Switchyard Problems That Contribute to Loss of Offsite PowerML031190398 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
12/16/1991 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-91-081, NUDOCS 9112110011 |
Download: ML031190398 (9) |
|
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>. |
K>
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 December 16, 1991 NRC INFORMATION NOTICE 91-81: SWITCHYARD PROBLEMS THAT CONTRIBUTE TO
LOSS OF OFFSITE POWER
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice
to alert addressees to several problems associated with plant switchyards. 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 require- ments; therefore, no specific action or written response is required.
Description of Circumstances
On April 23, 1991, a complete loss of offsite power occurred at the Vermont
Yankee Nuclear Power Station as a result of maintenance activities in the
switchyard. Maintenance workers were installing a new battery for one of the
two non-lE 125 VDC buses. The two normally independent buses were cross tied
through the swing battery charger 4A-5A after defeating a mechanical interlock
(Figure 1). Furthermore, the licensee was paralleling the battery chargers
on bus DC-4A without a battery on this bus. When the 4A-5A battery charger
output breaker feeding bus DC-5A was opened prior to connection of the new
battery 4A to bus DC-4A, a voltage transient propagated through the switchyard
DC control system that caused all but one of the 345kV and 115kV circuit
breakers to trip and lock open. The loss of offsite power which occurred
caused a main turbine and automatic reactor trip. Restoration of full offsite
power took thirteen hours.
The NRC dispatched an augmented inspection team (AIT) to investigate this
event, and the following generic concerns were identified by the team in its
report (50-217/91-13): (1) a lack of preventive maintenance on battery
chargers, (2) presence of sensitive components in logic cards making them
susceptible to failure, (3) switchyard protective relays that were susceptible
to a single failure, and (4) a lack of clear authority over the switchyard
during emergency conditions.
9112110011 /
v)
page 2 of 3
- - .... , Anntpriance char
Lack of Preventive ,-- - switchyard
chargers (4A, B, and 4A-5A) in the fn
Three of the four
non-lE battery
condition at the time of the event. filter
in a degraded the output
DC control system werebattery chargers, manufactured by Exidf, fuses in one iiter
each of the degraded The problems included blown capacitor *inthe
was not functional. another, and a failed
circuit
blown and wrong-sized fuses
in
charger output filter circuit r.ad
circuit, If the 4A-5A battery have been m(itigate
third filter circuit. effect of the voltage transient may problems resultCC
The
been functional, the power might have been prevented. battery chargers.
IlTe
and loss of offsite maintenance on the
preventive and it appeared
directly from infrequent maintenance program for the chargers battery chargers aigre
licensee had no regular in 1985. These is
was performed
that the last maintenance testing or preventive maintenance includit.u
and no surveillance system, not safety related at this facility, the switchyard battery associated distribu- and
required. However, their associated chargers, thequitchyard batteries, auxiliary electrical power system
and is required
is part of the
tion panels, plant's Technical Specifications.
to be operable by the
in Logic Cards
Sensitive Components
switchyard DC control 'y"u,, .baI_ . v circuit breakers
The voltage spike in the of two switchyard ard
failure units (SBFUS) breakers in the by AREA
-4zks
in the stuck breaker reaction that caused most of the are manufactured
which led to a chain to trip and lock open. These
SBFUs
Electric
115kV switchyard previous models were made by the Westinghouse
and units that are not as suscep- Brown Boveri, has developed new
zener diodes.
Corporation. The manufacturer because the new units do not contain
tible to voltage spikes
Failure
Relays Subject to a Single t%.,
Protective
from a single bus (DC-4A) even though a
are powered This desig.
All of the SBFU relays in the switchyard DC control system. similar proteccti;-
DC buses are available failure. Other facilities may havecause failure.
subject to a single could be vulnerable
to a common
relaying designs that
Coditions
c-..4+,4iiizrnrd Under Emergenc
a lack of coIrmunications
power was delayed because of (T&D) personnel.
offsite
The restoration of and the transmission and distribution the switchyard. The
between plant staff T&D is responsible
for operating
conditions, the responsi- Under normal that, under emergency conditions, does not
specifies the procedure
licensee's procedure to the plant staff. However, suggest the need to clarify
bility is transferred problems
These operational other emergency condi- define "emergency." during a loss of offsite power or
switchyard authority switchyard activities
are important.
tions when timely
Problems
Example of Switchyard Communication
Additional can be seen in Ar
problems in the switchyard Unit i, on
Another example of
communication Nuclear Generating Station, at the McGuire T&D personnel caused
event that took placeThe unit tripped from 100% power when
February 11, 1991.
v>
IN 91-81 December 16, 1991 a loss of all offsite power while testing a modification to the protective
relay circuitry in the 230 kV switchyard. Since the majority of the switchyard
is outside of the plant equipment boundary, the T&D personnel did not notify
the station operations personnel that work was in progress even though switch- yard activities can impact the station. Prior to this event there was no
agreement between station operations and T&D personnel on how to handle switch- yard activities outside the plant equipment boundary. Subsequent to this
event, a work control policy was established to provide improved communication
between the station operations personnel and T&D personnel.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the technical
contacts listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
arles E. Rossi Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Cliff Anderson, Region I
(215) 337-5376 Peter Kang, NRR
(301) 504-0779 David Skeen, NRR
(301) 504-1174 Attachments:
1. Figure 1: Switchyard House DC Distribution
One Line Diagram
2. List of Recently Issued NRC Information Notices
BUS 8 BUS 11 I - -1 - - - - - - --- I
I )-ldTL .) I
I I I
I %I a1 Io I. ,n 1 LMECHAN ICAL
- - --- , INTERLOCK-
)16 )3 )I8 I I )30 32
1)SI
DC DISTRIBUTIOw PANEL OC-SA - OISTRf8UT ION PANEL DC-4A
SIYD BATT SWYDBATT
SA 4A (
0D
M f0Co
Figure 1 Switchyard House DC Distribution One Line Diagram (D CIO
'0 D
K)
Attachment 2 IN 91-81 December 16, 1991 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
I tformation Date of
Notice to. Subject Issuance Issued to
91-80 Failure of Anchor 12/11/91 All holders of OLs or CPs
Head Threads on Post- for nuclear power reactors.
Tensioning System During
Surveillance Inspection
9I-79 Deficiencies in the 12/06/91 All holders of OLs or CPs
Procedures for Instal- for nuclear power reactors.
ling Thermo-Lag Fire
Barrier Materials
88-92, Potential for Spent 11/29/91 All holders of OLs or CPs
Supp. 1 Fuel Pool Draindown for nuclear power reactors.
Status Indication of 11/28/91 All holders of OLs or CPs
Control Power for for nuclear power reactors.
Circuit Breakers Used
in Safety-Related Appli- cations
9j-57, Substandard, Refur- 11/27/91 All holders of OLs or CPs
S..pp. 1 bished Potter & Brum- for nuclear power reactors.
field Relays Repre- sented as New
01 -77 Shift Staffing at 11/26/91 All holders of OLs or CPs
Nuclear Power Plants for nuclear power reactors.
91-76 10 CFR Parts 21 and 11/26/91 All holders of OLs or CPs
50.55(e) Final Rules and vendors for nuclear
power reactors.
91-75 Static Head Corrections 11/25/91 All holders of OLs or CPs
Mistakenly not Included for nuclear power reactors.
in Pressure Transmitter
Calibration Procedures
91-74 Changes in Pressurizer 11/25/91 All holders of OLs or CPs
Safety Valve Setpoints for nuclear power reactors.
Before Installation
OL = Operating License
CP = Construction Permit
IN 91-81 December 16, 1991 a loss of all offsite power while testing a modification to the protective
relay circuitry in the 230 kV switchyard. Since the majority of the switchyard
is outside of the plant equipment boundary, the T&D personnel did not notify
the station operations personnel that work was in progress even though switch- yard activities can impact the station. Prior to this event there was no
agreement between station operations and T&D personnel on how to handle switch- yard activities outside the plant equipment boundary. Subsequent to this
event, a work control policy was established to provide improved communication
between the station operations personnel and T&D personnel.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the technical
contacts listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager. Orgnal Signid by
Charles E. Rossi, Director Charles E.Rossi
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Cliff Anderson, Region I
(215) 337-5376 Peter Kang, NRR
(301) 504-0779 David Skeen, NRR
(301) 504-1174 Attachments:
1. Figure 1: Switchyard House DC Distribution
One Line Diagram
2. List of Recently Issued NRC Information Notices
OFC :*OEAB:NRR : *RI :*SC:OEAB:NRR:*ADM:RPB :*C:SELB:NRR :*C:OEAB:NRR
_____ _____ __ _ _ ____________ ____ - ------
NAME :DSkeen : CAnderson :RDennig :JMain :FRosa :AChaffee
____________ ------------ ______ __ __ ____________ - ------
_____
DATE :10/01/91 : 10/01/91 :11/05/91 :10/01/91 :11/05/91 :11/14/91 OFC :*C:OGCB:NRR :D:DOEA :
___----- ------- :-- -- ?- ---------- :------------:------------ ------------ -------
NAME :CBerlinger : :
DATE :11/25/91 :12////91 OFFICIAL RECORD COPY
Document Name: IN 91-81
IN 91-XX
November xx, 1991 there was no agreement between station operations and T&D personnel on how to
handle switchyard activities outside the plant owned equipment boundaries.
Subsequent to this event, a work control policy was established to provide
improved communication between the station operations personnel and T&D
personnel.
The staff is providing this information as an early notification of a matter
that could become significant and that the NRC staff is continuing to consider.
Upon completing its evaluation, the staff may require licensees to take
specific actions. No specific action or written reponse is required by this
information notice. If you have any questions about this matter, please contact
the technical contacts below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Cliff Anderson, Region I
(215) 337-5376 Peter Kang, NRR
(301) 492-0779 David Skeen, NRR
(301) 492-1174 Attachment:
1. Figure 1: Switchyard House DC Distribution
One Line Diagram
2. List of Recently Issued NRC Information Notices
OFC :*OEAB:NRR : *RI :*SC:OEAB:NRR:*ADM:RPB :*C:SELB:NRR :*C:OEAB:NRR
_____ ____________ - ----------- ____________ ____________ ____________ - ------
NAME :DSkeen : CAnderson :RDennig :JMain :FRosa :AChaffee :
DATE :10/01/91 : 10/01/91 :11/05/91 :10/01/91 :11/05/91 :11/14/91
OFC :C: UP, Y :D:DOEA
NAME :CBerlinger :CRossi I::
DATE : 1;/I91 : / /91 OFFICIAL RECORD COPY
Document Name: IN/SWITCHYARD/SKEEN
IN 91-XX
October xx, 1991 The staff is providing this information as an early notification of a matter
that could become significant and that the NRC staff is continuing to consider.
Upon completing its evaluation, the staff may require licensees to take
specific actions. No specific action or written reponse is required by this
information notice. If you have any questions about this matter, please contact
the technical contacts below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Cliff Anderson, Region I
(215) 337-5376 Peter Kang, NRR
(301) 492-0779 David Skeen, NRR
(301) 492-1174 Attachment: List of Recently Issued NRC Information Notices
OFC :*OEAB:NRR : *RI :S :NRR :*ADM:RPB :C:SELB.4NRR :C:OpAB:NRR :
- Rb g :------------n:F---o : f_-------- ------
NAME :DSkeen : CAnderson :Re~ig rJai c~oa :AChaffee :
- ,-- -- - : -- - ------- :- - -
__ -:--- ---_-_ _-__ - - - __-___
- _
DATE :10/01/91 : 10/01/91 :// / As /91 :10/01/91 : 1 /$/91 : [(//K/91 OFC :C:OGCB:NRR :D:DOEA :
NAME :CBerlinger :CRossi :
DATE : / /91 : / /91 :
OFFICIAL RECORD COPY
Document Name: IN/SWITCHYARD/SKEEN
No specific action or written reponse is required by this information notice.
If you have any questions about this matter, please contact the technical
contacts below or the appropriate Office of Nuclear Reactor Regulation project
manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Cliff Anderson, Region I
(215) 337-5376 Peter Kang, NRR
(301) 492-0779 David Skeen, NRR
(301) 492-1174 Attachment: List of Recently Issued NRC Information Notices
pfr TGLECoA
OFC :OEAB:NRR : RI :SC:OEAB:NRR :ADM:RPB :C:SELB:NRR :C:OEAB:NRR
____---- ------ --- " - tF------------ :------------ :------------ :------------:---
NAME :DSkeen j : CAnderson :RDennig :JMain - 9 :FRosa :AChaffee
DATE :/O/ 1/91 : 0/ //91 : / /91 :10/1 /91 : / /91 : / /91 OFC :C:OGCB:NRR :D:DOEA :
NAME :CBerlinger :CRossi : : :
DATE: / /91 : / /91 : :
OFFICIAL RECORD COPY
Document Name: IN/SWITCHYARD/SKEEN
|
---|
|
list | - Information Notice 1991-01, Supplier of Misrepresented Resistors (4 January 1991, Topic: Fitness for Duty)
- Information Notice 1991-02, Brachytherapy Source Management (7 January 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-03, Management of Wastes Contaminated with Radioactive Materials (Red Bag Waste & Ordinary Trash) (7 January 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-04, Reactor Scram Following Control Rod Withdrawal Associated with Low Power Turbine Testing (28 January 1991, Topic: Fitness for Duty)
- Information Notice 1991-05, Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles (30 January 1991, Topic: Fitness for Duty, Hydrostatic, Liquid penetrant)
- Information Notice 1991-06, Lock-up of Emergency Diesel Generator and Load Sequencer Control Circuits Preventing Restart of Tripped Emergency Diesel Generator (31 January 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-07, Maintenance Deficiency Associated with General Electric Horizontal Custom 8000 Induction Motors (4 February 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-08, Medical Examinations for Licensed Operators (5 February 1991, Topic: Brachytherapy)
- Information Notice 1991-09, Counterfeiting of Crane Valves (25 September 2007)
- Information Notice 1991-10, Summary of Semiannual Program Performance Reports on Fithess-For-Duty (FFD) in the Nuclear Industry (12 February 1991)
- Information Notice 1991-12, Potential Loss of Net Positive Suction Head (NPSH) of Standby Liquid Control System Pumps (15 February 1991)
- Information Notice 1991-13, Inadequate Testing of Emergency Diesel Generators (Edgs) (4 March 1991)
- Information Notice 1991-13, Inadequate Testing of Emergency Diesel Generators (EDGs) (4 March 1991)
- Information Notice 1991-14, Recent Safety-Related Incidents at Large Irradiators (5 March 1991, Topic: Fitness for Duty, Coatings, Incorporated by reference, Brachytherapy, Uranium Hexafluoride)
- Information Notice 1991-15, Incorrect Configuration of Breaker Operating Springs in General Electric AK-Series Metal-Clad Circuit Breakers (6 March 1991)
- Information Notice 1991-16, Unmonitored Release Pathways from Slightly Contaminated Recycle and Recirculation Water Systems at a Fuel Facility (6 March 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-17, Fire Safety of Temporary Installation or Services (11 March 1991)
- Information Notice 1991-18, High-Energy Piping Failures Caused by Wall Thinning (18 December 1991)
- Information Notice 1991-19, Steam Generator Feedwater Distribution Piping Damage (12 March 1991)
- Information Notice 1991-20, Electrical Wire Insulation Degradation Caused Failure in a Safety-Related Motor Control Center (19 March 1991)
- Information Notice 1991-21, Inadequate Quality Assurance Program of Vendor Supplying Safety-Related Equipment (19 March 1991)
- Information Notice 1991-22, Four Plant Outage Events Involving Loss of AC Power or Coolant Spills (19 March 1991)
- Information Notice 1991-23, Accidental Radiation Overexposures to Personnel Due to Industrial Radiography Accessory Equipment Malfunctions (26 March 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-24, Recent Operating Experience Involving Reactor Operation Without a Licensed Reactor Operator or Senior Reactor Operator Present in the Control Room (26 March 1991)
- Information Notice 1991-25, Commercial-Grade Structural Framing Components Supplied As Nuclear Safety-Related Equipment (1 April 1991)
- Information Notice 1991-25, Commercial-Grade Structural Framing Components Supplied as Nuclear Safety-Related Equipment (1 April 1991)
- Information Notice 1991-26, Potential Nonconservative Errors in the Working Format Hansen-Roach Cross-Section Set Provided with Keno and Scale Codes (2 April 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-27, Incorrect Rotation of Positive Displacement Pump (10 April 1991)
- Information Notice 1991-28, Cracking in Feedwater System Piping (15 April 1991)
- Information Notice 1991-29, Deficiencies Identifie During Electrical Distribution System Functional Inspections (15 April 1991)
- Information Notice 1991-30, Inadequate Calibration of Thermoluminescent Dosimeters Utilized to Monitor Extremity Dose at Uranium Processing and Fabrication Facilities (23 April 1991, Topic: Brachytherapy, Uranium Hexafluoride)
- Information Notice 1991-31, Nonconforming Magnaflux Magnetic Particle (14AM) Prepared Bath (9 May 1991)
- Information Notice 1991-32, Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering (15 May 1991, Topic: Hot Short, Liquid penetrant)
- Information Notice 1991-33, Reactor Safety Information for States During Exercises and Emergencies (31 May 1991)
- Information Notice 1991-34, Potential Problems in Identifying Causes of Emergency Diesel Generator Malfunctions (3 June 1991)
- Information Notice 1991-35, Labeling Requirements for Transporting Multi-Hazard Radioactive Materials (7 June 1991)
- Information Notice 1991-36, Nuclear Plant Staff Working Hours (10 June 1991)
- Information Notice 1991-37, Compressed Gas Cylinder Missile Hazards (10 June 1991)
- Information Notice 1991-38, Thermal Stratification in Feedwater System Piping (13 June 1991, Topic: Unanalyzed Condition)
- Information Notice 1991-39, Compliance with 10 CFR Part 21, Reporting of Defects and Noncompliance. (17 June 1991)
- Information Notice 1991-40, Contamination of Nonradioactive System and Resulting Possibility for Unmonitored, Uncontrolled Release to the Environment (19 June 1991)
- Information Notice 1991-41, Potential Problems with the Use of Freeze Seals (27 June 1991)
- Information Notice 1991-42, Plant Outage Events Involving Poor Coordination Between Operations and Maintenance Personnel During Valve Testing and Manipulations (27 June 1991)
- Information Notice 1991-43, Recent Incidents Involving Rapid Increases in Primary-To-Secondary Leak Rate (5 July 1991, Topic: Grab sample)
- Information Notice 1991-45, Possible Malfunction of Westinghouse Ard, Bfd, & Nbfd Relays, & A200 DC & DPC 250 Magnetic Contactors (5 July 1991)
- Information Notice 1991-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems (18 July 1991)
- Information Notice 1991-47, Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance Test (6 August 1991, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1991-48, False Certificates of Conformance Provided by Westinghouse Electric Supply Company for Refurbished Commercial-Grade Circuit Breakers (9 August 1991, Topic: Fire Barrier)
- Information Notice 1991-49, Enforcement of Safety Requirements for Radiographers (15 August 1991, Topic: High Radiation Area, Fire Barrier)
- Information Notice 1991-50, a Review of Water Hammer Events After 1985 (20 August 1991, Topic: Fire Barrier)
... further results |
---|