Revised - Potentially Undersized Emergency Diesel Generator (EDG ) Oil Coolers ML031050489 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:
06/27/1997 From:
Slosson M Office of Nuclear Reactor Regulation To:
References IN-97-041 , NUDOCS 9706230171Download: ML031050489 (7)
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 ,
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>.
"REVISED PAGE"
Contents
1 NLEAR REGULATORY COMMISSION, ADDRESSEE LINE 2 June 27, 1997 3 Purpose 4 Description of Circumstances
4.1 NOrICEt 9 7C7061 4.2 Marylee M. Slosson, Acting Director 4.3 Office of Nuclear Reactor Regulation 4.4 Jai Rajan, NRR 4.5 John R. Tappert, NRR 4.6 June 27, 1997 LIST OF RECENTLY ISSUED 4.7 Potential Nitrogen 4.8 Safety Injection Tanks 4.9 Safety Evaluations of 4.10 Storage Installations 4.11 Injection Pumps 4.12 Posilock Radiography 4.13 Compatibility 4.14 Unplanned Intakes by 4.15 Airborne Radioactive 4.16 Exposure Due to Inadequate 4.17 All holders of OLs or CPs 4.18 All holders of OLs or CPs 4.19 All holders of licenses for 4.20 All holders of OLs or CPs 4.21 All industrial radiography 4.22 All holders of OLs or CPs 4.23 All holders of OLs and CPs 4.24 Marylee M. Slosson, Acting Director 4.25 Office of Nuclear Reactor Regulation 4.26 Jai Rajan, NRR 4.27 John R. Tappert, NRR 4.28 OFFICIAL RECORD COPY 4.29 Marylee M. Slosson, Acting Director 4.30 Office of Nuclear Reactor Regulation 4.31 Jai Rajan, NRR 4.32 John R. Tappert, NRR 4.33 Thomas T. Martin, Director 4.34 Office of Nuclear Reactor Regulation 4.35 Jai Rajan, NRR 4.36 John R. Tappert
NLEAR REGULATORY COMMISSION, ADDRESSEE LINE OFFICE OF NUCLEAR REACTOR REGULATION
CHANGED
WASHINGTON , D.C. 20555-0001
June 27, 1997 NRC INFORMATION NOTICE 97-41: POTENTIALLY UNDERSIZED EMERGENCY
DIESEL GENERATOR (EDG ) OIL COOLERS
Addresses
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 the discovery of potentially undersized EDG oil coolers at Limerick
Generating Station, Units 1 and 2. It is expected that recipients will review the information
for applicability to their facilities and consider actions, as appropriate, to avoid similar
problems. However, suggestions contained in this information notice are not NRC
requirements; therefore, no specific action or written response is required.
Description of Circumstances Philadelphia Electric Company (PECO ) Nuclear, the licensee for Limerick Generating
Station, Units I and 2, and its consultant Stone and Webster were recently evaluating EDG
heat exchangers in response to NRC Generic Letter (GL) 89-13 . In the course of this
evaluation it was determined that the Limerick EDG lubricating oil coolers were undersized
relative to the design conditions reported on the heat exchanger data sheet. The oil coolers
in question are used to cool lubricating oil for the Coltec EDGs and were designed and
manufactured by American Standard in May 1976. The cooling water for heat removal
circulates through the tubes and the lubricating oil circulates on the shell side. Finned
tubes are used to provide additional heat transfer surface. In the process of verifying the
design adequacy of the heat exchanger, the licensee utilized the widely used computer
modeling program ST-5 , Mod 0.5-1.3, developed by Heat Transfer Research Inc. (HTRI).
HTRI is the leading association for the heat-exchanger industry; its membership includes all
major heat exchanger manufacturers and designers. The licensee used data obtained from
the design data sheet of the heat exchanger. This data included the design geometry and
design conditions, as well as the tube-side fouling factor of 0.002 and the oil-side heat
transfer rate of 83.2 BTUI(hr ft2 'F) for SAE 30 oil. The calculation indicated that the heat
exchanger was 22.8 percent undersized. The licensee informed Coltec about this
discrepancy and requested further evaluation.
Discussion
An evaluation performed by Coltec and its consultants indicates that all design calculations
performed by American Standard in 1976 for this heat exchanger were complete and
correct, TR Is
NOrICEt 9 7C7061 ______C______
XI
IC-
Ic r
9fI8t~lIlllIl!l. '
3 1111 I C
IN 97-41 June 27 1997 including the proper application of the finned tubing surface area ratio to the specified tube- side fouling factor. PECO Nuclear and its consultant originally suspected that the 0.002 fouling factor was erroneously applied unmodified to the outside surface in the original design
of the heat exchanger, resulting in an undersized heat transfer surface. The evaluation
demonstrated that this was not the case. Heat transfer calculations supported by HTRI at the
time of design were considered "state of the art" and the heat exchanger design was based
on the methodology that was current at that time.
The discrepancy between the newly calculated and original design heat transfer surfaces, according to Coltec and is consultants, was caused by a revision in the calculational
methodology for designing heat exchangers implemented in 1985. Calculations based on the
revised method invariably lead to a lower heat transfer surface in comparison with the
previously used calculation procedure. Thus heat exchangers designed before 1985, if
evaluated in accordance with the revised design methods, would be considered undersized.
In 1985, after extensively testing industrial-sized heat exchangers, HTRI modified its
calculation method for cooling viscous shell side fluids. The new calculation method is
considered to be more precise in predicting actual heat transfer and pressure drop
performance. In general, the calculated shell-side heat transfer coefficients obtained with this
revised method are lower than those obtained with the former method. In some cases, the
coefficient can be appreciably lower, depending on fluid viscosity, operating temperatures, flow velocity, and fin geometry.
It therefore appears that heat exchangers designed before 1985 are smaller in size for the
same performance requirements than those designed after 1985. This does not necessarily
mean that they are now considered inadequate for meeting the design requirements. It, however, does mean that they have a lower fouling margin, possibly requiring more frequent
cleaning and testing of the heat exchangers in order to maintain operability. PECO Nuclear
has determined that for the Limerick design, sufficient margin is available given the calculated
temperatures of the emergency service water (ESW ) system to handle the post-accident
loading (which is below the continuous rating). PECO Nuclear's analysis takes into
consideration the seasonal variation of ambient temperatures and the results indicate that by
scheduling of the heat exchanger cleaning precisely, Limerick will be able to maintain EDG
operability. Evaluation of similar heat exchangers of the same vintage may yield similar
results.
IN 97-41 June 27, 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:
Jai Rajan, NRR 301415-2788 E-mail: jrr@nrc.gov
John R. Tappert, NRR 301415-1167 E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
A[,
'-5cAt r
Attachment
IN 97-41
June 27, 1997 LIST OF RECENTLY ISSUED NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
97-40
97-39
97-38
Potential Nitrogen Accumulation Resulting
from Bakickakage from
Safety Injection Tanks Inadequate 10 CFR 72.48
Safety Evaluations of Independent Spent Fuel
Storage Installations Level-Sensing System
Initiates Common-Mode
Failure of High-Pressure-
Injection Pumps Retrofit to Amersham 660
Posilock Radiography Camera to Correct Incon- sistency in 10 CFR Part 34
Compatibility Main Transformer Fault
with Ensuing Oil Spill
into Turbine Building
Unplanned Intakes by Worker of Transuranic
Airborne Radioactive Materials and External
Exposure Due to Inadequate Control of Work
06/26/97
06/26/97
06/24/97
06/23/97
06/20/97
06/20/97
All holders of OLs or CPs for pressurized-water
reactors
All holders of OLs or CPs for nuclear power reactors.
All holders of licenses for independent spent fuel
storage installations
All holders of OLs or CPs for nuclear power reactors
All industrial radiography licensees
All holders of OLs or CPs for nuclear power reactors
All holders of OLs and CPs permits. All licensees of
of nuclear power reactors
in the decommissioning
stage and fuel cycle
96-53, Supp. 1
97-37
97-36 OL = Operating License
CP = Construction Permit
IN 97-41 June 27, 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:
Jai Rajan, NRR 301-415-2788 E-mail: jrr@nrc.gov
John R. Tappert, NRR 301-415-1167 E-mail: jrt2nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor has reviewed and concurred on 5121/97 DOCUMENT NAME: 97-41.IN
SEE PREVIOUS CONCURRENCES To receive a copy of this document Indicate In the box c=Copy w/o attachmentlendosure E=Copy with attadhmentlendosure
N = No copy
OFFICE
Tech
EMEB*
C:PECB*
D:DRPM
Contacts*
NAME
JRajan
DWessman
AChaffee
MSlosso
_
_
_
_
_ _ _ _
JT a p p e rt_
_
_
_
_
_
_
_
_
_
_
DATE
6/09197
6/09/97
6/16/97
6Z297
/
6/12/97
OFFICIAL RECORD COPY .
^
IN 97-XX
June x, 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:
Jai Rajan, NRR 301-415-2788 E-mail: jrr@nrc.gov
John R. Tappert, NRR 301-415-1167 E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME:G:\\RAJAN\\EDGCOO.LER *SEE PREVIOUS CONCURRENCES
To receive a copy of this document Indicate in the box C=Copy wlo zmnramPnT1PrvInoiirA E=Copy with attachmentlendosure N = No copy
OFFICE
Tech
EMEB*
C:PECB*
D:DRPM
l__Conta_
ct
s*ctl
NAME
JRajan
DWessman
AChaffee
MSlosson
JTappert
DATE
6/09/97
6/09/97
6/16/97
6/ /97
6/12/97 a~~~r~~p.~
A
r.fr
p~
UI-NU;AL Kr-UUKUJ tit Jr'T
&//7/ 7
IN 97-XX
June 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 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:
Jai Rajan, NRR 301-415-2788 E-mail: jrr@nrc.gov
John R. Tappert 301-415-1.167 E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME:G:ARAJAN\\EDGCOO.LER
To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure
Huff -e
E=Copy with attachmentlenclosure N - No copy
OFFICE
Tech
EMEB
CI:PECB
D:DRPM
Contacts
Adf
f
rf
NAME
JRajan
IA
DWessman
AChaffee
MSlosson
JTappert
M71 I I :1 DATE
_6/97
6/7 /97
.1 OFFICIAL
6/ /97 OFFICIAL RECORD COPY
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
