Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical ConditionsML031060622 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
02/24/1994 |
---|
From: |
Grimes B Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-94-014, NUDOCS 9402170298 |
Download: ML031060622 (11) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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 |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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 [[: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 [[: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>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 February 24, 1994 NRC INFORMATION
NOTICE 94-14: FAILURE TO IMPLEMENT
REQUIREMENTS
FOR BIENNIAL MEDICAL EXAMINATIONS
AND NOTIFICATION
TO THE NRC OF CHANGES IN LICENSED OPERATOR MEDICAL CONDITIONS
Addressees
All holders of operating
licenses or construction
permits for nuclear power and non-power
reactors and all licensed reactor operators
and senior reactor operators.
PurDose The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to remind addressees
of the requirements
for licensed reactor operators and senior reactor operators (licensees)
to be examined by a physician
every 2 years and for facility licensees
to notify the NRC of changes in a licensed operator's
physical or mental condition, as determined
by a physician, that cause the operator to fail to meet the medical requirements
of Title 10 of the Code of Federal Regulations
Part 55, "Operators'
Licenses" (10 CFR Part 55).It is expected that recipients
will review the information
for applicability
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.Background
10 CFR 55.21, "Medical examination," requires NRC-licensed
operators
to be examined by a physician
every 2 years. The purpose of this examination
is to determine
if the individual
meets the requirements
of 10 CFR 55.33(a)(1).
Further, 10 CFR 55.23 specifies
that an authorized
representative
of the facility licensee shall complete and sign NRC Form 396, "Certification
of Medical Examination
by Facility Licensee," to certify the medical fitness of the individual.
By signing NRC Form 396, the facility licensee certifies
that (1) the guidance in American Nuclear Society Standard, ANSI/ANS 3.4-1983,"Medical Certification
and Monitoring
of Personnel
Requiring
Operator Licenses for Nuclear Power Plants," was followed in determining
the medical fitness of an operator for power reactors, or (2) the guidance in ANSI/ANS 15.4-1988,"Selection
and Training of Personnel
for Research Reactors," was followed in determining
the medical fitness of an operator for non-power
reactors.
If the guidance in these documents
was not used, a facility licensee may certify that an alternative
method, acceptable
to the NRC, was used.As indicated
in 10 CFR 50.54(i), the facility licensee is responsible
for ensuring that (1) facility controls are manipulated
only by operators
licensed 9402170298 p _T g Vo+fc1eI 91-f' f? ( f0 W IDbV~~ -Ie-//c OAi
--iN 94-14 February 24, 1994 under 10 CFR Part 55 and (2) only operators
so licensed are permitted
to direct manipulation
of the facility controls.
This responsibility
includes ensuring that any conditions
or limitations
to an operator's
license are followed.
Controls in this sense are defined in 10 CFR 55.4 as apparatus
and mechanisms
the manipulation
of which directly affects the reactivity
or power level of the reactor.Description
of Circumstances
During recent inspections
of the implementation
of the above requirements, the NRC determined
that some facility licensees
did not ensure that the restrictions
or limitations
to an operator's
license were followed.
Further, the NRC found examples where facility licensees
failed to notify the NRC of changes in a licensed operator's
medical condition.
An inspection
of licensed operator medical records at the Brunswick
Steam Electric Plant found that a physician
had determined
that (1) the eyesight of four licensed operators
did not meet the medical standards
described
in ANSI/ANS-3.4-1983 and (2) a licensed operator's
medical condition
required that the operator not perform licensee duties alone. These changes in the licensed operators'
conditions
should have been reported to the NRC as required by 10 CFR 55.25. In 1993, NRC inspectors
found 74 instances
at Region III facilities
where licensed operators
had not had a medical examination
within the 2-year period prescribed
by 10 CFR 55.21. In one instance, the time since the last medical examination
exceeded 4 years.Discussion
The responsibility
for ensuring that only personnel
licensed in accordance
with 10 CFR Part 55 are permitted
to manipulate
or direct the manipulation
of the controls of a licensed facility rests with the facility licensee.
The NRC considers
proper certification
to medical standards, as required by 10 CFR 55.23, to be the basis for finding that a licensed operator's
medical condition
and general health will not adversely
affect performance
of assigned operator duties or cause operational
errors that endanger public health and safety. 10 CFR Part 55 Subpart C, "Medical Requirements," states that licensed operators
shall have a medical examination
by a physician
every 2 years. If, during the term of the license, the operator develops a permanent
physical or mental condition
that causes the operator to fail to meet the requirements
of 10 CFR 55.21, the facility licensee shall, in accordance
with 10 CFR 55.25, notify the Commission
within 30 days of learning of the diagnosis.
Deficiencies
were found during NRC inspections
in facility medical examination
programs for applicants
for licenses and for licensed operators.
The results of these inspections
indicate that some facility programs may not be receiving sufficient
management
oversight
to ensure that the medical qualifications
of licensed operators
and applicants
for licenses are maintained
at the required level. This information
notice reminds facility licensees
that, prior to submitting
NRC Form 396, the facility licensee needs to ensure that medical examinations
performed
by physicians
for certifying
the fitness of operators
Att'avthment
IN 94-14 February 24, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 92-36, Supp. I 94-I3 94-12 94-11 Intersystem
LOCA Outside Containment
Unanticipated
and Un-intended Movement of Fuel Assemblies
and Other Components
due to Improper Operation
of Refueling
Equipment Insights Gained from Resolving
Generic Issue 57: Effects of Fire Protection
System Actuation
on Safety-Related Equipment Turbine Overspeed
and Reactor Cooldown during Shutdown Evolution Failure of Motor-Operated
Valve Electric Power Train due to Sheared or Dislodged
Motor Pinion Gear Key Release of Patients with Residual Radioactivity
from Medical Treatment
and Control of Areas due to Presence of Patients Con-taining Radioactivity
Following
Implementation
of Revised 10 CFR Part 20 Potential
for Surveil-lance Testing to Fail to Detect an Inoperable
Main Steam Isolation
Valve 02/22/94 02/22/94 02/09/94 02/08/94 02/04/94 02/03/94 01/01/94 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All U.S. Nuclear Regulatory
Commission
medical licensees.
All holders of OLs or CPs for nuclear power reactors.94-10 94-09 94-08 OL = Operating
License CP -Construction
Permit
K-' \%U-4N 94-14 February 24, 1994 are complete and accurate and that any restriction
or limitation
to an operator's
license resulting
from the examination
is complied with.10 CFR 55.25 requires that the NRC be notified when a licensed operator's
medical condition
no longer meets the original licensing
standard and that an appropriate
certification
form be submitted
if the facility licensee is requesting
a conditional
license to accommodate
the change in the operator's
physical or mental condition.
NRC Information
Notice 91-08, "Medical Examination
for Licensed Operators," February 5, 1991, provides additional
information
on this subject.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 contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Odginal signed by Brian IL Grmes Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: R. J.(610)Conte, RI 337-5210 J. L.(817)Pellet, RIV 860-8159 T. A.(404)M. A.(708)Peebles, R11 331-5541 Ring, RIII 829-9703 P. J. Morrill, RV (510) 975-0293 D. J.(301)Lange, NRR 504-3171 Attachment:
List of Recently Issued NRC Information
Notices SEE PREVIOUS Region I RConte*01/27/94 CONCURRENCE*
Region II TPeebles*01/28/94 Region III MRing*01/27/94 Region IV JPellet*01/25/94 Region V PMorrill*02/02/94 HOLB:DRCH:NRR
DLange*01/26/94 TechEd RSanders*01/13/94 C/HOLB:DRCH:NRR
RGallo*01/24/94 OGCB:DORS:NRR
JBirmingham*
02/03/94 C/ONDD:NRR
SWeiss*01/27/94 AC/OGCB:DORS:NRR
AJKugler*02/07/94 D/DRCH:NRR
BBoger*01/26!/ 9 9-O$7IC/94 OFFICIAL DOCUMENT NAME: 94-14. IN
K...AIN 94-14 February 24, 1994 are complete and accurate and that any restriction
or limitation
to an operator's
license resulting
from the examination
is complied with.10 CFR 55.25 requires that the NRC be notified when a licensed operator's
medical condition
no longer meets the original licensing
standard and that an appropriate
certification
form be submitted
if the facility licensee is requesting
a conditional
license to accommodate
the change in the operator's
physical or mental condition.
NRC Information
Notice 91-08, "Medical Examination
for Licensed Operators," February 5, 1991, provides additional
information
on this subject.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 contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
R. J. Conte, RI J. L. Pellet, RIV (610) 337-5210 (817) 860-8159 T. A. Peebles, R11 P. J. Morrill, RV (404) 331-5541 (510) 975-0293 M. A. Ring, RIII D. J. Lange, NRR (708) 829-9703 (301) 504-3171 Attachment:
List of Recently Issued NRC Information
Notices
/IN 94-XX February X, 1994 It is important
that the NRC be notified when a licensed operator's
medical condition
no longer meets the original licensing
standard and that the facility licensee is requesting
a conditional
license to accommodate
the change in the operator's
physical or mental condition.
NRC Information
Notice 91-08, 'Medical Examination
for Licensed Operators," February 5, 1991, provides additional
information
on this subject.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.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: R. J.(215)Conte, RI 337-5210 J. L.(817)Pellet, RIV 860-8159 T. A.(404)M. A.(708)Peebles, RII 331-5541 Ring, RIII 829-9703 P. J. Morrill, RV (510) 975-0293 D. J.(301)Lange, NRR 504-3171 Attachment:
List of Recently Issued NRC Information
Notices SEE PREVIOUS CONCURRENCE*
Region I Region II RConte TPeebles 01/ /94 01/ /94 Region III MRing 01/ /94 Region IV JPellet*01/24/94 Region V PMorrill 01/ /94 HOLB:DRCH:NRR
DLange*01/26/94 C/HOLB:DRCH:NRR
RGallo*01/24/94 D/DRCH:NRR
BBoger*01/26/94 C/ONDD:NRR
SWei ss 01/ /94 TechEd RSanders 01/13/94 OGCB:DORS:NRR
JBirmingham
01/ /94 C/OGCB:DORS:NRR
GHMarcus 01/ /94 D/DORS:NRR
BKGrimes 01/ /94 OFFICIAL DOCUMENT NAME: MDCLEXAM.JLB
IN 94-XX January, XX, 1994 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.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: R. J. Conte, RI (215) 337-5210 J. L. Pellet, RIV (817) 860-8159 T. A. Peebles, RII (404) 331-5541 P. J.(510)Morrill, RV 975-0293 Lange, NRR 504-3171 M. A.(708)Ring, RIII 829-9703 D. J.(301)Attachment:
List of Recently Issued NRC Information
Notices SEE PREVIOUS CONCURRENCE*
Region I Region II RConte TPeebles 01/ /94 01/ /94 Region III MRing 01/ /94 Region LYAc-Region
V JPelletC"'f6PMorrill
01/xqJ/94
01/ /94 HOLB:DRCIJ:VR
C/HOLB:D DLangej0 ..,j .RGallo*01 A /94L d1 01/24/94 TechEd P OGCB:DORS:NRR
RSandefst*
JBirmingham
01/13/94 01/ /94 RCH:NRR O / /94 C/ONDD:NRR
SWeiss 01/ /94 D/DORS:NRR
BKGrimes 01/ /94 C/OGCB:DORS:NRR
GHMarcus 01/ /94 OFFICIAL DOCUMENT NAME: MDCLEXAM.JLB
j.-1 IN 94-XX January, XX, 1994 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.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: L. H. Bettenhausen, RI 215-337-5291 J. L. Pellet, 817-860-8159 RIV L. L. Lawyer, RII 404-331-4700
M. A. Ring, RII 708-790-5602 P. J. Morrill, 510-975-0293 RV D. J. Lange, NRR 301-504-3171 Attachment:
List of Recently Issued NRC Information
Notices SEE PREVIOUS CONCURRENCE*
Region I Region II LBettenhausen
LLawyer O/ /94 01/ /94 Region III MRing 01/ /94 Region IV JPellet 01/ /94 Region V PMorrill 01/ /94:NRR M0 0 1 /C/HOLB: RES5ERR RGallo MP 01/y294 D/DRCH:NRR
BBoger 01/ /94 C/ONDD:NRR
SWeiss 01/ /94 D/DORS:NRR
BKGrimes 01/ /94 OGC SLewis 01/ /94 TechEd 8 8 RSandergl 01/13/94 OGCB:DORS:NRR
JBirmingham
01/ /94 C/OGCB:DORS:NRR
GHMarcus 01/ /94 OFFICIAL DOCUMENT NAME: MDCLEXAM.JLB
IN 94-XX January, XX, 1994 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.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: R. J.(215)Conte, RI 337-5210 J. L. Pellet, RIV (817) 860-8159 T. A.(404)Peebles, RII 331-5541 P. J.(510)Morrill, RV 975-0293 Lange, NRR 504-3171 M. A. Ring, RIII (708) 829-9703 D. J.(301)Attachment:
List of Recently SEE PREVIOV ON(Region IWjL#RConte 01/247/9 C/HOLB:DRCH:NRR
RGallo*01/24/94 TechEd OGCB: RSanders JBJrm 01/13/94 Xf11/1 Issued NRC Information
Noti Region I TPeebl es 01/1949 Region V a.PMorril I n JX/ /94 -e-- A 9 /21t D/DRCH:NRR
BBoger 01/ /94:DORS:NRI, ni ng ham//%X/94 o01z 7/9 4 C/OGCB:DORS:NRR
D/DORS:NRR
GHMarcus BKGrimes 01/ /94 01/ /94 2.OFFICIAL DOCUMENT NAME: MDCLEXAM.JLB
IN 94-XX February X, 1994 operators
are complete and accurate and that any restriction
or limitation
to an operator's
license resulting
from the examination
is complied with.It is important
that the NRC be notified when a licensed operator's
medical condition
no longer meets the original licensing
standard and that the facility licensee is requesting
a conditional
license to accommodate
the change in the operator's
physical or mental condition.
NRC Information
Notice 91-08, 'Medical Examination
for Licensed Operators," February 5, 1991, provides additional
information
on this subject.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 persons listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: R. J.(610)Conte, RI 337-5210 J. L.(817)Pellet, RIV 860-8159 T. A. Peebles, RII (404) 331-5541 P. J. Morrill, RV (510) 975-0293 D. J. Lange, NRR (301) 504-3171 M. A.(708)Ring, RIII 829-9703 Attachment:
List of Recently Issued NRC Information
Notices SEE PREVIOUS CONCURRENCE*
Region I Region II RConte* TPeebles*01/27/94 01/28/94 Region III MRing*01/27/94 Region IV JPellet*01/25/94 Region V PMorrill*02/02/94 HOLB:DRCH:NRR
DLange*01/26/94 TechEd RSanders*01/13/94 C/HOLB:DRCH:NRR
RGallo*01/24/94 OGCB:DORS:NRR
JBirmingham*
02/03/94 C/ONDD:NRR
SWeiss*01/27/94 AC/OGCB:DORS:NRR
AJKugler J k-02/7/94 D/DRCH:NRR
BBoger*01/26/94 D/DORS:NRR
BKGrimes 02/ /94 OFFICIAL DOCUMENT NAME: MDCLEXAM.JLB
IN 94-14 February 24, 1994 are complete and accurate and that any restriction
or limitation
to an operator's
license resulting
from the examination
is complied with.10 CFR 55.25 requires that the NRC be notified when a licensed operator's
medical condition
no longer meets the original licensing
standard and that an appropriate
certification
form be submitted
if the facility licensee is requesting
a conditional
license to accommodate
the change in the operator's
physical or mental condition.
NRC Information
Notice 91-08, 'Medical Examination
for Licensed Operators," February 5, 1991, provides additional
information
on this subject.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 contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Odginal -tgned by Brian K. Grims Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: R. J. Conte, RI (610) 337-5210 J. L.(817)Pellet, RIV 860-8159 T. A.(404)M. A.(708)Peebles, RII 331-5541 P. J.(510)Morrill, RV 975-0293 Lange, NRR 504-3171 Ring, RIII 829-9703 D. J.(301)Attachment:
List of Recently Issued NRC Information
Notices SEE PREVIOUS CONCURRENCE*
Region I Region II RConte* TPeebles*01/27/94 01/28/94 Region III MRing*01/27/94 Region IV JPellet*01/25/94 Region V PMorrill*02/02/94 HOLB:DRCH:NRR
DLange*01/26/94 TechEd RSanders*01/13/94 C/HOLB:DRCH:NRR
RGallo*01/24/94 OGCB:DORS:NRR
JBirmingham*
02/03/94 C/ONDD:NRR
SWeiss*01/27/94 AC/OGCB:DORS:NRR
AJKugler*02/07/94 D/DRCH:NRR
BBoger*01/26 9 21t/94 OFFICIAL DOCUMENT NAME: 94-14.IN
|
---|
|
list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
---|