Offsite Power Reliability Challenges from Industry DeregulationML031050278 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
02/27/1998 |
---|
From: |
Roe J Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-98-007, NUDOCS 9802240067 |
Download: ML031050278 (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, 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 [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
X 71 C sa'
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 February 27, 1998 NRC INFORMATION NOTICE 98-07: OFFSITE POWER RELIABILITY CHALLENGES FROM
INDUSTRY DEREGULATION
Addressees
All holders of operating licenses for nuclear power reactors except those who have ceased
operations and have certified that fuel has been permanently removed from the vessel.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to a potential concern relating to electric power industry deregulation that could
adversely affect the reliability of offsite power sources, i.e., power from the transmission system
grid to nuclear power plants. 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 to this notice is required.
Description of Circumstances
On July 11, 1989, safety systems at Virgil C. Summer Nuclear Station experienced a sustained
degraded voltage condition and as a result the safety buses were automatically transferred from
the offsite power system to onsite standby diesel generators. The degraded condition was
caused by a turbine trip and deficiencies in the offsite power system's transmission network
equipment. The transfer of power supplies was initiated by operation of degraded voltage
protective relays, as designed. Non-safety system loads remained operable while being powered
for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the degraded offsite power source. (LER 50-395/89-012)
On November 5, 1991, the licensee for Arkansas Nuclear One, Units 1 and 2 reported that, had
its 500kV auto-transformer been lost during summer peak conditions, the 161kV system might
not have been able to maintain adequate voltages to support the operation of the safety system
loads of both units. (LER 50-313/91-010)
On April 15, 1992, Northeast Nuclear Energy Company reported that under certain operating
conditions of the transmission network (i.e., during heavy load conditions), a failure of
transmission system equipment may cause a trip of all three Millstone units and a loss of offsite
power to the station. This operating condition was precipitated by the economic displacement
of oil-fired generating units by non-utility generators and by the addition of other generating
capacity (Seabrook and Hydro-Quebec) to the transmission network. (LER 50-245/92-020)
?PD 1re-F Normf, 1g-0o7 80a.2 7 q~ r 1l~lill~lill~lill~lililuill1!\i
IN -07 February 27, 1998 On April 14, 1993, Wisconsin Public Service Corporation reported that under certain transmission
line contingencies, a potential existed for the Kewaunee Nuclear Power Plant grid to become
unstable and cause all offsite power sources into the plant to trip. (Ref: LER 50-305/93-010)
On December 30, 1993, Northeast Nuclear Energy Company reported that under certain
operating conditions of the transmission network (i.e., Millstone Units 2 and 3 off line), the
transmission network may not have sufficient capacity to permit the continued operation of safety
system loads from offsite sources following a trip of Millstone Unit 1. (LER 50-245/94-001)
On August 8, 1995, Pacific Gas and Electric Company (PG&E) reported that under certain
operating conditions (i.e., a high system load with a specific 230kV transmission line out of
service), the transmission network may not have sufficient capacity to permit the continued
operation of the safety system loads from offsite sources following a trip of one of the two Diablo
Canyon units. (Ref: LER 50-275/95-007)
On August 10, 1996, a transmission line sagged into a tree in Oregon creating a ground fault that
progressed into a major fault on the western Interconnection. The subsequent transient resulted
in the tripping of both Diablo Canyon, Units 1 and 2 (LER 50-275/96-012) and Palo Verde, Units 1 and 3 (LER 50-528/004).
During the summer of 1997, concerns were expressed about the impact of electric peak
conditions on the offsite power sources for nuclear power plants located in the Midwest and
New England. In addition, the licensee for Clinton nuclear station sought an exemption from
offsite power regulatory requirements because of its analysis that offsite power would become
inadequate under certain summer peak conditions following the loss of the nuclear unit.
Recent NRC inspection findings and Licensee Event Reports have indicated instances when grid
stability analyses had not been updated by the licensees to reflect changes in the grid power
system. Office for Analysis and Evaluation of Operational Data study C97-01, "Grid Performance
Factors" dated March 20, 1997, identified a Oneed to monitor grid conditions on a regular basis."
Discussion
In 1988, NRC issued the station blackout (SBO) rule. The requirements of 10 CFR 50.63, "Loss
of All Alternating Current Power," specify that each light-water-cooled nuclear power plant be
able to withstand and recover from an SBO (i.e., a loss of offsite and onsite emergency ac power
sources) for a specified period. The NRC review of licensees' analyses to assess the
vulnerability of offsite power and the time required for recovery indicated that for most nuclear
power plant sites the grid was stable and reliable.
Historically, grid control is decentralized and each utility or a small group of utilities forms a
control area containing customers for which it Is jurisdictionally responsible. The control areas
form reliability councils that establish operating standards by consensus. These agreements, in
turn, became the factors that determine the reliability of the grid and the bases for the availability
of the offsite power system. Although the grid operating standards that evolved in the past
provided reasonable grid reliability, events like those discussed herein reveal vulnerabilities of
the electrical grid either through actual challenges or through licensee's analyses to assess the
adequacy of the offsite power system.
INS '7 Feb,--dry 27, 1998 The present grid management may be dismantled or restructured by two factors that are
emerging: non-utility generation and deregulation. It Is anticipated that in the future, power
suppliers, whether utilities or independent power producers, will actively compete for sales to
customers who may be located anywhere on the power grid. This option creates multiple
combinations of generating units going on and off the grid based on economic and performance
related consequences. Regional grid control could be the responsibility of centralized
independent system operators (ISOs). The responsibilities and authority of an ISO are yet to be
defined, but It is expected that the ISO, or a similar entity, will be charged with maintaining grid
reliability to facilitate the marketing of power. It is uncertain how the historic mechanisms for
reliable operation will change under the new grid operational structure. The Department of
Energy has sponsored a Task Force on Electric System Reliability to examine the implications of
industry deregulation on the Nation's electric power supply.
The capacity and capability of the offsite power system for each nuclear power plant could be
significantly influenced by the decisions emerging from these forthcoming changes. Since the
capability of the offsite power cannot be tested except when challenged in an actual event, the
design bases of the offsite power can only be assured through an enveloping analysis that
accounts for the full spectrum of grid loading and transient conditions that support the operability
of safety systems. The NRC Standard Review Plan Section 8.2 provides current guidance for
assessing the adequacy of the offsite power system. It addresses grid analyses that
demonstrate acceptable voltage and frequency when subjected to scenarios involving loss of
nuclear unit generation, loss of the largest other unit, or loss of the most critical transmission line.
Although the above events discussed may not demonstrate present generic weaknesses in
licensees' processes, it is vital that licensees continue to ensure that the design bases with
respect to the reliability and stability of the offsite power sources do not degrade during the life of
the nuclear facility. The capacity and capability of the offsite power system for nuclear power
plants are important elements to be factored into the management of the changes resulting from
industry deregulation.
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.
orig /s/'d by
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Ronaldo V. Jenkins, NRR Thomas Koshy, NRR
301415-2985 301415-1 176 E-Mail: rvj2nrc.gov E-Mail: txk@nrc.gov
A-1T E~A FiL ;1 JAckETF
Attachment: Ust of recently issued Information Notices
OGC Concurrence (R. K Hoefling) 214198, PGEB Id 2/17198 (T. Essig),
AEOD Idc 2/12/98 (E.Rossi) & Tech Editor 1/27/98 DOCUMENT NAME: S:%DRPM SEC\98-07.IN - SEE PREVIOUS CONCURRENCE
To receive a copy of Nhis document, Indicate Inthe box C=Copy wlo attachmentlenclosure E=Copy with attachmenUendosure N =No copy l
OFFICE PECB I EELB I IEELB I PECB PECB LI DRPM A
NAME TKoshy* RJenkins* JCalvo* RDennig* SRichards* JRoe*
DATE 2/2/98 j 2/2/98 j 2/2/98 2/10/98 2/11/98 2/17/98 OFFICIAL RECORD COPY
Attachment
IN 98-07 February 27, 1998 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
98-06 Unauthorized Use of Ucense to 2/19198 All NRC licensees authorized to
Obtain Radioactive Materials, possess licensed material
And Its Implications Under The
Expanded Title 18 of the
U.S. Code
97-45, Supp. 1 Environmental Qualification 2/17/98 All holders of operating
Deficiency for Cables and licenses for nuclear power
Containment Penetration reactors except those licensees
Pigtails who have permanently ceased
operations and have certified that
the fuel has been permanently
removed from the reactor vessel
98-05 Criminal History Record 2111/98 All holders of operating
Information licenses for power reactors
98-04 1997 Enforcement Sanctions for 2/9/98 All U.S. Nuclear Regulatory
deliberate Violations of NRC Commission licensees
Employee Protection requirements
98-03 Inadequate Verification of 1/21/98 All holders of operating licenses
Overcurrent Trip Setpoints in for nuclear power reactors
Metal-Clad, Low-Voltage
Circuit Breakers
98-02 Nuclear Power Plant Cold 1/21/98 All holders of operating licenses
Weather Problems and for nuclear power reactors
Protective Measures
98-01 Thefts of Portable Gauges 1/15/98 All portable gauge licensees
97-91 Recent Failures of Control 12/31/97 All industrial radiography
Cables Used on Amersham licensees
Model 660 Posilock Radiography
Systems
97-90 Use of Nonconservative 12/30/97 All holders of OLs for nuclear
Acceptance Criteria in power reactors except those
Safety-Related Pump who have ceased operations
Surveillance Tests and have certified that fuel has
been permanently removed from
the vessel
OL = Operating License
CP = Construction Permit
IN9' Y
, Feb~Uyxx, 1998 The present grid management may be dismantled or restructured by two factors that are
emerging: non-utility generation and deregulation. It Is anticipated that in the future, power
suppliers, whether utilities or independent power producers, will actively compete for sales to
customers who may be located anywhere on the power grid. This option creates multiple
combinations of generating units going on and off the grid based on economic and performance
related consequences. Regional grid control could be the responsibility of centralized
independent system operators (ISOs). The responsibilities and authority of an ISO are yet to be
defined, but it Is expected that the ISO, or a similar entity, will be charged with maintaining grid
reliability to facilitate the marketing of power. It is uncertain how the historic mechanisms for
reliable operation will change under the new grid operational structure. The Department of
Energy has sponsored a Task Force on Electric System Reliability to examine the implications of
industry deregulation on the Nation's electric power supply.
The capacity and capability of the offsite power system for each nuclear power plant could be
significantly influenced by the decisions emerging from these forthcoming changes. Since the
capability of the offsite power cannot be tested except when challenged in an actual event, the
design bases of the offsite power can only be assured through an enveloping analysis that
accounts for the full spectrum of grid loading and transient conditions that support the operability
of safety systems. The NRC Standard Review Plan Section 8.2 provides current guidance for
assessing the adequacy of the offsite power system. It addresses grid analyses that
demonstrate acceptable voltage and frequency when subjected to scenarios Involving loss of
nuclear unit generation, loss of the largest other unit, or loss of the most critical transmission line.
Although the above events discussed may not demonstrate present generic weaknesses in
licensees' processes, it is vital that licensees continue to ensure that the design bases with
respect to the reliability and stability of the offsite power sources do not degrade during the life of
the nuclear facility. The capacity and capability of the offsite power system for nuclear power
plants are important elements to be factored into the management of the changes resulting from
industry deregulation.
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.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Ronaldo V. Jenkins, NRR Thomas Koshy, NRR
301-415-2985 301-415-1176 E-Mail: rvjenrc.gov E-Mail: txk@nrc.gov
Attachment: List of recently issued Information Notices
OGC Concurrence (R. K Hoefling) 2/4198 DOCUMENT NAME: G:ITXK\GRIDIN2.1WPD - 'SEE PREVIOUS CONCURRENCE
To receive a copy of this document indicate Inthe box C=Copy wlo aftachmentlenclosure E d: .ATo osure N = No copy
[OFFICE lPECB lI EELB 1 _ EELB l PECB lI PECB I DRPM
NAME TKoshy* RJenkins* JCalvo* RDennig* lSRichards'Jle
l DATE j 2/2/98
_J___A_
[2/2/98 .
2/2/98 j 2/10/98 l-;1 /98
18-
1/98
1/ 8--
OFFICIAL RECORD COPY t CM I
Tre
ING' x
Febkty xx, 1998 The present grid management may be dismantled or restructured by two factors that are
emerging: non-utility generation and deregulation. It is anticipated that in the future, power
suppliers, whether utilities or Independent power producers, will a6tively compete for sales to
customers who may be located anywhere on the power grid. This option creates multiple
combinations of generating units going on and off the grid based on economic and performance
related consequences. Regional grid control could be the responsibility of centralized
independent system operators (ISOs). The responsibilities and authority of an ISO are yet to be
defined, but it is expected that the ISO, or a similar entity, will be charged with maintaining grid
reliability to facilitate the marketing of power. It is uncertain how the historic mechanisms for
reliable operation will change under the new grid operational structure. The Department of
Energy has sponsored a Task Force on Electric System Reliability to examine the implications of
industry deregulation on the Nation's electric power supply.
The capacity and capability of the offsite power system for each nuclear power plant could be
significantly influenced by the decisions emerging from these forthcoming changes. Since the
capability of the offsite power cannot be tested except when challenged in an actual event, the
design bases of the offsite power can only be assured through an enveloping analysis that
accounts for the full spectrum of grid loading and transient conditions that support the operability
of safety systems. The NRC Standard Review Plan Section 8.2 provides current guidance for
assessing the adequacy of the offsite power system. It addresses grid analyses that
demonstrate acceptable voltage and frequency when subjected to scenarios involving loss of
nuclear unit generation, loss of the largest other unit, or loss of the most critical transmission line.
Although the above events discussed may not demonstrate present generic weakness in
licensees' process, it is vital that licensees continue to ensure that the design bases with respect
to the reliability and stability of the offsite power sources do not degrade during the life of the
nuclear facility. The capacity and capability of the offsite power system for nuclear power plants
are important elements to be factored into the management of the changes resulting from
industry deregulation.
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.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Ronaldo V. Jenkins, NRR Thomas Koshy, NRR
301-415-2985 301-415-1176 E-Mail: rvjenrc.gov E-Mail: txk@nrc.gov
Attachment: List of recently issued Information Notices
OGC Concurrence (R. K Hoefling) 2/4/98 DOCUMENT NAME: G:ITXK\GRIDIN2.1WPD - SEE PREVIOUS CONCURRENCE
To receive a copy of this document, idicate hithe box C=Copy wlo attachmentlenclosure E=Copy with attachmentlenclosure N = No copy
lOFFICE PECB I EELB _L EELB I - PECB l- DRPM_
NAME TKoshyl RJenkins* JCalvo* gnig ~ SRichards JRoe
l DATE I /== 2/2/9f 12/219°B9%
i ,I l I / I9t
OFFICIAL RECORD COPY
IN "x
February xx, 1998 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.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Ronaldo V. Jenkins, NRR
301-415-2985 E-Mail: rvjenrc.gov
Thomas Koshy, NRR
301-415-1176 E-Mail: txkenrc.gov
Attachment: List of recently issued Information Notices
DOCUMENT NAME: G:\TXKAGRIDIN2.1WPD
To receive a copy of this document, indicate in the box C=Copy wlo atachment/enclosure E=Copy with attachment/enclosure N = No copy
OFFICE l PECB lEELB EELB El I PECB I PECB l lDRPMl
NAME s RJenkins JCalvo /1 RDennig SRichards JRoe
l DATE 121249 I L,-,9l 212/t9 I / , II,9 , / W
OFFICIAL RECORD COPY
|
---|
|
list | - Information Notice 1998-01, Thefts of Portable Gauges (15 January 1998, Topic: Shutdown Margin, Moisture Density Gauge, Stolen)
- Information Notice 1998-02, Nuclear Power Plant Cold Weather Problems and Protective Measures (21 January 1998)
- Information Notice 1998-03, Inadequate Verification of Overcurrent Trip Setpoints in Metal-Clad, Low-Voltage Circuit Breakers (21 January 1998)
- Information Notice 1998-04, 1997 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements (9 February 1998)
- Information Notice 1998-05, Criminal History Record Information (11 February 1998)
- Information Notice 1998-06, Unauthorized Use of License to Obtain Radioactive Materials, and Its Implication Under the Expanded Title 18 of the U.S. Code (19 February 1998)
- Information Notice 1998-07, Offsite Power Reliability Challenges from Industry Deregulation (27 February 1998)
- Information Notice 1998-08, Information Likely to Be Requested If an Emergency is Declared (2 March 1998)
- Information Notice 1998-08, Information Likely to Be Requested If an Emergency Is Declared (2 March 1998)
- Information Notice 1998-09, Collapse of an Isocam II, Dual-Headed Nuclear Medicine Gamma Camera (5 March 1998)
- Information Notice 1998-10, Probable Misadministrations Occurring During Intravascular Brachytherapy with Novoste Beta-cath System (9 March 1998, Topic: Brachytherapy)
- Information Notice 1998-11, Cracking of Reactor Vessel Internal Baffle Former Bolts in Foreign Plants (25 March 1998, Topic: Fire Barrier, Brachytherapy)
- Information Notice 1998-12, Licensees' Responsibilities Regarding Reporting & Follow-up Requirements for Nuclear-Powered Pacemakers (3 April 1998, Topic: Fire Barrier, Brachytherapy, Stolen)
- Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality (20 April 1998, Topic: Fire Barrier, VT-2, Pressure Boundary Leakage, Brachytherapy)
- Information Notice 1998-14, Undocumented Changes to Non-Power Reactor Safety System Wiring (20 April 1998, Topic: Brachytherapy)
- Information Notice 1998-15, Integrity of Operator Licensing Examinations (20 April 1998, Topic: Fire Barrier, Job Performance Measure)
- Information Notice 1998-16, Inadequate Operational Checks of Alarm Ratemeters (30 April 1998, Topic: Brachytherapy)
- Information Notice 1998-17, Federal Bureau of Investigation'S (FBI) Awareness of National Security Issues and Response (ANSIR) Program (7 May 1998)
- Information Notice 1998-17, Federal Bureau of Investigation'S (FBI) Awareness of National Security Issues and Response (Ansir) Program (7 May 1998, Topic: Brachytherapy)
- Information Notice 1998-18, Recent Contamination Incidences Resulting from Failure to Perform Adequate Surveys (13 May 1998, Topic: Brachytherapy)
- Information Notice 1998-19, Shaft Binding in General Electric Type Sbm Control Switches (3 June 1998)
- Information Notice 1998-20, Problems with Emergency Preparedness Respiratory Protection Programs (3 June 1998, Topic: Brachytherapy)
- Information Notice 1998-21, Potential Deficiency of Electrical Cable/Connection Systems (4 June 1998)
- Information Notice 1998-22, Deficiencies Identified During NRC Design Inspections (17 June 1998, Topic: Stroke time, Tornado Missile)
- Information Notice 1998-23, Crosby Relief Valve Setpoint Drift Problems Caused by Corrosion of Guide Ring (23 June 1998, Topic: Loop seal, Condition Adverse to Quality)
- Information Notice 1998-25, Loss of Inventory from Safety-Related Closed-Loop Cooling Water Systems (8 July 1998, Topic: Ultimate heat sink)
- Information Notice 1998-26, Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations (24 July 1998, Topic: Condition Adverse to Quality)
- Information Notice 1998-27, Steam Generator Tube End Cracking (24 July 1998)
- Information Notice 1998-28, Development of Systematic Sample Plan for Operator Licensing Examinations (31 July 1998)
- Information Notice 1998-29, Predicted Increase in Fuel Rod Cladding Oxidation (3 August 1998, Topic: Fuel cladding)
- Information Notice 1998-30, Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders (12 August 1998, Topic: Brachytherapy)
- Information Notice 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2 (18 August 1998)
- Information Notice 1998-33, NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities (28 August 1998, Topic: Brachytherapy)
- Information Notice 1998-34, Configuration Control Errors (28 August 1998)
- Information Notice 1998-36, Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems (18 September 1998)
- Information Notice 1998-37, Eligibility of Operator License Applicants (1 October 1998)
- Information Notice 1998-38, Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections (15 October 1998, Topic: Overtravel)
- Information Notice 1998-39, Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 1997 (30 October 1998, Topic: Fitness for Duty)
- Information Notice 1998-40, Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents (26 October 1998)
- Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators From Design Oversight (20 November 1998)
- Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators from Design Oversight (20 November 1998)
- Information Notice 1998-42, Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements (1 December 1998)
- Information Notice 1998-43, Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping (4 December 1998)
- Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping (10 December 1998, Topic: Probabilistic Risk Assessment)
- Information Notice 1998-45, Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds (15 December 1998)
|
---|