFICIAL RECORD
51
97 DOCUMENT NAME: GATAGXINCONT
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uIN
97-XX
May XX, 1997 This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact 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: Seung Lee, NRR
(301) 415-2737 E-mail: sjlenrc.gov
Hans Ashar, NRR
(301) 415-2851 E-mail: hga@nrc.gov
REFERENCES
1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation of
Amended 10 CFR 50.55a, " September 19, 1996 (Accession 9704180074).
2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation of
Containment Inspection Rule," November 6, 1996 (Accession 9611130161).
Attachment: List of Recently Issued NRC Information Notices
,no to?'
OFC
PECB:DRPM
ECGB:DE
C/ECGB:DE
OGC
NAME
T. Greene*
S. Lee*
G. Bagchi*
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/
DATE
04/22/97
04/22/97
04/24/97
6//97 See previous concurrence
--
______
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NA
A. Chaffee
T. Martin
lDATE
/97
1 197
OFFICIAL RECORD COPY
DOCUMENT NAME: G:\\TAGXINCONT
IN 97-XX
April XX, 1997 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
the technical contact 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: Seung Lee, NRR
(301) 415-2737 E-mail: sjl~nrc.gov
Hans Ashar, NRR
(301) 415-2851 E-mail: hga@nrc.gov
REFERENCES
1.
Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation of
Amended 10 CFR 50.55a, " dated September 19, 1996 (Accession, 9704180074).
2.
Letter from Gus Lainas (NRC) to Alex Marion (NEI), 'Implementation of
Containment Inspection Rule," dated November 6, 1996 (Accession
9611130161).
Attachment: List of Recently Issued NRC Information Notices
OFC
PECB:DRPM
l ECGB:DE
C
SBE
ECB:DRPM
D/DRPM
NAME
T. Greene*
S. Lee*
ij 9 -I
j A. Chaffee
T. Martin
DATE
04/22/97
04/22/97
/97 j
/
/97
I
I
OFFICIAL RECORD COPY
DOCUMENT NAME:
G:\\TAG\\INCONT
IN 97-XX
April XX, 1997 This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact 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:
Seung Lee, NRR
(301) 415-2737 E-mail: sjlnrc.gov
Hans Ashar, NRR
(301) 415-2851 E-mail: hgaenrc.gov
REFERENCES
1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation of
Amended 10 CFR 50.55a, " September 19, 1996 (Accession xxxxxoxxxx).
2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation of
Containment Inspection Rule," November 6, 1996 (Accession 9611130161).
Attachment: List of Recently Issued NRC Information Notices
OFC
PECB:DRPM
ECGB:DE
C/ECGB:DE
C/PECB:DRPM
D/DRPM
NAME
T. Greene
S. Lee ;;f
G. Bagchi
A. Chaffee
T. Martin
DATE
1
97 II
97 I //97
1 /97
1 /97 OFFICIAL RECORD COPY]
DOCUMENT NAME: G:ITAGUNCONT
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 , Topic : Intergranular Stress Corrosion Cracking )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 : Notice of Violation , 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 , Topic : Basic Component )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 , Loss of Offsite Power )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 , Loss of Offsite Power )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 , Topic : Overexposure )Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997 , Topic : Loss of Offsite Power )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 , Topic : Gas accumulation )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 )... further results