Undocumented Changes to Non-Power Reactor Safety System WiringML031050184 |
Person / Time |
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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) |
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Issue date: |
04/20/1998 |
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From: |
Roe J Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-98-014, NUDOCS 9804150188 |
Download: ML031050184 (10) |
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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 |
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Category:NRC Information Notice
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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>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 April 20, 1998 NRC INFORMATION
NOTICE 98-14: UNDOCUMENTED
CHANGES TO NON-POWER REACTOR SAFETY SYSTEM WIRING
Addressees
All holders of operating
licenses or construction
permits for test and research reactors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to inform addressees
of undocumented
modifications
that have occurred in the scram system wiring of two research reactors.
In the first case, the modification
in conjunction
with a switch failure resulted in the reactor being operated for a short time without any technical
specification (TS)required scrams. In the second case, because of a modification, a switch failure could have resulted in a TS required scram being disabled.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider action, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
Oregon State Universty On the morning of February 17, 1998, the TRIGA non-power
reactor at Oregon State University (OSU) had completed
a routine 14-minute
run at 15 watts of power to perform core excess reactivity
measurements.
An attempt was made to manually scram the reactor at the end of the run using the scram button. When the manual scram button did not work, the operators
next step was to turn off power to the scram circuit using the reactor's
three-position
key switch.This switch-1s
OFF, OPERATE, and RESET positions
with a spring return between the RESET and OPERATE positions.
As the operator touched the switch, the switch moved from a position between OPERATE and RESET to the OPERATE position.
The operator then tried the manual scram button again and this time it worked.The licensee determined
that a buildup of dirt prevented
the three-position
switch from returning to the OPERATE position.
When the switch is in the RESET position, the scram bus is disabled.
This switch dates to 1967 when the original console was installed.
The switch operated properly during preoperational
testing before startup.Upon further investigation, the licensee discovered
that the wiring of the scram circuit was different
from the wiring shown in the Instrument
Maintenance
Manual provided by the reactor vndr. Fgure I shows part of the circuitry
as designed.
If the key switch is in the OPERATE D 04151-'i ureg 1D s4 ows~g- lt;)X
K>IN 98-14 April 20, 1998 position, ac power is supplied from terminal block one, terminal number four (TBI -4) through TBI-9, to TB2-3, the A3 and Al contacts of the three-position
switch, and then the console power switch. This allows transformer
four (T4) to power the rod magnets. When the key is turned to RESET, this circuit is opened and the magnet current is cut off. This prevents rod withdrawal
if the rods are down, or causes the rods to drop if they are up. This design feature prevents a single failure of the three-position
switch from disabling
the scram circuits.
In the RESET position, power is supplied to the scram reset relays (K19, K20, and K24), which reset the scram relays (only one scram relay, K12, is shown). If the key switch sticks in the RESET position, the scram relay will continued
to be energized
by the reset relay even if a scram signal occurs. This is not a problem because the power would already be cut off to the magnets.Figure 2 shows the wiring as found in the OSU console. The wiring that was between TB1-9 and TB2-3 in the "as designed" circuit was between TBI-9 and TBIO-10 in the OSU console.As a result, there is power to the magnets when the switch is in the RESET or OPERATE position.The licensee concluded
that the location of the jumper was probably modified during initial installation
of the reactor console in 1967. This modification
was probably done to provide power to the *B deck 3 on the three-position
switch to power REACTOR ON lights.The licensee took a number of corrective
actions. The three-position
switch was removed, cleaned, relubricated, and reinstalled
in the console. The reactor console wiring was restored to its as-designed
condition.
The wiring in the scram circuitry
and in other non-scram-related
circuits was checked physically
and electronically
to demonstrate
that the wiring in the console is as designed.
The reactor startup procedure
was rewritten
to test that the magnet power is cut off when the three-position
switch is placed in the RESET position.
The reactor console was subject to routine startup checks and the semiannual
console check procedure.
The reactor vendor was contacted
to obtain checkout procedures
to confirm that all suggested surveillances
are done before reactor operation.
Texas A&M Universiy OSU quickly placed information
about the failure to scram on the Organization
of Test, Researth and Training Reactors (TRTR) list server. As a result, the staff at the Texas A&M University
N&clear Science Center checked the logic diagrams for its TRIGA research reactor and determined
that its reactor could not fail to scram. The Texas A&M console differs from the one at OSU in that there is no master reset equivalence
to the three-position
switch. Three of the scrams have push-button
spring-returned
switches that clear the locked-in
alarm on the console and allow the scram relay coil to be reenergized
if the signal is clear.The licensee also tested the circuit and determined
that each of the three scrams associated
with these switches could be defeated by holding its switch down in the RESET position (this simulated
a switch failure).
In this case, the failure of a single switch could prevent an individual
scram signal but would have not disabled all scrams. The licensee then checked the wiring diagrams for the console and discovered
that the wiring of the console matched the wiring diagrams.
The RESET switches were wired in parallel with the normally closed scram contacts.This wiring maintained
power to the magnets through one parallel path if the switch was
IN 9S*14 April 20, 1998 depressed, even if a scram contact opened in the other parallel path. The switches should have been wired in series. The licensee cannot determine
when the console was wired this way, but notes that the console underwent
a major upgrade in 1968. The logic diagram, drawn in 1976, which differs from the wiring diagram and the as-wired console, appears to have been based on system knowledge
of how it should be configured
rather than on the actual configuration.
To correct this situation, the licensee changed the wiring to put the RESET switch in series with the protective
action contacts, physically
verified console wiring for scram circuits, identified
various failure modes, and tested the console for proper operation.
Discussion
The circumstances
described
above demonstrate
the importance
of controlling
modifications, ensuring that all of the consequences
of a modification
are carefully
considered, and ensuring that design features in the scram circuitry
perform as designed.
Careful reviews of modifications
through the safety review process can be an effective
method to help to ensure that unintended
deleterious
effects from modifications
do not occur. The identification
of safety system design features could lead to surveillances
or tests that could prevent the occurrence
of similar problems.
The staff noted that many licensees
contacted
the NRC to discuss the results of testing performed
on consoles because of the information
placed on the TRTR listed server by OSU.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below.Jack Roe, Acting Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: Alexander
Adams, Jr., NRR 301-415-1127.E-mail: axa@nrc.gov
Attachments:
1. Figure 1, *Reactor Operate Circuit, As-Designed" 2. Figure 2, Reactor Operate Circuit -As Found" 3. List of Recently Issued NRC Information
Notices-L
vD C Em DOCUMENT NAME: G:WVERN\OSUSCRAM.INF
Tech Editor concurred
on 3126/98 To receive a copy of this document, indicate in the box C=Copy wlo attachmentlenclosure
E=Copy with attachmentfenclosure
N = NIcopy OFFICE PDND (A)D:PDND
C:PECB (A)D:DRPIV\S
A NAME AAdams* MMendonca*
JStolz* JRoe*[DATE 03/30198 03/30/98 04/06/98 04/13/98 5'OFFICIAL RECORD COPY
P6-3 5 P22-1 0 TB10 Switched AC (H)T P2 f6 2 T T1 Bi B36P22-l1 T910 4 T4 50 Operate Permissive
Jumper 1 3 A .34P3-21 TB2 1 4TB` P3-202 CBB1l A4 >3 P5-4 AC (N) *OFF 0J5) *OPERATE (*RESET Part of Console Key Switch TBl 0 dAC (N)External Scram AC (N)-. (Kl12 K19 K20 K24 Kl2 l H tK1 6-7 'Switched AC (H)Fiaure I. Reactor OnprAt0 Circiuit.
Aq-dpeinnadr
..I-- -..--. -V-- --- -..-- .-, --- --- .U.-
Si9 P6-35 P22-10 TB10 TB10 Si "KSwitched
AC (H)82 AC (N) TB1 POWER OR P6-36 P22-11 TB10 E3 T4 P5-1 A2 .341 P3(2 T82 P3-0 Cal 8L P5-4 AC (N) f*OF*OPERATE* RESET Part of Console Key Switch (TB1 0 SIAC (N)Exterral Scram NO AC (N)0- -- 9X6-7 l_______ Switched AC (H) f5B Ftc Figr 0. Reco prt 0cft- A Fud
.I Attachment
3 IN 98-14 April20, 1998 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 98-13 Post-Refueling
Outage Reactor 4120/98 All holders of operating
licenses Pressure Vessel Leak Testing Before Core Criticality
for nuclear power reactors except those that have permanently
ceased operations
and have certified
that fuel has been permanently
removed from the reactor vessel 98-12 9&-1 1 Licensees'
Responsibilities
Regarding
Reporting
and Follow-up Requirements
for Nuclear-Powered
Pacemakers
Cracking of Reactor Vessel Internal Baffle Former Bolts in Foreign Plants 4/3/98 3/25/98 All U.S. Nuclear Regulatory
Commission
nuclear pacemaker licensees All holders of operating
licensing for pressurized-water
reactors (PWRs) except those who have ceased operation
and have certified
that fuel has been permanently
removed from the reactor vessel.95-52, Supp. 1 Fire Endurance
Test Results for Electrical
Raceway Fire Barrier Systems Constructed
From 3M Company Interam-ire Barrier Materials 3/17/98 All holders of operating licenses for nuclear power reactors except those who have permanently
ceased operation
and have certified
that fuel has been permanently
removed from the reactor vessel.98-10 98-09 Probable Misadministrations
Occurring
During Intravascular
Brachytherapy
With The Novoste Beta-Cath
System Collapse Of An Isocam II Dual-Headed
Nuclear Medicine Gamma Camera 3/9/98 3/5/98 All Medical Licensees All Medical Licensees OL = Operating
License CP = Construction
Permit
- KIN ?-14 April 20, 1998 depressed, even if a scram contact opened in the other parallel path. The switches should have been wired in series. The licensee cannot determine
when the console was wired this way, but notes that the console underwent
a major upgrade in 1968. The logic diagram, drawn in 1976, which differs from the wiring diagram and the as-wired console, appears to have been based on system knowledge
of how it should be configured
rather than on the actual configuration.
To correct this situation, the licensee changed the wiring to put the RESET switch in series with the protective
action contacts, physically
verified console wiring for scram circuits, identified
various failure modes, and tested the console for proper operation.
Discussion
The circumstances
described
above demonstrate
the importance
of controlling
modifications, ensuring that all of the consequences
of a modification
are carefully
considered, and ensuring that design features in the scram circuitry
perform as designed.
Careful reviews of modifications
through the safety review process can be an effective
method to help to ensure that unintended
deleterious
effects from modifications
do not occur. The identification
of safety system design features could lead to surveillances
or tests that could prevent the occurrence
of similar problems.
The staff noted that many licensees
contacted
the NRC to discuss the results of testing performed
on consoles because of the information
placed on the TRTR listed server by OSU.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below.orig /sfd by D. B. Matthews FOR Jack Roe, Acting Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: Alexander
Adams, Jr., NRR 301-415-1127 E-mail: axa~nrc.gov
Attachments:
1. Figure 1, OReactor Operate Circuit, As-Designed'
2. Figure 2, uReactor Operate Circuit -As Found" 3. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:WVERN\OSUSCRAM.INF
Tech Editor concurred
on 3/26198 To receive a copy of this document indicate In the box C=Copy wlo attachmentenclosure
E=Copy with attachmentlenclosure
N = No copy OFFICE PDND (A)D:PDND
I C:PECB Il (A)D:DRPM
Il NAME AAdams* MMendonca*
JStolz* JRoe*lDATE _ 03/30/98 03/30/98 04106198 j 04/13/98 OFFICIAL RECORD COPY
-- INbe14 April 20, 1998 depressed, even if a scram contact opened in the other parallel path. The switches should have been wired in series. The licensee cannot determine
when the console was wired this way, but notes that the console underwent
a major upgrade in 1968. The logic diagram, drawn in 1976, which differs from the wiring diagram and the as-wired console, appears to have been based on system knowledge
of how it should be configured
rather than on the actual configuration.
To correct this situation, the licensee changed the wiring to put the RESET switch in series with the protective
action contacts, physically
verified console wiring for scram circuits,.identified
various failure modes, and tested the console for proper operation.
Discussion
The circumstances
described
above demonstrate
the importance
of controlling
modifications, ensuring that all of the consequences
of a modification
are carefully
considered, and ensuring that design features in the scram circuitry
perform as designed.
Careful reviews of modifications
through the safety review process can be an effective
method to help to ensure that unintended
deleterious
effects from modifications
do not occur. The identification
of safety system design features could lead to surveillances
or tests that could prevent the occurrence
of similar problems.
The staff noted that many licensees
contacted
the NRC to discuss the results of testing performed
on consoles because of the information
placed on the TRTR listed server byOSU.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below.Jack Roe, Acting Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: Alexander
Adams, Jr., NRR 301-415-1127 E-mail: axa@nrc.gov
Attachments:
1. Figure 1, uReactor Operate Circuit, As-Designed" 2. Figure 2, "Reactor Operate Circuit -As Found" 3. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:WVERNOSUSCRAM.INF
Tech Editor concurred
on 3/26198 To receive a copy of this document, indicate in the box C=Copy wlo attachmentlenclosure
E=Copy with attachmentenclosure
N = Nlcopy I OFFICE PDND I (A)D:PDND
l C:PECB I (A)D:DRP NAME AAdams* MMendonca*
JStoz* JRoe*l DATE 03/30/98 03/30/98 04/06/98 04/13/98 OFFICIAL RECORD COPY
IN' XX .K ApexL 1998 (this simulated
a switch failure).
In this case, the failure of a single switch could preve an individual
scram signal but would have not disabled all scrams. The licensee then ecked the wiring diagrams for the console and discovered
that the wiring of the console moed the wiring diagrams.
The RESET switches were wired in parallel with the normall y-losed scram contacts.
This wiring maintained
power to the magnets through one paralle ath if the switch was depressed, even if a scram contact opened in the other parallel pathThe switches should have been wired in series. The licensee cannot determine
when the sole was wired this way, but notes that the console underwent
a major upgrade in 1968. e logic diagram, drawn in 1976, which differs from the wiring diagram and the as-wired co sole, appears to have been based on system knowledge
of how i should be configured
rat r than on the actual configuration.
To correct this situation, the licensee changed the wiring put the RESET switch in series with the protective
action contacts, physically
verified conso wiring for scram circuits, identified
various failure modes, and tested the console for probr operation.
Discussion
The circumstances
described
above demon ate the importance
of controlling
modifications, ensuring that all of the consequences
of a odification
are carefully
considered, and ensuring that design features in the scram circuit perform as designed.
Careful reviews of modifications
through the safety revie process can be an effective
method to help to ensure that unintended
deleterious
effects f m modifications
do not occur. The Identification
of safety system design features could lead o surveillances
or tests that could prevent the occurrence
of similar problems.
The staff note that many licensees
contacted
the NRC to discuss the results of testing performed
on consols because of the information
placed on the TRTR listed server by OSU.This information
notice r uires no specific action or written response.
If you have any questions
about the inf ation in this notice, please contact the technical
contact listed below.Jack Roe, Acting Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
c ctac: Alexander
Adams, Jr., NRR 301-415-1127 E-mail: axaenrc.gov
Attac ent: List of Recently Issued NRC Information
Notices DT e MENT NAME: G:WVERN\OSUSCRAM.INF
To receive a copy f this document.
indicate In the box C=Copy w/o attachmeE=Copy
with co OFFICE PDND I _ (A)D:PDND
l C:PE'CB (A)D:DR hl1 I NAME AAdams* MMendonca*
iQStolz JRoe Jk DATE 03/30198 03/30/98 g 4 /j3198 OFFICIAL RECORD COPY a-) .
IN'- XX_ ApiV..x, 1998 switch failure).
The licensee then checked the wiring diagrams for the console and discovered
that the wiring of the console matched the wiring diagrams.
In this case, the failure of a single switch could prevent an individual
scram signal but would have not disabled all scrams. The RESET switches were wired in parallel with the normally closed scram contacts.
This wiring maintained
power to the magnets through one parallel path if the switch was depressed, even if a scram contact opened in the other parallel path. The switches should have been wired in series. The licensee cannot determine
when the console was wired this way, but notes that the console underwent
a major upgrade in 1968. The logic diagram, drawn in 1976, which differs from the wiring diagram and the as-wired console, appears to have been based on system knowledge
of how it should be configured
rather than on the actual configuration.
To correct this situation, the licensee changed the wiring to put the RESET switch in series with the protective
action contacts, physically
verified console wiring for scram circuits, identified
various failure modes, and tested the console for proper operation.
Discussion
The circumstances
described
above demonstrate
the Importance
of controlling
modifications, ensuring that all of the consequences
of a modification
are carefully
considered, and ensuring that design features in the scram circuitry
perform as designed.
Careful reviews of modifications
through the safety review process can be an effective
method to help to ensure that unintended
deleterious
effects from modifications
do not occur. The identification
of safety system design features could lead to surveillances
or tests that could prevent the occurrence
of similar problems.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below.Jack Roe, Acting Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: Alexander
Adams, Jr., NRR 301-415-1127 E-mail: axa@nrc.gov
Attachment:
List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:WVERN\OSUSCRAM.INF
To receive a copy of this document, indicate in the box C=Copy wlo attachment/endosure
E=Copy with attachment/enclosure
N = No copy OFFICE PDND I l (A)D:PDND
l l C:PECB (A)D:DRPM
Il NAME AAdams OA l MMendonca
L4/) T JStolz JRoe DATE 1 031/)/98 l 0313)198 1 03/ /98 7 03/ /98 OFFICIAL RECORD COPY
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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)
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