Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants: Difference between revisions
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UNITED STATES | ===UNITED STATES=== | ||
NUCLEAR REGULATORY COMMISSION | |||
NUCLEAR | ===OFFICE OF NUCLEAR REACTOR REGULATION=== | ||
WASHINGTON, D.C. | |||
20555-0001 | |||
===January 25, 1996=== | |||
NRC INFORMATION NOTICE 96-06: DESIGN AND TESTING DEFICIENCIES OF TORNADO | |||
DAMPERS AT NUCLEAR POWER PLANTS | ===DAMPERS AT NUCLEAR POWER PLANTS=== | ||
==Addressees== | ==Addressees== | ||
| Line 38: | Line 41: | ||
dampers because of either inadequacies in damper testing or deficiencies in | dampers because of either inadequacies in damper testing or deficiencies in | ||
damper design. It is expected that recipients will review the information for | damper design. | ||
It is expected that recipients will review the information for | |||
applicability to their facilities and consider actions, as appropriate, to | applicability to their facilities and consider actions, as appropriate, to | ||
| Line 59: | Line 64: | ||
discovered an interference between the plant exhaust vent tornado damper and a | discovered an interference between the plant exhaust vent tornado damper and a | ||
gusset (duct work stru,..turdi stiffener). | gusset (duct work stru,..turdi stiffener). | ||
===The gusset limited the closing=== | |||
travel of the damper linkage in one damper section to 40 percent of full | travel of the damper linkage in one damper section to 40 percent of full | ||
| Line 91: | Line 97: | ||
structures, systems, or components. | structures, systems, or components. | ||
PDfJR | PDfJR | ||
A _oo | |||
o1 | |||
6 s | |||
&H | 9601190306 &H | ||
b | |||
l | |||
aog3t | |||
21 | |||
IN 96-06 January 25, 1996 The licensee revised the preventive maintenance program to require preventive | IN 96-06 January 25, 1996 The licensee revised the preventive maintenance program to require preventive | ||
| Line 109: | Line 126: | ||
condition to the NRC (Licensee Event Report No. 93-020) that could result in | condition to the NRC (Licensee Event Report No. 93-020) that could result in | ||
loss of ventilation to several buildings after passage of a tornado. The | loss of ventilation to several buildings after passage of a tornado. | ||
The | |||
licensee determined through static pressure testing, that the air-exhaust | licensee determined through static pressure testing, that the air-exhaust | ||
| Line 129: | Line 148: | ||
air-intake dampers for the diesel generator from reopening. Other plant areas | air-intake dampers for the diesel generator from reopening. Other plant areas | ||
were less susceptible to damage because of design features and/or alarms, followed by operator actions that could mitigate the consequences. The | were less susceptible to damage because of design features and/or alarms, followed by operator actions that could mitigate the consequences. | ||
The | |||
air-exhaust tornado dampers in the diesel generator building were modified by | air-exhaust tornado dampers in the diesel generator building were modified by | ||
| Line 142: | Line 163: | ||
capable of automatically returning to their normal operating position (open) | capable of automatically returning to their normal operating position (open) | ||
after the tornado passed. However, the specification did not specify the | after the tornado passed. | ||
===However, the specification did not specify the=== | |||
design-bases conditions on the inlet side of the exhaust tornado dampers. | |||
The | |||
static pressure that the damper counterweights would have to overcome was not | static pressure that the damper counterweights would have to overcome was not | ||
| Line 162: | Line 186: | ||
are installed. Surveillance tests in the technical specifications may involve | are installed. Surveillance tests in the technical specifications may involve | ||
damper operations during HVAC systems testing. | damper operations during HVAC systems testing. | ||
===However, specific NRC=== | |||
requirements or guidelines for damper testing in general are limited and do | requirements or guidelines for damper testing in general are limited and do | ||
not extend to tornado dampers. | not extend to tornado dampers. | ||
===Likewise, industry standards and guidelines=== | |||
for testing of tornado dampers are also limited. Unlike other active safety- related dampers that are generally tested along with the HVAC system in which | for testing of tornado dampers are also limited. Unlike other active safety- related dampers that are generally tested along with the HVAC system in which | ||
| Line 174: | Line 200: | ||
until they were called upon to perform their function. | until they were called upon to perform their function. | ||
'wO | 'wO | ||
IN 96-06 January 25, 1996 When called on, certain dampers must close to prevent rapid depressurization | |||
within the structures and HVAC ductwork and then reopen after the tornado | within the structures and HVAC ductwork and then reopen after the tornado | ||
passes. | passes. | ||
In cases for which no redundancy exists, a single failure of a | |||
tornado damper to perform its safety function could result in a loss of safety | |||
system function. Therclore, absence of appropriate surveillance testing | system function. Therclore, absence of appropriate surveillance testing for | ||
tornado dampers could lead to multiple failures in safety systems. | tornado dampers could lead to multiple failures in safety systems. | ||
If | This information notice requires no specific action or written response. If | ||
you have any questions about the information in this notice, please contact | |||
one of the technical contacts listed below or the appropriate Office of | |||
one of the technical contacts listed below or the appropriate Office | |||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
4ennr . | 4ennr .C r u t Coto | ||
d rector | |||
===Division of Reactor rogram Management=== | |||
Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation | ||
Technical contacts: | Technical contacts: William T. LeFave, NRR | ||
(301) 415-3285 Internet:wtllenrc.gov | (301) 415-3285 Internet:wtllenrc.gov | ||
Thomas Koshy, NRR | ===Thomas Koshy, NRR=== | ||
(301) 415-1176 Internet:txk@nrc.gov | |||
Attachment: List of Recently Issued NRC Information Notices | |||
tr | |||
-;1 | |||
\ | \\ | ||
E | |||
Attachment | Attachment | ||
IN 96-06 | IN 96-06 | ||
===January 25, 1996 LIST OF RECENTLY ISSUED=== | |||
NRC INFORMATION NOTICES | NRC INFORMATION NOTICES | ||
Information | Information | ||
Date of | |||
Notice No. | |||
Subject | |||
Issuance | |||
Issued to | |||
96-05 | |||
96-04 | |||
96-03 | |||
===Partial Bypass of Shutdown=== | |||
Cooling Flow from the | |||
===Reactor Vessel=== | |||
Incident Reporting Require- ments for Radiography | |||
Licensees | |||
===Main Steam Safety Valve=== | |||
Setpoint Variation as a | |||
===Result of Thermal Effects=== | |||
01/18/96 | |||
01/10/96 | |||
01/05/96 | |||
===All holders of OLs or LPs=== | |||
for boiling water reactors | |||
===All radiography licensees=== | |||
and manufacturers of radio- graphy equipment | |||
===All holders of OLs or CPs=== | |||
for nuclear power reactors | |||
96-02 Inoperability of Power- | |||
===Operated Relief Valves=== | |||
Masked by Downstream | Masked by Downstream | ||
Indications During Testing | ===Indications During Testing=== | ||
01/05/96 All holders | |||
for PWRs | |||
of OLs or CPs | |||
96-01 | |||
95-58 | |||
95-57 Potential for High Post- Accident Closed-Cycle | |||
===Cooling Water Temperatures=== | |||
to Disable Equipment | to Disable Equipment | ||
Important to Safety | ===Important to Safety=== | ||
10 CFR 34.20; Final | |||
===Effective Date=== | |||
Risk Impact Study Regarding | |||
Maintenance During Low-Power | |||
95 | ===Operation and Shutdown=== | ||
01/03/96 | |||
12/18/95 | |||
12/18/95 | |||
===All holders of OLs or CPs=== | |||
for PWRs | |||
===Industrial Radiography=== | |||
Licensees | |||
===All holders of OLs or CPs=== | |||
for nuclear power reactors. | |||
OL - Operating License | OL - Operating License | ||
| Line 288: | Line 352: | ||
tornado dampers could lead to multiple failures in safety systems. | tornado dampers could lead to multiple failures in safety systems. | ||
This information notice requires no specific action or written response. If | This information notice requires no specific action or written response. | ||
If | |||
you have any questions about the information in this notice, please contact | you have any questions about the information in this notice, please contact | ||
| Line 298: | Line 364: | ||
original signed by | original signed by | ||
Dennis M. Crutchfield, Director | ===Dennis M. Crutchfield, Director=== | ||
Division of Reactor Program Management | |||
===Office of Nuclear Reactor Regulation=== | |||
Technical contacts: William T. LeFave, NRR | |||
(301) 415-3285 Internet:wtl1@nrc.gov | |||
===Thomas Koshy, NRR=== | |||
(301) 415-1176 Internet:txk@nrc.gov | |||
Attachment: | |||
===List of Recently Issued NRC Information Notices=== | |||
Tech Editor Reviewed 10/05/95 DOCUMENT NAME: | |||
96-06.IN | |||
*SEE PREVIOUS CONCURRENCES | |||
To receive a copy of this document, hIdicate In the box: wC" - Copy without enclosures 'E' | |||
- Copy with enclosures "N" - | |||
No copy | |||
OFFICE | |||
SPLB/DSSA | |||
PECB/DRPM | |||
C/PECB:DRPM | |||
INAME | |||
WTLeFave* | |||
ITKoshy* | |||
AChaffee* | |||
Dtfkidhfield | |||
I | |||
DATE | |||
10/11/95 | |||
01/04/96 | |||
01/17/96 | |||
01/9/96 | |||
01/ /96 | |||
===OFFICIAL RECORD COPY=== | |||
IN 96-xx | IN 96-xx | ||
| Line 346: | Line 436: | ||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
Dennis M. Crutchfield, Director | ===Dennis M. Crutchfield, Director=== | ||
Division of Reactor Program Management | Division of Reactor Program Management | ||
Office of Nuclear Reactor Regulation | ===Office of Nuclear Reactor Regulation=== | ||
Technical contacts: | |||
Technical contacts: | |||
===William T. LeFave, NRR=== | |||
(301) 415-3285 Internet: wtl1@nrc.gov | (301) 415-3285 Internet: wtl1@nrc.gov | ||
Thomas Koshy, NRR | ===Thomas Koshy, NRR=== | ||
(301) 415-1176 Internet: txk@nrc.gov | (301) 415-1176 Internet: txk@nrc.gov | ||
Attachment: | Attachment: | ||
DOCUMENT NAME: G:\IN\IN-DAMP | ===List of Recently Issued NRC Information Notices=== | ||
DOCUMENT NAME: G:\\IN\\IN-DAMP | |||
OFFICE 1SPLB/DSSA | |||
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DATE | |||
101/A | |||
/96 | |||
01/ 5 /96 e | |||
OFFICIAL RECORD COPY | 01/17 /96 e 01/ /96 | ||
- bee previous Concurrence OFFICIAL RECORD COPY | |||
I | |||
i; | |||
IN 96-xx | |||
January xx, 1996 They must then close to prevent rapid depressurization within the structures | January xx, 1996 They must then close to prevent rapid depressurization within the structures | ||
| Line 397: | Line 521: | ||
could lead to multiple failures in safety systems. | could lead to multiple failures in safety systems. | ||
This information notice requires no specific action or written r onse. If | This information notice requires no specific action or written r | ||
onse. If | |||
you have any questions about the information in this notice, p ase contact | you have any questions about the information in this notice, p ase contact | ||
one of the technical contacts listed below or the appropria Office of | one of the technical contacts listed below or the appropria | ||
Office of | |||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
Dennis M. Cr | Dennis M. Cr c | ||
hfield, Director | |||
===Division of eactor Program Management=== | |||
Office of uclear Reactor Regulation | Office of uclear Reactor Regulation | ||
Technical contacts: | Technical contacts: | ||
(301) 415-3285 Thomas Koshy, | ===William T. LeFave, RR=== | ||
(301) 415-3285 Thomas Koshy, R | |||
(301) 415-117 Attachment: | (301) 415-117 Attachment: | ||
nnri | ===List of Recently Issued NRC Info ation Notices=== | ||
N | |||
NAME: G:\\IN\\IN-DAMP | |||
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NAME | NAME | ||
WTLeFave* | |||
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DATE | TECH ED/BCalure CMcCracken * | ||
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DATE | |||
10/11/95 | |||
10/11/9 | |||
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10/12/95 | |||
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DATE | ===DCrutchfield=== | ||
DATE | |||
11/29/95 4 | |||
10/12A5 5 | |||
01/ | |||
/96 | |||
01/ /96 | |||
* See previous G currence | * See previous G currence | ||
OFFICIAL RECORD COPY | ===OFFICIAL RECORD COPY=== | ||
IN 95-xx | IN 95-xx | ||
| Line 484: | Line 669: | ||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
Dennis M. Crutchfield, Director | ===Dennis M. Crutchfield, Director=== | ||
Division of Reactor Program Management | |||
===Office of Nuclear Reactor Regulation=== | |||
Technical contacts: | |||
===William T. LeFave, NRR=== | |||
(301) 415-3285 | |||
===Thomas Koshy, NRR=== | |||
(301)415-1176 Attachments: | |||
1. Referenced Codes and Standards2 | |||
2. List of Recently Issued NRC Information Notices | |||
DOCUMENT NAME: G:\\IN\\IN-DAMP | |||
OFFICE | |||
SPLB/DSSA | |||
l E SC:SPLB/DSSA | |||
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ADM:PUB* I N BC:SPLB/DSSA I C IRIV/DRS I N | |||
NAME | |||
WTLeFave* | |||
GHubbard * | |||
TECH ED/BCalure CMcCracken * | |||
DATE | |||
10/11/95 | |||
110/11/95 | |||
10/05/95 | |||
10/12/95 | |||
/ /95 OFFICE .EBDRML | |||
SOCB/OPSIE | |||
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===DCrutchfield=== | |||
DATE | |||
11/29/95 ' | |||
10/12/95 | |||
/ | |||
1 / /95 | |||
/ /95 | |||
* See previous Concurrence | |||
I | |||
OFFICIAL RECORD COPY | OFFICIAL RECORD COPY | ||
zmy- | |||
2 See Exhibit 24 for the format to be used when codes or standards are | |||
referenced in the information notice. | referenced in the information notice. | ||
| Line 536: | Line 770: | ||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
Dennis M. Crutchfield, Director | ===Dennis M. Crutchfield, Director=== | ||
Division of Reactor Program Management | |||
===Office of Nuclear Reactor Regulation=== | |||
Technical contacts: | |||
===William T. LeFave, NRR=== | |||
(301) 415-3285 Thomas Koshy, | |||
(301)415-1176 NRR | |||
Attachments: | |||
1. Referenced Codes and Standards2 | |||
2. List of Recently Issued NRC Information Notices | |||
DOCUMENT NAME: | |||
G:\\IN\\IN-DAMP | |||
OFFICE jSPLB/DSSA | |||
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NAME | |||
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TECH ED/BCalure CMcCracken * | |||
DATE | |||
10/11/95 | |||
10/11/95 | |||
10/05/95 | |||
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/ /95 | |||
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* See previous ConcurrenceC)FFICIAL RECORD COPY | |||
2 See Exhibit 24 for the format to be used when codes or standards are | 2 See Exhibit 24 for the format to be used when codes or standards are | ||
| Line 585: | Line 868: | ||
referenced in the information notice. | referenced in the information notice. | ||
I . | I . | ||
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1- IN 95-xx | |||
October xx, 1995 depressurization within the structures and HVAC ductwork and then reopen after | October xx, 1995 depressurization within the structures and HVAC ductwork and then reopen after | ||
| Line 605: | Line 896: | ||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
Dennis M. Crutchfield, Director | ===Dennis M. Crutchfield, Director=== | ||
Division of Reactor Program Management | |||
===Office of Nuclear Reactor Regulation=== | |||
Technical contacts: | |||
===William T. LeFave, NRR=== | |||
(301) 415-3285 | |||
===Thomas Koshy, NRR=== | |||
(301)415-1176 Attachments: | |||
1. Referenced Codes and Standards2 | |||
2. List of Recently Issued NRC Information Notices | |||
OFFICE | |||
SPLB/DSSA | |||
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NAME | |||
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TECH ED/BCalure CMcCracken * | |||
DATE | |||
110/11/95 | |||
10/11/95 | |||
10/05/95 | |||
10/12/95 I | |||
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10/12/95 11&& L | |||
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I / /95 | |||
4%, I / /95 | |||
* See previous Concurrence | * See previous Concurrence | ||
OFFICIAL RECORD COPY | ===OFFICIAL RECORD COPY=== | ||
2 See Exhibit 24 for the format to be used when codes or standards are | 2 See Exhibit 24 for the format to be used when codes or standards are | ||
Latest revision as of 10:50, 16 January 2025
Nf
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C.
20555-0001
January 25, 1996
NRC INFORMATION NOTICE 96-06: DESIGN AND TESTING DEFICIENCIES OF TORNADO
DAMPERS AT NUCLEAR POWER PLANTS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the potential for inoperability of tornado
dampers because of either inadequacies in damper testing or deficiencies in
damper design.
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.
Description of Circumstances
On March 2, 1994, the licensee for South Texas Project, Unit 1, reported a
condition to the NRC that could result in the rapid depressurization of
heating, ventilation and air conditioning (HVAC) systems and buildings in the
event of a tornado (Licensee Event Report No.94-003). The licensee
discovered an interference between the plant exhaust vent tornado damper and a
gusset (duct work stru,..turdi stiffener).
The gusset limited the closing
travel of the damper linkage in one damper section to 40 percent of full
stroke, thus preventing the damper from closing completely. The interference
was discovered during stroke testing in response to an NRC inspector
observation that there was no testing evidence to show that tornado dampers
would actuate as required. In response to that observation, the licensee
initiated changes to existing preventive maintenance work instructions for all
tornado dampers (15 per unit) to include manual stroking on a periodic basis.
Only one of the 30 dampers subsequently tested was found to be inoperable.
The originally planned periodic maintenance of tornado dampers at 10-year
intervals did not include any stroke or motion testing.
South Texas stated that rapid depressurization could result in the collapse of
the HVAC duct work and could prevent cooling of safety-related equipment. The
rapid depressurization could also cause unanalyzed internal pressure
differential conditions that might result in damage to safety-related
structures, systems, or components.
PDfJR
A _oo
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6 s
9601190306 &H
b
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aog3t
21
IN 96-06 January 25, 1996 The licensee revised the preventive maintenance program to require preventive
maintenance on the tornado dampers every 2 years or at each refueling outage, depending on the specific damper function. The 2 year or refueling outage
check includes inspection, cleaning, lubricating, and stroking of the damper
while taking dynamometer measurements of the spring forces.
On October 22, 1993, the licensee for the River Bend Station reported a design
condition to the NRC (Licensee Event Report No.93-020) that could result in
loss of ventilation to several buildings after passage of a tornado.
The
licensee determined through static pressure testing, that the air-exhaust
dampers for several buildings would not reopen after passage of a tornado.
The failure to reopen results from inadequate spring force on dampers to
overcome exhaust fan shutoff pressure. This condition was applicable to the
diesel generator building, the auxiliary building, the control building, the
fuel building, and the standby cooling tower.
The licensee evaluation at the River Bend Station revealed that the postulated
tornado event could cause loss of offsite power and could prevent the
air-intake dampers for the diesel generator from reopening. Other plant areas
were less susceptible to damage because of design features and/or alarms, followed by operator actions that could mitigate the consequences.
The
air-exhaust tornado dampers in the diesel generator building were modified by
blocking them open. The licensee evaluated the equipment in the diesel
generator building and concluded that it would not be affected by
depressurization resulting from the tornado.
The licensee purchase specification for dampers required the dampers to be
capable of automatically returning to their normal operating position (open)
after the tornado passed.
However, the specification did not specify the
design-bases conditions on the inlet side of the exhaust tornado dampers.
The
static pressure that the damper counterweights would have to overcome was not
specified.
Discussion
Equipment such as tornado dampers may have been overlooked in development of
surveillance testing programs as tornado dampers are not generally considered
part of the HVAC system in which they are required to function. Tornado
dampers are more likely to be considered part of the structure in which they
are installed. Surveillance tests in the technical specifications may involve
damper operations during HVAC systems testing.
However, specific NRC
requirements or guidelines for damper testing in general are limited and do
not extend to tornado dampers.
Likewise, industry standards and guidelines
for testing of tornado dampers are also limited. Unlike other active safety- related dampers that are generally tested along with the HVAC system in which
they function, the licensees considered tornado dampers as passive devices
until they were called upon to perform their function.
'wO
IN 96-06 January 25, 1996 When called on, certain dampers must close to prevent rapid depressurization
within the structures and HVAC ductwork and then reopen after the tornado
passes.
In cases for which no redundancy exists, a single failure of a
tornado damper to perform its safety function could result in a loss of safety
system function. Therclore, absence of appropriate surveillance testing for
tornado dampers could lead to multiple failures in safety systems.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
4ennr .C r u t Coto
d rector
Division of Reactor rogram Management
Office of Nuclear Reactor Regulation
Technical contacts: William T. LeFave, NRR
(301) 415-3285 Internet:wtllenrc.gov
Thomas Koshy, NRR
(301) 415-1176 Internet:txk@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
tr
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Attachment
January 25, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
96-05
96-04
96-03
Partial Bypass of Shutdown
Cooling Flow from the
Reactor Vessel
Incident Reporting Require- ments for Radiography
Licensees
Main Steam Safety Valve
Setpoint Variation as a
Result of Thermal Effects
01/18/96
01/10/96
01/05/96
All holders of OLs or LPs
for boiling water reactors
All radiography licensees
and manufacturers of radio- graphy equipment
All holders of OLs or CPs
for nuclear power reactors
96-02 Inoperability of Power-
Operated Relief Valves
Masked by Downstream
Indications During Testing
01/05/96 All holders
for PWRs
96-01
95-58
95-57 Potential for High Post- Accident Closed-Cycle
Cooling Water Temperatures
to Disable Equipment
Important to Safety
10 CFR 34.20; Final
Effective Date
Risk Impact Study Regarding
Maintenance During Low-Power
Operation and Shutdown
01/03/96
12/18/95
12/18/95
All holders of OLs or CPs
for PWRs
Industrial Radiography
Licensees
All holders of OLs or CPs
for nuclear power reactors.
OL - Operating License
CP - Construction Permit
IN 96-06 January 25, 1996 When called on, certain dampers must close to prevent rapid depressurization
within the structures and HVAC ductwork and then reopen after the tornado
passes. In cases for which no redundancy exists, a single failure of a
tornado damper to perform its safety function could result in a loss of safety
system function. Therefore, absence of appropriate surveillance testing for
tornado dampers could lead to multiple failures in safety systems.
This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
original signed by
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: William T. LeFave, NRR
(301) 415-3285 Internet:wtl1@nrc.gov
Thomas Koshy, NRR
(301) 415-1176 Internet:txk@nrc.gov
Attachment:
List of Recently Issued NRC Information Notices
Tech Editor Reviewed 10/05/95 DOCUMENT NAME:
96-06.IN
- SEE PREVIOUS CONCURRENCES
To receive a copy of this document, hIdicate In the box: wC" - Copy without enclosures 'E'
- Copy with enclosures "N" -
No copy
OFFICE
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DATE
10/11/95
01/04/96
01/17/96
01/9/96
01/ /96
OFFICIAL RECORD COPY
IN 96-xx
January xx, 1996 They must then close to prevent rapid depressurization within the structures
and HVAC ductwork and then reopen after the tornado passes. In cases for
which no redundancy exists, a single failure of a tornado damper to perform
its safety function could result in a loss of safety system function.
Therefore, absence of appropriate surveillance testing for tornado dampers
could lead to multiple failures in safety systems.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
William T. LeFave, NRR
(301) 415-3285 Internet: wtl1@nrc.gov
Thomas Koshy, NRR
(301) 415-1176 Internet: txk@nrc.gov
Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\\IN\\IN-DAMP
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IN 96-xx
January xx, 1996 They must then close to prevent rapid depressurization within the structures
and HVAC ductwork and then reopen after the tornado passes. In cases for
which no redundancy exists, a single failure of a tornado damper to perform
its safety function could result in a loss of safety system function.
Therefore, absence of appropriate surveillance testing for tornado dampe
could lead to multiple failures in safety systems.
This information notice requires no specific action or written r
onse. If
you have any questions about the information in this notice, p ase contact
one of the technical contacts listed below or the appropria
Office of
Nuclear Reactor Regulation (NRR) project manager.
Dennis M. Cr c
hfield, Director
Division of eactor Program Management
Office of uclear Reactor Regulation
Technical contacts:
William T. LeFave, RR
(301) 415-3285 Thomas Koshy, R
(301) 415-117 Attachment:
List of Recently Issued NRC Info ation Notices
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NAME
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- See previous G currence
OFFICIAL RECORD COPY
IN 95-xx
December xx, 1995 They must then close to prevent rapid depressurization within the structures
and HVAC ductwork and then reopen after the tornado passes. In cases for
which no redundancy exists, a single failure of a tornado damper to perform
its safety function could result in a loss of safety system function.
Therefore, absence of appropriate surveillance testing for tornado dampers
could lead to multiple failures in safety systems.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
William T. LeFave, NRR
(301) 415-3285
Thomas Koshy, NRR
(301)415-1176 Attachments:
1. Referenced Codes and Standards2
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\\IN\\IN-DAMP
OFFICE
SPLB/DSSA
l E SC:SPLB/DSSA
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ADM:PUB* I N BC:SPLB/DSSA I C IRIV/DRS I N
NAME
WTLeFave*
GHubbard *
TECH ED/BCalure CMcCracken *
DATE
10/11/95
110/11/95
10/05/95
10/12/95
/ /95 OFFICE .EBDRML
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DATE
11/29/95 '
10/12/95
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- See previous Concurrence
I
OFFICIAL RECORD COPY
zmy-
2 See Exhibit 24 for the format to be used when codes or standards are
referenced in the information notice.
IN 95-xx
December xx, 1995 depressurization within the structures and HVAC ductwork and then reopen after
the tornado passes. In cases which no redundancy exists, a single failure of
a tornado damper to perform its safety function could result in a loss of
safety system function. Therefore, absence of appropriate surveillance
testing for tornado dampers could lead to multiple failures in safety systems.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
William T. LeFave, NRR
(301) 415-3285 Thomas Koshy,
(301)415-1176 NRR
Attachments:
1. Referenced Codes and Standards2
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME:
G:\\IN\\IN-DAMP
OFFICE jSPLB/DSSA
I E SC:SPLB/DSSA I N ADM:PUB* I N BC:SPLB/DSSA I C RIV/DRS I N
NAME
WTLeFave*
GHubbard *
TECH ED/BCalure CMcCracken *
DATE
10/11/95
10/11/95
10/05/95
10/12/95 I /95
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DATE
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- See previous ConcurrenceC)FFICIAL RECORD COPY
2 See Exhibit 24 for the format to be used when codes or standards are
referenced in the information notice.
I .
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1- IN 95-xx
October xx, 1995 depressurization within the structures and HVAC ductwork and then reopen after
the tornado passes. In cases which no redundancy exists, a single failure of
a tornado damper to perform its safety function could result in a loss of
safety system function. Therefore, absence of appropriate surveillance
testing for tornado dampers could lead to multiple failures in safety systems.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
William T. LeFave, NRR
(301) 415-3285
Thomas Koshy, NRR
(301)415-1176 Attachments:
1. Referenced Codes and Standards2
2. List of Recently Issued NRC Information Notices
OFFICE
SPLB/DSSA
E SC:SPLB/DSSA I N ADM:PUB* I N BC:SPLB/DSSA I C RIV/DRS I N
NAME
jWTLeFave*
GHubbard *
TECH ED/BCalure CMcCracken *
DATE
110/11/95
10/11/95
10/05/95
10/12/95 I
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- See previous Concurrence
OFFICIAL RECORD COPY
2 See Exhibit 24 for the format to be used when codes or standards are
referenced in the information notice.