Information Notice 2004-19, Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES | ||
NUCLEAR REGULATORY COMMISSION | ===NUCLEAR REGULATORY COMMISSION=== | ||
OFFICE OF NUCLEAR REACTOR REGULATION | OFFICE OF NUCLEAR REACTOR REGULATION | ||
WASHINGTON, D.C. 20555 November 4, 2004 NRC INFORMATION NOTICE 2004-19: | ===WASHINGTON, D.C. 20555=== | ||
November 4, 2004 NRC INFORMATION NOTICE 2004-19: | |||
PROBLEMS ASSOCIATED WITH BACK-UP | |||
===POWER SUPPLIES TO EMERGENCY=== | |||
RESPONSE FACILITIES AND EQUIPMENT | RESPONSE FACILITIES AND EQUIPMENT | ||
| Line 38: | Line 38: | ||
addressees to problems with back-up power supplies for emergency response facilities (ERFs) | addressees to problems with back-up power supplies for emergency response facilities (ERFs) | ||
and equipment. Emergency response equipment and ERFs need to be functional in the event | and equipment. Emergency response equipment and ERFs need to be functional in the event | ||
of an emergency. It is expected that recipients will review the information for applicability to | of an emergency. It is expected that recipients will review the information for applicability to | ||
their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRC requirements; therefore, no | their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRC requirements; therefore, no | ||
specific action or written response is required. | specific action or written response is required. | ||
| Line 50: | Line 50: | ||
of Title 10 of the Code of Federal Regulations (CFR), Part 50, Paragraph 47(b)(8): | of Title 10 of the Code of Federal Regulations (CFR), Part 50, Paragraph 47(b)(8): | ||
Adequate emergency facilities and equipment to support the emergency response are | |||
provided and maintained. | provided and maintained. | ||
| Line 57: | Line 57: | ||
Appendix E to 10 CFR Part 50: | Appendix E to 10 CFR Part 50: | ||
Adequate provisions shall be made and described for emergency facilities and | |||
equipment, including: | equipment, including: | ||
A licensee onsite technical support center (TSC) and a licensee near-site emergency | |||
operations facility from which effective direction can be given and effective control can | operations facility from which effective direction can be given and effective control can | ||
| Line 74: | Line 74: | ||
On June 14, 2004, as a result of a loss of offsite power (LOOP) event at Palo Verde Nuclear | On June 14, 2004, as a result of a loss of offsite power (LOOP) event at Palo Verde Nuclear | ||
Generating Station, electrical power was lost to the TSC. The TSC diesel generator started as | Generating Station, electrical power was lost to the TSC. The TSC diesel generator started as | ||
designed, but subsequently tripped due to high engine temperature. During troubleshooting, it | designed, but subsequently tripped due to high engine temperature. During troubleshooting, it | ||
was determined that the engine operating switch was in idle. With the switch in idle, the diesel | was determined that the engine operating switch was in idle. With the switch in idle, the diesel | ||
generator started on loss of electrical power to the TSC, but did not come up to proper voltage | generator started on loss of electrical power to the TSC, but did not come up to proper voltage | ||
and frequency and did not reenergize the TSC electrical distribution panel. As a result, the | and frequency and did not reenergize the TSC electrical distribution panel. As a result, the | ||
engine radiator cooling fan did not start; therefore, the engine overheated and tripped on high | engine radiator cooling fan did not start; therefore, the engine overheated and tripped on high | ||
| Line 96: | Line 96: | ||
leader allowed the electricians to test the engine starting system without a working copy of the | leader allowed the electricians to test the engine starting system without a working copy of the | ||
test procedure in the field, since this test was routinely performed by the electricians. After the | test procedure in the field, since this test was routinely performed by the electricians. After the | ||
diesel generator was successfully started, the engine operating switch was moved from run to | diesel generator was successfully started, the engine operating switch was moved from run to | ||
idle to allow the engine to run at a slower speed and cool down before being secured. A follow- up NRC inspection determined that the failure to have a working copy of the test procedure at | idle to allow the engine to run at a slower speed and cool down before being secured. A follow- up NRC inspection determined that the failure to have a working copy of the test procedure at | ||
the engine during this post-maintenance testing and failure to use the restoration guidance | the engine during this post-maintenance testing and failure to use the restoration guidance | ||
| Line 106: | Line 106: | ||
contained in the test procedure contributed directly to the failure to restore the TSC diesel | contained in the test procedure contributed directly to the failure to restore the TSC diesel | ||
generator to its normal standby condition. The NRC inspection also determined that the diesel | generator to its normal standby condition. The NRC inspection also determined that the diesel | ||
generator failure contributed to a delay in staffing the TSC because the responding members of | generator failure contributed to a delay in staffing the TSC because the responding members of | ||
the emergency response organization were moved to an alternate TSC. This issue was | the emergency response organization were moved to an alternate TSC. This issue was | ||
documented in NRC Inspection Report 05000528/2004012; 05000529/2004012; | documented in NRC Inspection Report 05000528/2004012; 05000529/2004012; | ||
05000530/2004012. (ADAMS# ML042020061) | 05000530/2004012. (ADAMS# ML042020061) | ||
Procedural Changes Modifying the Effectiveness of the Emergency Operations Facility (EOF) | Procedural Changes Modifying the Effectiveness of the Emergency Operations Facility (EOF) | ||
On June 25, 2001, the NRC resident inspector at the Cooper Nuclear Station observed the | On June 25, 2001, the NRC resident inspector at the Cooper Nuclear Station observed the | ||
licensees response to an alert declaration due to a fire affecting the station startup transformer. | licensees response to an alert declaration due to a fire affecting the station startup transformer. | ||
During the event, the inspector noted that the EOF had no alternating current (AC) power. The | During the event, the inspector noted that the EOF had no alternating current (AC) power. The | ||
normal power supply to the EOF was deenergized when the startup transformer isolated | normal power supply to the EOF was deenergized when the startup transformer isolated | ||
following an electrical component failure. As a result, the EOF had limited communication | following an electrical component failure. As a result, the EOF had limited communication | ||
abilities and emergency battery powered lighting. | abilities and emergency battery powered lighting. | ||
| Line 129: | Line 129: | ||
Although a back-up power supply existed for the EOF, it was only allowed to supply power to | Although a back-up power supply existed for the EOF, it was only allowed to supply power to | ||
necessary equipment when the plant was operating in Mode 4, cold shutdown or Mode 5, refueling. In operating Modes 1, 2, and 3, power operations, startup, and hot shutdown, respectfully, the back-up power supply was allowed to power only communication equipment | necessary equipment when the plant was operating in Mode 4, cold shutdown or Mode 5, refueling. In operating Modes 1, 2, and 3, power operations, startup, and hot shutdown, respectfully, the back-up power supply was allowed to power only communication equipment | ||
due to electrical loading restrictions on the switchgear. The NRC resident inspector determined | due to electrical loading restrictions on the switchgear. The NRC resident inspector determined | ||
that this restriction significantly compromised the ability of the emergency operations facility to | that this restriction significantly compromised the ability of the emergency operations facility to | ||
| Line 137: | Line 137: | ||
adequately function following a loss of normal power in Modes 1, 2, and 3. In 1986, the licensee performed a design change to increase the reliability of the EOF and | adequately function following a loss of normal power in Modes 1, 2, and 3. In 1986, the licensee performed a design change to increase the reliability of the EOF and | ||
provide a back-up source of power during a loss of offsite power event. This design change | provide a back-up source of power during a loss of offsite power event. This design change | ||
originally placed no restrictions on using the back-up power supply to the EOF for any operating | originally placed no restrictions on using the back-up power supply to the EOF for any operating | ||
mode. On September 14, 1991, the licensee revised a system operating procedure which | mode. On September 14, 1991, the licensee revised a system operating procedure which | ||
restricted the back-up power source to supply only the emergency operations facility | restricted the back-up power source to supply only the emergency operations facility | ||
| Line 147: | Line 147: | ||
communication system when operating in Modes 1, 2, and 3, due to power limitations on the | communication system when operating in Modes 1, 2, and 3, due to power limitations on the | ||
electrical switchgear. This issue was documented in NRC Inspection Report 50-298/01-09. | electrical switchgear. This issue was documented in NRC Inspection Report 50-298/01-09. | ||
(ADAMS# ML043070372) | (ADAMS# ML043070372) | ||
===Failure to Maintain the TSC Batteries=== | ===Failure to Maintain the TSC Batteries=== | ||
On December 11, 2003, the NRC completed an inspection at the Indian Point Nuclear | On December 11, 2003, the NRC completed an inspection at the Indian Point Nuclear | ||
Generating Station, Unit 2. While reviewing condition reports, the inspection team noted that, during the quarterly surveillance tests performed on October 21, 2003, one cell in each of the | Generating Station, Unit 2. While reviewing condition reports, the inspection team noted that, during the quarterly surveillance tests performed on October 21, 2003, one cell in each of the | ||
two TSC battery banks did not meet the acceptance criteria specified in the test procedures. | two TSC battery banks did not meet the acceptance criteria specified in the test procedures. | ||
| Line 164: | Line 164: | ||
evaluate the impact of the out of specification conditions on the functionality of the battery | evaluate the impact of the out of specification conditions on the functionality of the battery | ||
banks. Although the TSC battery banks performed as designed during the northeastern grid | banks. Although the TSC battery banks performed as designed during the northeastern grid | ||
blackout on August 14, 2003 (August 14 event), the team determined that the degraded cells | blackout on August 14, 2003 (August 14 event), the team determined that the degraded cells | ||
| Line 170: | Line 170: | ||
had the potential to adversely affect the facilities and equipment required to support emergency | had the potential to adversely affect the facilities and equipment required to support emergency | ||
response. This issue was documented in NRC Inspection Report 05000247/2004003. | response. This issue was documented in NRC Inspection Report 05000247/2004003. | ||
(ADAMS# ML040360248) | (ADAMS# ML040360248) | ||
===Miscellaneous Failures During the August 14 Event=== | ===Miscellaneous Failures During the August 14 Event=== | ||
| Line 181: | Line 181: | ||
The Unit 2 TSC diesel generator failed to function due to electrical loading in excess of its | The Unit 2 TSC diesel generator failed to function due to electrical loading in excess of its | ||
design capacity. This condition was initially identified in February 2000 and was not resolved in | design capacity. This condition was initially identified in February 2000 and was not resolved in | ||
a timely manner. Observations by the licensee during emergency planning training revealed a | a timely manner. Observations by the licensee during emergency planning training revealed a | ||
potential for the TSC back-up diesel generator to be overloaded. Also, a review by the licensee | potential for the TSC back-up diesel generator to be overloaded. Also, a review by the licensee | ||
of the electrical power distribution drawings showed a potential existed for the TSC back-up | of the electrical power distribution drawings showed a potential existed for the TSC back-up | ||
diesel generator to be overloaded under some conditions. Long-term corrective actions for this | diesel generator to be overloaded under some conditions. Long-term corrective actions for this | ||
diesel were postponed. The Unit 2 TSC and Operational Support Center remained without a | diesel were postponed. The Unit 2 TSC and Operational Support Center remained without a | ||
back-up AC electrical power supply until September 15, 2003, when a temporary alteration was | back-up AC electrical power supply until September 15, 2003, when a temporary alteration was | ||
| Line 201: | Line 201: | ||
started and then tripped while being loaded and was unavailable for the duration of the | started and then tripped while being loaded and was unavailable for the duration of the | ||
blackout. The Unit 3 TSC diesel generator failed to function due to a malfunctioning overspeed | blackout. The Unit 3 TSC diesel generator failed to function due to a malfunctioning overspeed | ||
controller. The diesel generator was repaired and restored to service on September 16, 2003. | controller. The diesel generator was repaired and restored to service on September 16, 2003. | ||
During a refueling outage, on April 18, 2003, the Unit 3 TSC back-up diesel generator was | During a refueling outage, on April 18, 2003, the Unit 3 TSC back-up diesel generator was | ||
| Line 209: | Line 209: | ||
tested under simulated blackout conditions and tripped while being loaded. Subsequently, a licensee system engineer initiated a work order to replace a suspected faulty overspeed trip | tested under simulated blackout conditions and tripped while being loaded. Subsequently, a licensee system engineer initiated a work order to replace a suspected faulty overspeed trip | ||
module. Seven hours later, the Unit 3 TSC diesel was retested in an unloaded condition and | module. Seven hours later, the Unit 3 TSC diesel was retested in an unloaded condition and | ||
declared operable. The work order to replace the TSC diesel generator overspeed trip module | declared operable. The work order to replace the TSC diesel generator overspeed trip module | ||
was postponed by the licensees maintenance planning organization until November 2003, based upon a determination that the diesel problem was not an operability concern. | was postponed by the licensees maintenance planning organization until November 2003, based upon a determination that the diesel problem was not an operability concern. | ||
| Line 221: | Line 221: | ||
the continued functionality of the numerous Un-Interruptible Power Supplies (UPSs) in the EOF | the continued functionality of the numerous Un-Interruptible Power Supplies (UPSs) in the EOF | ||
which provide back-up power to emergency response equipment. By design, there is no | which provide back-up power to emergency response equipment. By design, there is no | ||
electrical back-up power supply to the EOF. Instead, the EOF has a number of UPSs which | electrical back-up power supply to the EOF. Instead, the EOF has a number of UPSs which | ||
provide short-term battery back-up power to dedicated ERF communications and data | provide short-term battery back-up power to dedicated ERF communications and data | ||
transmission systems. During the August 14 event, the UPSs failed or functioned at only a | transmission systems. During the August 14 event, the UPSs failed or functioned at only a | ||
fraction of their design capacity. | fraction of their design capacity. | ||
| Line 233: | Line 233: | ||
The failures of the Unit 2 and 3 TSC back-up diesel generators and the EOF UPSs were | The failures of the Unit 2 and 3 TSC back-up diesel generators and the EOF UPSs were | ||
documented in NRC Inspection Report 05000247/2003013 and 05000286/2003010. (ADAMS# | documented in NRC Inspection Report 05000247/2003013 and 05000286/2003010. (ADAMS# | ||
ML033570386) | ML033570386) | ||
CONCLUSION | CONCLUSION | ||
| Line 239: | Line 239: | ||
Problems with back-up power supplies and equipment have the potential to impact the ability of | Problems with back-up power supplies and equipment have the potential to impact the ability of | ||
ERFs to support a prompt and effective response to an emergency. The occurrence of these | ERFs to support a prompt and effective response to an emergency. The occurrence of these | ||
types of problems can be reduced by following restoration procedures after testing and | types of problems can be reduced by following restoration procedures after testing and | ||
| Line 248: | Line 248: | ||
==CONTACT== | ==CONTACT== | ||
This information notice requires no specific action or written response. Please direct any | This information notice requires no specific action or written response. Please direct any | ||
questions about information in this notice to the technical contact listed below or the appropriate | questions about information in this notice to the technical contact listed below or the appropriate | ||
| Line 255: | Line 255: | ||
/RA/ | /RA/ | ||
===Patrick L. Hiland, Chief=== | |||
Reactor Operations Branch | Reactor Operations Branch | ||
Division of Inspection Program Management | ===Division of Inspection Program Management=== | ||
Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation | ||
| Line 266: | Line 265: | ||
===Jason L. Flemming=== | ===Jason L. Flemming=== | ||
(301) 415-5787 E-mail: jlf2@nrc.gov | |||
Attachment: List of Recently Issued NRC Information Notices licensee system engineer initiated a work order to replace a suspected faulty overspeed trip | Attachment: List of Recently Issued NRC Information Notices licensee system engineer initiated a work order to replace a suspected faulty overspeed trip | ||
module. Seven hours later, the TSC diesel was retested in an unloaded condition and declared | module. Seven hours later, the TSC diesel was retested in an unloaded condition and declared | ||
operable. The work order to replace the TSC diesel generator overspeed trip module was | operable. The work order to replace the TSC diesel generator overspeed trip module was | ||
postponed by the licensees maintenance planning organization until November 2003, based | postponed by the licensees maintenance planning organization until November 2003, based | ||
| Line 285: | Line 284: | ||
the continued functionality of the numerous UPSs in the EOF which provide back-up power to | the continued functionality of the numerous UPSs in the EOF which provide back-up power to | ||
emergency response equipment. By design, there is no electrical back-up power supply to the | emergency response equipment. By design, there is no electrical back-up power supply to the | ||
EOF. Instead, the EOF has a number of UPSs which provide short-term battery back-up power | EOF. Instead, the EOF has a number of UPSs which provide short-term battery back-up power | ||
to dedicated ERF communications and data transmission systems. During the August 14 event, the UPSs failed or functioned at only a fraction of their design capacity. | to dedicated ERF communications and data transmission systems. During the August 14 event, the UPSs failed or functioned at only a fraction of their design capacity. | ||
The failures of the Unit 2 and 3 TSC back-up diesel generators and the EOF UPSs were | The failures of the Unit 2 and 3 TSC back-up diesel generators and the EOF UPSs were | ||
documented in NRC Inspection Report 05000247/2003013 and 05000286/2003010. (ADAMS# | documented in NRC Inspection Report 05000247/2003013 and 05000286/2003010. (ADAMS# | ||
ML033570386) | ML033570386) | ||
CONCLUSION | CONCLUSION | ||
| Line 299: | Line 298: | ||
Problems with back-up power supplies and equipment have the potential to impact the ability of | Problems with back-up power supplies and equipment have the potential to impact the ability of | ||
ERFs to support a prompt and effective response to an emergency. The occurrence of these | ERFs to support a prompt and effective response to an emergency. The occurrence of these | ||
types of problems can be reduced by following restoration procedures after testing and | types of problems can be reduced by following restoration procedures after testing and | ||
| Line 308: | Line 307: | ||
==CONTACT== | ==CONTACT== | ||
This information notice requires no specific action or written response. Please direct any | This information notice requires no specific action or written response. Please direct any | ||
questions about information in this notice to the technical contact listed below or the appropriate | questions about information in this notice to the technical contact listed below or the appropriate | ||
| Line 315: | Line 314: | ||
/RA/ | /RA/ | ||
===Patrick L. Hiland, Chief=== | |||
Reactor Operations Branch | Reactor Operations Branch | ||
Division of Inspection Program Management | ===Division of Inspection Program Management=== | ||
Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation | ||
| Line 326: | Line 324: | ||
===Jason L. Flemming=== | ===Jason L. Flemming=== | ||
(301) 415-5787 E-mail: jlf2@nrc.gov | |||
Attachment: List of Recently Issued NRC Information Notices | Attachment: List of Recently Issued NRC Information Notices | ||
DISTRIBUTION: | DISTRIBUTION: | ||
ADAMS | |||
IN File | |||
ADAMS ACCESSION #: ML042730010 | ADAMS ACCESSION #: ML042730010 | ||
DOCUMENT NAME: E:\Filenet\ML042730010.wpd | DOCUMENT NAME: E:\\Filenet\\ML042730010.wpd | ||
OFFICE | |||
DPR:EPD:NSIR | |||
TECH EDITOR | |||
EMCB | |||
EPD:DPR:NSIR | |||
D:EPD:DPR:NSIR | |||
NAME | |||
JLFlemming | |||
PKleene | |||
SLRosenberg | |||
EWWeiss | |||
NLMamish | |||
DATE | |||
10/06/2004 | |||
09/23/2004 | |||
10/17/2004 | |||
10/08/2004 | |||
10/12/2004 OFFICE | |||
DPR:NSIR | |||
OES:IROB:DIPM | |||
A:SC:OES:IROB:DIPM | |||
A:C:IROB:DIPM | |||
NAME | |||
EJLeeds | |||
CDPetrone | |||
ACMcMurtray | |||
PLHiland | |||
DATE | |||
10/14/2004 | |||
10/18/2004 | |||
11/03/2004 | |||
11/04/2004 | |||
/ /2004 | |||
===OFFICIAL RECORD COPY=== | |||
______________________________________________________________________________________ | |||
OL = Operating License | |||
CP = Construction Permit | |||
===Attachment 1 LIST OF RECENTLY ISSUED=== | |||
NRC INFORMATION NOTICES | NRC INFORMATION NOTICES | ||
_____________________________________________________________________________________ | _____________________________________________________________________________________ | ||
Information | Information | ||
Notice No. | Date of | ||
Notice No. | |||
Subject | |||
Issuance | |||
Issued to | |||
_____________________________________________________________________________________ | _____________________________________________________________________________________ | ||
2004-18 | 2004-18 Recent Safety-related Event at | ||
Panoramic Wet-source- storage Irradiator | |||
10/26/2004 | |||
===All licensees authorized to=== | |||
possess and use sealed sources | |||
in panoramic wet-source-storage | |||
irradiators, and irradiator vendors. | irradiators, and irradiator vendors. | ||
2004-17 | 2004-17 Loose Part Detection and | ||
===Computerized Eddy Current=== | |||
Data Analysis in Steam | |||
Generators | |||
08/25/2004 | |||
===All holders of operating licenses=== | |||
for pressurized-water reactors | |||
(PWRs), except those who have | |||
permanently ceased operations | |||
and have certified that fuel has | and have certified that fuel has | ||
| Line 377: | Line 453: | ||
the reactor. | the reactor. | ||
2004-16 | 2004-16 | ||
===Tube Leakage Due to a=== | |||
Fabrication Flaw in a | |||
===Replacement Steam Generator=== | |||
08/03/2004 | |||
===All holders of operating licenses=== | |||
for pressurized-water reactors | |||
(PWRs), except those who have | |||
permanently ceased operations | permanently ceased operations | ||
| Line 391: | Line 474: | ||
the reactor. | the reactor. | ||
2004-15 | 2004-15 Dual-Unit Scram at Peach | ||
===Bottom Units 2 and 3=== | |||
07/22/2004 | |||
===All holders of operating licenses=== | |||
for nuclear power reactors except | |||
those who have permanently | those who have permanently | ||
| Line 405: | Line 492: | ||
reactor vessel. | reactor vessel. | ||
2004-14 | 2004-14 | ||
===Use of less than Optimal=== | |||
Bounding Assumptions in | |||
===Criticality Safety Analysis at=== | |||
Fuel Cycle Facilities | |||
07/19/2004 | |||
===All licensees authorized to=== | |||
possess a critical mass of special | |||
nuclear material. | |||
Note: | Note: | ||
NRC generic communications may be received in electronic format shortly after they are | |||
issued by subscribing to the NRC listserver as follows: | issued by subscribing to the NRC listserver as follows: | ||
To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following | |||
command in the message portion: | command in the message portion: | ||
subscribe gc-nrr firstname lastname}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} | ||
Latest revision as of 01:01, 16 January 2025
| ML042730010 | |
| Person / Time | |
|---|---|
| Issue date: | 11/04/2004 |
| From: | Hiland P NRC/NRR/DIPM/IROB |
| To: | |
| Fleming J NSIR/DPR/EPD 415-1587 | |
| References | |
| TAC MC4467 IN-04-019 | |
| Download: ML042730010 (6) | |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555
November 4, 2004 NRC INFORMATION NOTICE 2004-19:
PROBLEMS ASSOCIATED WITH BACK-UP
POWER SUPPLIES TO EMERGENCY
RESPONSE FACILITIES AND EQUIPMENT
ADDRESSEES
All holders of operating licenses for nuclear power reactors, except those who have
permanently ceased operations and have certified that fuel has been permanently removed
from the reactor vessel.
PURPOSE
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to problems with back-up power supplies for emergency response facilities (ERFs)
and equipment. Emergency response equipment and ERFs need to be functional in the event
of an emergency. It is expected that recipients will review the information for applicability to
their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRC requirements; therefore, no
specific action or written response is required.
BACKGROUND
The ERF and emergency response equipment requirements must meet the following standard
of Title 10 of the Code of Federal Regulations (CFR), Part 50, Paragraph 47(b)(8):
Adequate emergency facilities and equipment to support the emergency response are
provided and maintained.
Requirements are also found in Section IV.E Emergency Facilities and Equipment of
Appendix E to 10 CFR Part 50:
Adequate provisions shall be made and described for emergency facilities and
equipment, including:
A licensee onsite technical support center (TSC) and a licensee near-site emergency
operations facility from which effective direction can be given and effective control can
be exercised during an emergency.
DESCRIPTION OF CIRCUMSTANCES
AND
DISCUSSION
TSC Emergency Diesel Generator Switch Misalignment
On June 14, 2004, as a result of a loss of offsite power (LOOP) event at Palo Verde Nuclear
Generating Station, electrical power was lost to the TSC. The TSC diesel generator started as
designed, but subsequently tripped due to high engine temperature. During troubleshooting, it
was determined that the engine operating switch was in idle. With the switch in idle, the diesel
generator started on loss of electrical power to the TSC, but did not come up to proper voltage
and frequency and did not reenergize the TSC electrical distribution panel. As a result, the
engine radiator cooling fan did not start; therefore, the engine overheated and tripped on high
temperature.
The licensee determined that the engine operating switch was apparently left in the idle position
following post-maintenance testing of the engine-starting system performed on June 8, 2004.
After corrective maintenance was performed on one battery terminal and connector, the team
leader allowed the electricians to test the engine starting system without a working copy of the
test procedure in the field, since this test was routinely performed by the electricians. After the
diesel generator was successfully started, the engine operating switch was moved from run to
idle to allow the engine to run at a slower speed and cool down before being secured. A follow- up NRC inspection determined that the failure to have a working copy of the test procedure at
the engine during this post-maintenance testing and failure to use the restoration guidance
contained in the test procedure contributed directly to the failure to restore the TSC diesel
generator to its normal standby condition. The NRC inspection also determined that the diesel
generator failure contributed to a delay in staffing the TSC because the responding members of
the emergency response organization were moved to an alternate TSC. This issue was
documented in NRC Inspection Report 05000528/2004012; 05000529/2004012;
05000530/2004012. (ADAMS# ML042020061)
Procedural Changes Modifying the Effectiveness of the Emergency Operations Facility (EOF)
On June 25, 2001, the NRC resident inspector at the Cooper Nuclear Station observed the
licensees response to an alert declaration due to a fire affecting the station startup transformer.
During the event, the inspector noted that the EOF had no alternating current (AC) power. The
normal power supply to the EOF was deenergized when the startup transformer isolated
following an electrical component failure. As a result, the EOF had limited communication
abilities and emergency battery powered lighting.
Although a back-up power supply existed for the EOF, it was only allowed to supply power to
necessary equipment when the plant was operating in Mode 4, cold shutdown or Mode 5, refueling. In operating Modes 1, 2, and 3, power operations, startup, and hot shutdown, respectfully, the back-up power supply was allowed to power only communication equipment
due to electrical loading restrictions on the switchgear. The NRC resident inspector determined
that this restriction significantly compromised the ability of the emergency operations facility to
adequately function following a loss of normal power in Modes 1, 2, and 3. In 1986, the licensee performed a design change to increase the reliability of the EOF and
provide a back-up source of power during a loss of offsite power event. This design change
originally placed no restrictions on using the back-up power supply to the EOF for any operating
mode. On September 14, 1991, the licensee revised a system operating procedure which
restricted the back-up power source to supply only the emergency operations facility
communication system when operating in Modes 1, 2, and 3, due to power limitations on the
electrical switchgear. This issue was documented in NRC Inspection Report 50-298/01-09.
(ADAMS# ML043070372)
Failure to Maintain the TSC Batteries
On December 11, 2003, the NRC completed an inspection at the Indian Point Nuclear
Generating Station, Unit 2. While reviewing condition reports, the inspection team noted that, during the quarterly surveillance tests performed on October 21, 2003, one cell in each of the
two TSC battery banks did not meet the acceptance criteria specified in the test procedures.
Although the cells were marginally out of specification, the team determined that the licensee
did not take prompt corrective actions either to return the two cells to within specifications or to
evaluate the impact of the out of specification conditions on the functionality of the battery
banks. Although the TSC battery banks performed as designed during the northeastern grid
blackout on August 14, 2003 (August 14 event), the team determined that the degraded cells
had the potential to adversely affect the facilities and equipment required to support emergency
response. This issue was documented in NRC Inspection Report 05000247/2004003.
(ADAMS# ML040360248)
Miscellaneous Failures During the August 14 Event
During the August 14 event, the TSC back-up diesel generator at Indian Point Unit 2 failed to
automatically start and subsequent operator actions to manually start and load the diesel failed.
The Unit 2 TSC diesel generator failed to function due to electrical loading in excess of its
design capacity. This condition was initially identified in February 2000 and was not resolved in
a timely manner. Observations by the licensee during emergency planning training revealed a
potential for the TSC back-up diesel generator to be overloaded. Also, a review by the licensee
of the electrical power distribution drawings showed a potential existed for the TSC back-up
diesel generator to be overloaded under some conditions. Long-term corrective actions for this
diesel were postponed. The Unit 2 TSC and Operational Support Center remained without a
back-up AC electrical power supply until September 15, 2003, when a temporary alteration was
installed and satisfactorily tested.
Additionally during the August 14 event, the Indian Point Unit 3 TSC back-up diesel generator
started and then tripped while being loaded and was unavailable for the duration of the
blackout. The Unit 3 TSC diesel generator failed to function due to a malfunctioning overspeed
controller. The diesel generator was repaired and restored to service on September 16, 2003.
During a refueling outage, on April 18, 2003, the Unit 3 TSC back-up diesel generator was
tested under simulated blackout conditions and tripped while being loaded. Subsequently, a licensee system engineer initiated a work order to replace a suspected faulty overspeed trip
module. Seven hours later, the Unit 3 TSC diesel was retested in an unloaded condition and
declared operable. The work order to replace the TSC diesel generator overspeed trip module
was postponed by the licensees maintenance planning organization until November 2003, based upon a determination that the diesel problem was not an operability concern.
During an inspection at Indian Point Units 2 and 3, following the August 14 event, an NRC team
identified that the licensee did not have a preventive maintenance program in place to ensure
the continued functionality of the numerous Un-Interruptible Power Supplies (UPSs) in the EOF
which provide back-up power to emergency response equipment. By design, there is no
electrical back-up power supply to the EOF. Instead, the EOF has a number of UPSs which
provide short-term battery back-up power to dedicated ERF communications and data
transmission systems. During the August 14 event, the UPSs failed or functioned at only a
fraction of their design capacity.
The failures of the Unit 2 and 3 TSC back-up diesel generators and the EOF UPSs were
documented in NRC Inspection Report 05000247/2003013 and 05000286/2003010. (ADAMS#
CONCLUSION
Problems with back-up power supplies and equipment have the potential to impact the ability of
ERFs to support a prompt and effective response to an emergency. The occurrence of these
types of problems can be reduced by following restoration procedures after testing and
maintenance, promptly resolving deficiencies identified during testing and maintenance, and
reviewing design changes for impact on the operability of ERF back-up power supplies.
CONTACT
This information notice requires no specific action or written response. Please direct any
questions about information in this notice to the technical contact listed below or the appropriate
Office of Nuclear Reactor Regulation project managers.
/RA/
Patrick L. Hiland, Chief
Reactor Operations Branch
Division of Inspection Program Management
Office of Nuclear Reactor Regulation
Technical Contact:
Jason L. Flemming
(301) 415-5787 E-mail: jlf2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices licensee system engineer initiated a work order to replace a suspected faulty overspeed trip
module. Seven hours later, the TSC diesel was retested in an unloaded condition and declared
operable. The work order to replace the TSC diesel generator overspeed trip module was
postponed by the licensees maintenance planning organization until November 2003, based
upon a determination that the diesel problem was not an operability concern.
Failure of EOF Uninterruptible Power Supplies (UPSs)
During an inspection at Indian Point Units 2 and 3, following the August 14 event, an NRC team
identified that the licensee did not have a preventive maintenance program in place to ensure
the continued functionality of the numerous UPSs in the EOF which provide back-up power to
emergency response equipment. By design, there is no electrical back-up power supply to the
EOF. Instead, the EOF has a number of UPSs which provide short-term battery back-up power
to dedicated ERF communications and data transmission systems. During the August 14 event, the UPSs failed or functioned at only a fraction of their design capacity.
The failures of the Unit 2 and 3 TSC back-up diesel generators and the EOF UPSs were
documented in NRC Inspection Report 05000247/2003013 and 05000286/2003010. (ADAMS#
CONCLUSION
Problems with back-up power supplies and equipment have the potential to impact the ability of
ERFs to support a prompt and effective response to an emergency. The occurrence of these
types of problems can be reduced by following restoration procedures after testing and
maintenance, promptly resolving deficiencies identified during testing and maintenance, and
reviewing design changes for impact on the operability of ERF back-up power supplies.
CONTACT
This information notice requires no specific action or written response. Please direct any
questions about information in this notice to the technical contact listed below or the appropriate
Office of Nuclear Reactor Regulation project managers.
/RA/
Patrick L. Hiland, Chief
Reactor Operations Branch
Division of Inspection Program Management
Office of Nuclear Reactor Regulation
Technical Contact:
Jason L. Flemming
(301) 415-5787 E-mail: jlf2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DISTRIBUTION:
IN File
ADAMS ACCESSION #: ML042730010
DOCUMENT NAME: E:\\Filenet\\ML042730010.wpd
OFFICE
DPR:EPD:NSIR
TECH EDITOR
EMCB
EPD:DPR:NSIR
D:EPD:DPR:NSIR
NAME
JLFlemming
PKleene
SLRosenberg
EWWeiss
NLMamish
DATE
10/06/2004
09/23/2004
10/17/2004
10/08/2004
10/12/2004 OFFICE
DPR:NSIR
OES:IROB:DIPM
A:SC:OES:IROB:DIPM
A:C:IROB:DIPM
NAME
EJLeeds
CDPetrone
ACMcMurtray
PLHiland
DATE
10/14/2004
10/18/2004
11/03/2004
11/04/2004
/ /2004
OFFICIAL RECORD COPY
______________________________________________________________________________________
OL = Operating License
CP = Construction Permit
Attachment 1 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
_____________________________________________________________________________________
Information
Date of
Notice No.
Subject
Issuance
Issued to
_____________________________________________________________________________________
2004-18 Recent Safety-related Event at
Panoramic Wet-source- storage Irradiator
10/26/2004
All licensees authorized to
possess and use sealed sources
in panoramic wet-source-storage
irradiators, and irradiator vendors.
2004-17 Loose Part Detection and
Computerized Eddy Current
Data Analysis in Steam
Generators
08/25/2004
All holders of operating licenses
for pressurized-water reactors
(PWRs), except those who have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor.
2004-16
Tube Leakage Due to a
Fabrication Flaw in a
Replacement Steam Generator
08/03/2004
All holders of operating licenses
for pressurized-water reactors
(PWRs), except those who have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor.
2004-15 Dual-Unit Scram at Peach
Bottom Units 2 and 3
07/22/2004
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.
2004-14
Use of less than Optimal
Bounding Assumptions in
Criticality Safety Analysis at
Fuel Cycle Facilities
07/19/2004
All licensees authorized to
possess a critical mass of special
nuclear material.
Note:
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issued by subscribing to the NRC listserver as follows:
To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following
command in the message portion:
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