Information Notice 2004-19, Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 17: Line 17:
{{#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:                 PROBLEMS ASSOCIATED WITH BACK-UP
===WASHINGTON, D.C. 20555===
 
November 4, 2004 NRC INFORMATION NOTICE 2004-19:
POWER SUPPLIES TO EMERGENCY
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
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
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
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


===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
(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


===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
(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:                   ADAMS               IN File
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


OFFICE  DPR:EPD:NSIR      TECH EDITOR      EMCB                EPD:DPR:NSIR  D:EPD:DPR:NSIR
PLHiland


NAME    JLFlemming        PKleene          SLRosenberg          EWWeiss        NLMamish
DATE


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
10/14/2004
10/18/2004
11/03/2004
11/04/2004
    /       /2004


NAME    EJLeeds          CDPetrone        ACMcMurtray          PLHiland
===OFFICIAL RECORD COPY===


DATE    10/14/2004        10/18/2004      11/03/2004          11/04/2004        /  /2004 OFFICIAL RECORD COPY
______________________________________________________________________________________
OL = Operating License


Attachment 1 LIST OF RECENTLY ISSUED
CP = Construction Permit


===Attachment 1 LIST OF RECENTLY ISSUED===
NRC INFORMATION NOTICES
NRC INFORMATION NOTICES


_____________________________________________________________________________________
_____________________________________________________________________________________
Information                                               Date of
Information


Notice No.             Subject                           Issuance       Issued to
Date of
 
Notice No.
 
Subject
 
Issuance
 
Issued to


_____________________________________________________________________________________
_____________________________________________________________________________________
2004-18           Recent Safety-related Event at         10/26/2004     All licensees authorized to
2004-18 Recent Safety-related Event at
 
Panoramic Wet-source- storage Irradiator
 
10/26/2004


Panoramic Wet-source-                                  possess and use sealed sources
===All licensees authorized to===
possess and use sealed sources


storage Irradiator                                    in panoramic wet-source-storage
in panoramic wet-source-storage


irradiators, and irradiator vendors.
irradiators, and irradiator vendors.


2004-17           Loose Part Detection and               08/25/2004      All holders of operating licenses
2004-17 Loose Part Detection and
 
===Computerized Eddy Current===
Data Analysis in Steam


Computerized Eddy Current                              for pressurized-water reactors
Generators


Data Analysis in Steam                                (PWRs), except those who have
08/25/2004


Generators                                            permanently ceased operations
===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           Tube Leakage Due to a                 08/03/2004     All holders of operating licenses
2004-16
 
===Tube Leakage Due to a===
Fabrication Flaw in a
 
===Replacement Steam Generator===
08/03/2004


Fabrication Flaw in a                                  for pressurized-water reactors
===All holders of operating licenses===
for pressurized-water reactors


Replacement Steam Generator                            (PWRs), except those who have
(PWRs), except those who have


permanently ceased operations
permanently ceased operations
Line 391: Line 474:
the reactor.
the reactor.


2004-15           Dual-Unit Scram at Peach               07/22/2004     All holders of operating licenses
2004-15 Dual-Unit Scram at Peach
 
===Bottom Units 2 and 3===
07/22/2004


Bottom Units 2 and 3                                  for nuclear power reactors except
===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           Use of less than Optimal               07/19/2004      All licensees authorized to
2004-14
 
===Use of less than Optimal===
Bounding Assumptions in
 
===Criticality Safety Analysis at===
Fuel Cycle Facilities


Bounding Assumptions in                                possess a critical mass of special
07/19/2004


Criticality Safety Analysis at                        nuclear material.
===All licensees authorized to===
possess a critical mass of special


Fuel Cycle Facilities
nuclear material.


Note:           NRC generic communications may be received in electronic format shortly after they are
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
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
subscribe gc-nrr firstname lastname}}
 
______________________________________________________________________________________
OL = Operating License
 
CP = Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 01:01, 16 January 2025

Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment
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#

ML033570386)

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#

ML033570386)

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:

ADAMS

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:

NRC generic communications may be received in electronic format shortly after they are

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:

subscribe gc-nrr firstname lastname