Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection TanksML031050497 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/26/1997 |
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From: |
Slosson M Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-97-040, NUDOCS 9706230168 |
Download: ML031050497 (12) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
v>
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 June 26, 1997 NRC INFORMATION NOTICE 97-40: POTENTIAL NITROGEN ACCUMULATION
RESULTING FROM BACKLEAKAGE FROM SAFETY
INJECTION TANKS
Addressees
All holders of operating licenses or construction permits for pressurized-water reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to potential nitrogen accumulation in interfacing systems resulting from
backleakage from safety injection tanks (SITs). 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
Waterford
On November 19 and 21, 1996, Waterford Generating Station, Unit 3, experienced
waterhammer events on the low-pressure safety injection (LPSI) B train. On November 19,
1996, the control room pressure gauge was observed to spike to approximately 3.55 MPa
[500 psig] (normal operating pressure is approximately 1.2 MPa [160 psig]). On
November 21, 1996, the train B piping was vented, and a strip chart recorder was installed to
monitor pressure. A pressure of 4.65 MPa [660 psig] was observed following the start of the
pump. Shortly thereafter, the LPSI train B flow control valve was found partially open
because of a valve mispositioning error by the operations crew. The valve was closed, and
the pump started without a pressure transient. Apparently no structural damage resulted
from the waterhammer events.
On December 13, 1996, LPSI train A experienced a waterhammer event. During a routine
surveillance run of LPSI pump A, the pressure spiked to approximately 2.3 MPa [317 psig].
The licensee's investigation after this event utilized ultrasonic testing (UT) to inspect high
points in the LPSI piping. The licensee identified gas voiding in the horizontal run of the two
A train injection lines of 30.5 cm [12 inches] and 35.5 cm [14 inches) of arc. The injection
lines are 20 cm [8 inches] in diameter. The gas was sampled and found to be approximately
97 percent nitrogen. The licensee concluded that nitrogen-saturated water from the SIT (the
0t IaoTIS 91 o-00 976 Q424 tdX9{1lll70623]llll~ll~ll0168l~! 8 O
aS tC 3 C
IN 9740
June 26, 1997 The gas was vented from the A train of LPSI, and LPSI was declared operable on
December 14, 1996. On December 18, 1996, voiding was found in LPSI train B piping, with
arcs of 28 cm (11 inchesl and 25.4 cm [10 inches]. Because of the location of these gas
pockets, the licensee was unable to vent these lines. The licensee performed an operability
evaluation and concluded that the B train remained operable but instituted a UT surveillance
program to inspect the voids every 3 days and identified acceptance criteria for an
acceptable arc length. Furthermore, the licensee was pursuing a design modification to
install high-point vents.
In February 1997, the licensee noted that one of its SITs was experiencing a lowering in
level. Upon investigation, the licensee found that a LPSI system containment isolation valve
was off its shut seat. The licensee surmised that water was leaking from the SIT past check
valves and the partially open isolation valve in the LPSI to the refueling water storage pool
(RWSP). On February 20, 1997, the licensee conducted testing on the isolation valve to
investigate why the valve was not shut. The licensee cycled the valve several times during
the course of this testing. At the completion of the testing, the licensee performed UT of the
A LPSI injection line to check for voiding.
The licensee found that the high horizontal run of piping was dry and that a void extended
203 cm [80 inches) down the vertical run of piping. In response to the large void, the
licensee used a vacuum pump to draw water into the line until the voiding was reduced to a
12.7-cm [5-inch] arc. The reduced arc was within the licensee's acceptance criteria for this
line, and LPSI was declared operable.
The licensee also postulated that the shutdown cooling heat exchanger isolation valves may
be susceptible to waterhammer-induced pressure locking. The isolation valves had been
previously evaluated for a trapped bonnet pressure of 2.2 MPa [300 psig] and found to be
operable. However, there is no assurance that bonnet pressure would not exceed 2.2 MPa
[300 psig] when subjected to a waterhammer pressure surge. There is no evidence that this
pressure locking has occurred in the past, and the licensee believes that this scenario is
unlikely. However, the postulated phenomenon could result in common-mode failure of the
heat exchangers, and the licensee has installed bonnet pressure relief devices.
Sequoyah
In January 1995, during a Sequoyah Unit I scheduled quarterly residual heat removal (RHR)
pump test, a loud metallic noise was heard and movement of the refueling water storage tank
(RWST) suction piping was observed. At the time when the noise was heard and pipe
movement observed, personnel were performing a walkdown of a previously identified
damaged RHR pipe hanger. The RHR system piping was subsequently inspected for gas
voids and approximately .23 cubic meters (8 cubic feet] of gas was identified. A sample
taken of the vented gas determined the gas to be approximately 98 percent nitrogen. The
license believed that the source of the gas was one or more of the Emergency Core Cooling
System (ECCS) Cold Leg Accumulators (CLA) and that there were two potential leakage
IN 97-40
June 26, 1997 paths that water could travel from the CLAs to the RHR injection piping where the nitrogen
gas came out of solution: through the Safety Injection System (SIS) test header and/or
through the secondary check valves on the RHR cold leg Injection lines to the Reactor
Coolant System (RCS). The licensee performed an operability evaluation which determined
that the gas did not affect operability of the RHR system either in normal or accident
conditions.
Over the course of the next several months the licensee periodically vented the RHR piping, monitored the rate of gas accumulation and calculated the gas volume in the RHR piping, and tracked the level decrease of the CLAs. To date, the licensee has not been successful
in identifying and correcting leaking isolation valves in the SIS test header. The Sequoyah
RHR system design and layout may have contributed to the gas accumulation due to the lack
of high point vents in the RHR system and the difficult accessibility of those vents which
were available. In November 1996, the licensee installed a manual vent in the Unit 1 A train
RHR system in a 49 meter 1160 footl section of piping which previously was not completely
ventable.
In October 1996, an analysis of the Unit 1 RHR piping system was performed to determine
the imposed forces resulting from system operation with various volumes of gas in the piping
system. The analysis concluded that the hydraulic forces built up are higher with increasing
volumes of gas but level off when the gas volumes go beyond more than .28 cubic meters
[10 cubic feet). The measured volumes of gas in the Unit 1 RHR system have varied from
approximately .23 cubic meters [8 cubic feet] to .4 cubic meters [14 cubic feet]. The licensee
also calculated that for each gallon of water released from the CLAs, approximately 2.1 liters
[0.073 cubic feet] of gas is released.
Discussion
If SITs or CLAs lose water level, nitrogen gas accumulation could be occurring in interfacing
systems. The presence of large amounts of gas in discharge piping creates the possibility of
waterhammer with potentially significant consequences. Waterhammer of sufficient magni- tude can cause common-mode failure of safety injection trains. Structural failure of the
discharge piping could create a containment bypass release path in addition to preventing
safety injection flow. Additionally, a waterhammer event could potentially cause pressure
locking in some valves. A plant's susceptibility to nitrogen accumulation in the ECCS lines is
dependent on a number of plant-specific factors, including operating pressure of the SITs or
CLAs, elevations and orientation of ECCS injection lines, and the elevation of the RWSP or
RWST. Licensees may wish to evaluate the possibility and effect of gas accumulation on
potentially susceptible systems. Licensees may also wish to evaluate the design of these
systems to ensure adequate venting capability.
IN 97-40
June 26, 1997 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.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Robert D. Starkey, RII Christopher Jackson, NRR
(423) 842-8001 301-415-2947 E-mail: drs@nrc.gov E-mail: cpj@nrc.gov
Phillip Harrell, RIV John Tappert, NRR
(817) 860-8250 301415-1167 E-mail: phhenrc.gov E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
f " F6. (aJ % C-1 Zt- -- JAC46-f-
Attachment
IN 97-40
June 26, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-39 Inadequate 10 CFR 72.48 06/26/97 All holders of OLs or CPs
Safety Evaluations of for nuclear power reactors.
Independent Spent Fuel All holders of licenses for
Storage Installations independent spent fuel
storage installations
97-38 Level-Sensing System 06/24/97 All holders of OLs or CPs
Initiates Common-Mode for nuclear power reactors
Failure of High-Pressure- Injection Pumps
96-53, Retrofit to Amersham 660 06/23/97 All industrial radiography
Supp. 1 Posilock Radiography licensees
Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility
97-37 Main Transformer Fault 06/20/97 All holders of OLs or CPs
with Ensuing Oil Spill for nuclear power reactors
into Turbine Building
97-36 Unplanned Intakes by 06/20/97 All holders of OLs and CPs
Worker of Transuranic permits. All licensees of
Airborne Radioactive of nuclear power reactors
Materials and External in the decommissioning
Exposure Due to Inadequate stage and fuel cycle
Control of Work
97-35 Retrofit to Industrial 06/18/97 All industrial radiography
Nuclear Company (INC) licensees
IR100 Radiography Camera
to Correct Inconsistency
in 10 CFR Part 34 Compatibility
OL = Operating License
CP = Construction Permit
..
K> K>
IN 97-40
June 26, 1997 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 S. H. Weiss for
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Robert D. Starkey, RII Christopher Jackson, NRR
(423) 842-8001 301-415-2947 E-mail: drs@nrc.gov E-mail: cpj@nrc.gov
Phillip Harrell, RIV John Tappert, NRR
(817) 860-8250 301-415-1167 E-mail: phh@nrc.gov E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 3131/97 DOCUMENT NAME: 97-40.IN
OFFICE Contacts C/SRXB:DSSA C/PECB:DRPM (A)DIDRPM
NAME RStarkey JLyons* AChaffee* MSlosson
CJackson* lu I
PHarrell* fa
_ _ JTappert*
DATE 04/22/87 05/11/97 06/04/97 06t097 Official Rec ord Copy
IN 97-xx
June xx, 1997 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.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Robert D. Starkey, Ril Christopher Jackson, NRR
(423) 842-8001 301-415-2947 E-mail: drs@nrc.gov E-mail: cpj@nrc.gov
Phillip Harrell, RIV John Tappert, NRR
(817) 8604250 301415-1 167 E-mail: phh@nrc.gov E-mail: jrtenrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 3/31/97 DOCUMENT NAME: G:URT1N2VOID.IN
OFFICE Contacts C/SRXB:DSSA CIPECB:DRPM (A)D/DRPM
NAME RStarkey JLyons* AChaffee MSlosson
CJackson*
PHarrell*
_ JTappert2 05111/97 5/____51_/97 DAE 04/22/87 105/11/97 5/ /97 15/ /97 _J
ufciaal ecora Copy
19kW 6/3&/9 7
K2 IN 97-xx
May xx, 1997 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.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Robert D. Starkey, RII Christopher Jackson, NRR
(423) 842-8001 (301) 415-2947 E-mail: drs@nrc.gov E-mail: cpj@nrc.gov
Phillip Harrell, RIV John Tappert, NRR
(817) 860-8250 (301) 415-1167 E-mail: phh@nrc.gov E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 3131/97 DOCUMENT NAME: G:VRTN2VOID.IN
OFFICE Contacts C/SRXB:DSSA C/PECB:DRPM (A)D/DRPM
NAME RStarkey JLyons*AChaffee MSlosson
CJackson*
PHarrell*
JTappert* _
DATE 04/22/87 05111/97 5/ 197 5/ 197 Official Record Copy Ad
IN 97-xx
May xx, 1997 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 manage
Marylee M. Slosson, Acting Direor
Division of Reactor Program nagement
Office of Nuclear Reactor gulation
Technical contacts: Robert D. Starkey, RII Christopher Jac on, NRR
(423) 842-8001 (301) 415-29 E-mail: drs@nrc.gov E-mail: cpj nrc.gov
Phillip Harrell, RIV John appert, NRR
(817) 860-8250 (30 415-1167 E-mail: phh@nrc.gov E ail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Inform tion Notices
Tech Editor reviewed 3/3147 DOCUMENT NAME: G: ThN2VOID.IN
OFFICE Contacts / CISRXB:DSSA C/PECB:DRPM (A)DIDRPM
NAME RStarkey JLyons* AChaffee MSlosson
CJacks
PHarre
l__ _ JTap rt*_
DATE 042/87 05/11/97 5//97 5/ 197
";_1! Darr ... f%._
Iffnciai rneuru %'VPY 0
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i"
!'J' 5 14^ 1, V
IN 97-xx
May xx, 1997 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 age
Marylee M. Slosson, Acting irector
Division of Reactor ProgrT Management
Office of Nuclear Rea r Regulation
Technical contacts: Robert D. Starkey, RII Christophe ackson, NRR
(423) 842-8001 (301) 41 -2947 E-mail: drs@nrc.gov E-maillcpjnrc.gov
Phillip Harrell, RIV ohn Tappert, NRR
(817) 860-8250 (301) 415-1167 E-mail: phh@nrc.gov E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NR nformation Notices
Tech Editor revie ed 3/31/97 DOCUMENT N ME: G:URTRN2VOID.IN
OFFICE I ntacts C/SRXB:DSSA CIPECB:DRPM D/DRPM
NAME /RStarkey JLyons* AChaffee TMartin
CJackson*
/ PHarreli*
JTappert*
DATE 04/22/87 05111/97 Official Record Co
3W4497
%I%.
- -1/
J K> IN 97-xx
May xx, 1997 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.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Robert D. Starkey, Region II Christopher Jackson, NRR
(423) 842-8001 (301) 415-2947 E-mail: drs@nrc.gov E-mail: cpjenrc.gov
Phillip Harrell, Region IV John Tappert, NRR
(817) 860-8250 (301) 415-1167 E-mail: phhenrc.gov E-mail: jrtenrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 3131/97 DOCUMENT NAME: G:AJRTNN2VOID.IN
OFFICE Contacts C/SRXB:DSSA CIPECB:DRPM DIDRPM
NAME RStarkey JLyons* AChaffee TMartin
CJackson*
PHarrell*
JTappert*
DATE 04122/87 05/11/97 'J13 I
Official Record Copy
v-e K>
IN 97-xx
April xx, 1997 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.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Robert D. Starkey, Region II Christopher Jackson, NRR
(423) 842-8001 (301) 415-2947 E-mail: drs@nrc.gov E-mail: cpj@nrc.gov
Phillip Harrell, Region IV John Tappert, NRR
(817) 860-8250 (301) 415-1167 E-mail: phh@nrc.gov E-mail: jrt@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 3/31/97 DOCUMENT NAME: G:\JRT\N2VOID.IN
OFFICE Contacts C/SRXB:DSSA C/PECB: DRPM D/DRPM
NAME RStarkey -$1YA'J'JLo4 I L144 AChaffee TMartin
CJacksonV elII
PHarrel ^1A X
JTappert __ __I_ _ _ _
DATE . Copy
uticial Heord Copy
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake, Uranium Hexafluoride)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
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