Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor SitesML031060295 |
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 |
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Issue date: |
06/05/1995 |
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From: |
Grimes B, Travers W NRC/NMSS/SFPO, Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-95-028, NUDOCS 9506010112 |
Download: ML031060295 (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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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555-0001 June 5, 1995 NRC INFORMATION NOTICE 95-28: EMPLACEMENT OF SUPPORT PADS FOR SPENT FUEL DRY
STORAGE INSTALLATIONS AT REACTOR SITES
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Independent spent fuel storage installation designers and fabricators.
Purpose
-
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the importance of complying with all conditions
and requirements specified in Section 72.212(b) of Title 10 of the Code of
Federal Regulations (10 CFR 72.212(b)) and other applicable NRC regulations
before using certified casks under the provisions of the general license under
10 CFR Part 72 for the dry storage of spent fuel. It is expected that the
recipients will review this information notice for applicability to their
facilities and consider actions, as appropriate. However, suggestions
contained in this information notice are not NRC requirements; therefore, no
specific action or written response is required.
Background
The NRC reviews and approves cask designs for use in storing spent fuel under
a general license as stated in Subpart L of 10 CFR Part 72. Approved cask
designs are listed in Subpart K of 10 CFR Part 72, (10 CFR 72.214), and a
certificate of compliance is issued to the cask designer after the rulemaking
approving the cask design is completed. Once a cask design has been certified
and casks fabricated, casks may be used to store spent-fuel at nuclear power
- reactor sites in accordance with Subpart K of 10 CFR Part 72. Such a license
is only available to utilities that hold a license to possess or operate a
power reactor under 10 CFR Part 50.
Before storing spent fuel under the general license, reactor facility
licensees must meet the requirements stated in 10 CFR 72.212(b). Notably, they must--
- Determine and document that storage activities are in accordance
with the provisions and conditions of the certificate of compliance
for the cask.
- Ensure that reactor site parameters, including any external hazards, are enveloped by the design-basis values established in the cask
9506010112 fDR EVtE Dulcet o
0cqc o(S 2OO
IN 95-28 June 5, 1995 design safety analysis report referenced in the certificate of
compliance and the related NRC safety evaluation report.
- Determine whether cask use will involve a reactor facility
unreviewed safety question or a change to the facility technical
specifications (10 CFR 50.59).
- Review and modify the reactor facility quality assurance program, security program, emergency plan, training program, and radiation
control program to include spent fuel storage activities as
appropriate.
- Develop reactor facility written operating procedures for cask
handling and storage operations.
This information notice discusses circumstances regarding the emplacement of
spent fuel dry storage cask pads.
Spent fuel storage cask designs are analyzed for normal, off-normal, and
accident conditions, including tip-over and cask drop accidents. In instances
where the pad supporting the casks, including the foundation beneath the pad, is not relied upon to perform a safety function, it is not treated as safety
related or as important to safety. The cask design safety analysis report
does not analyze for the effects of earthquakes, soil stability, or erosion on
the cask pad and foundation.
However, 10 CFR 72.212(b)(2) requires that the general licensee ensure that,
'cask storage pads and areas have been designed to adequately support the
stati(c] load of the stored casks." Section 72.212(b)(3) states that the
licensee shall, determine whether or not the reactor site parameters, including analyses of earthquake intensity and tornado missiles, are enveloped
by the cask design bases." The holder of a general license performs these
evaluations to ensure that the design and construction of the cask storage pad
is adequate to support the static load of the fully loaded storage casks. In
addition, if potential conditions exist at the reactor site that could
unacceptably diminish cask safety by any credible means, then the licensee
must evaluate the potential conditions to verify that impairment of cask
safety is highly unlikely. These evaluations are reviewed during NRC
inspections and audits of licensee operations.
Description of Circumstances
During its initial siting analysis for dry spent fuel storage at the Palisades
facility, Consumers Power Company (the licensee) noted that the peak ground
acceleration used in the initial analysis for siting the power plant was 0.2g.
The design-basis ground motion for the spent fuel dry storage casks is a peak
ground acceleration of 0.25g. Therefore, the licensee determined that the
safe shutdown ground acceleration of the site was enveloped by the design
basis for the cask. No additional analyses were performed for the siting
analysis at that time.
IN 95-28 June 5, 1995 Since the Palisades plant is in close proximity to Lake Michigan, questions
were raised by the NRC staff and interested members of the public regarding
the possible effects of earthquakes on soil liquefaction, wind and wave
effects on ground erosion, and the effects of these phenomena on the cask
support pad and the spent fuel storage casks.
As a result of these questions, the licensee performed a detailed analysis of
the effects of soil erosion, including the effects of high lake waves, wind, and rain on the cask support pad. In addition, the licensee analyzed the
effect of a safe shutdown earthquake (SSE) on soil and foundation stability, based on both existing soil data and new data acquired from additional soil
borings taken in response to the questions regarding the stability of the pad
site.
Other questions addressed by the review included the following:
- Whether there had been any changes in the general site conditions
since the submittal of the environmental impact statement for
licensing of the facility (e.g., stability of site topography and
wind erosion concerns).
- Whether there was sufficient vertical and horizontal separation
between Lake Michigan and the pad location to provide a conservative
margin against wave-driven erosion.
- Whether the cask support pad had been analyzed for the SSE peak
ground acceleration defined for the Palisades site.
- Whether the geologic and seismological analyses had been properly
performed.
The results of the licensee analysis showed that the pad could support the
casks safely. These results are documented in a letter to the NRC dated July
27, 1994.
NRC independently reviewed the licensee analyses of the soil liquefaction
effects on pad integrity, the pad design and construction, and the stability
of slopes surrounding the pad to determine both the long-term effects of
erosion under normal conditions and the effects of a postulated earthquake.
This independent analysis also concluded that the cask pad would adequately
support the cask as required by 10 CFR 72.212. The NRC independent assessment
of the licensee analysis is documented in the "Independent NRC Staff Final
Safety Assessment of the Dry Spent Fuel Cask Storage Facility at Palisades
Nuclear Power Plant Site," dated September 20, 1994.
Discussion
Potential dry cask storage users are required by 10 CFR 72.212 to perform
written evaluations, before use, that establish that the conditions for using
NRC-approved spent fuel storage casks set forth in the certificate of
compliance have been met. These evaluations include review of the cask design
IN 95-28 June 5, 1995 safety analysis report and the related NRC safety evaluation report to ensure
that the reactor site parameters are enveloped by the cask design bases. The
licensee is also required to perform a written evaluation that ensures that
the cask storage pad and areas are designed to support the static load of the
stored cask. The effects of a postulated earthquake based on the earthquake
ground motion used for the plant design-basis SSE is valid for the storage
casks without further analysis only if the foundation geology for the cask pad
is the same as that for the plant. A different soil amplification resulting
from SSE ground motion at the pad site could result in exceeding the cask
design basis.
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.
rian . Grimes, rector William D. Travers irector
Division of Project Support Spent Fuel Program Office
Office of Nuclear Reactor Office of Nuclear Material
Regulation Safety and Safeguards
Technical contacts: F. Sturz, NMSS
(301) 415-7278 M. Gamberoni, NRR
(301) 415-3024 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
Attachment I
IN 95-28 June 5, 1995 Page I of I
LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-25 Valve Failure during 05/11/95 All U.S. Nuclear Regulatory
Patient Treatment with Commission Medical
Gamma Stereotactic Licensees.
Radiosurgery Unit
94-64, Reactivity Insertion Trans- 04/06/95 All holders of OLs or CPs
Supp. 1 ient and Accident Limits for Nuclear Power Reactors
for High Burnup Fuel and all fuel fabrication
licensees.
95-07 Radiopharmaceutical Vial 01/27/95 All U.S. Nuclear Regulatory
Breakage during Preparation Commission medical licensees
authorized to use byproduct
material for diagnostic
procedures.
95-01 DOT Safety Advisory: 01/04/95 All U.S. Nuclear Regulatory
High Pressure Aluminum Commission licensees.
Seamless and Aluminum
Composite Hoop-Wrapped
Cylinders
94-89 Equipment Failures at 12/28/94 All U.S. Nuclear Regulatory
Irradiator Facilities Commission irradiator
licensees.
89-25, Unauthorized Transfer of 12/07/94 All fuel cycle and material
Rev. 1 Ownership or Control of licensees.
Licensed Activities
94-81 Accuracy of Bioassay 11/25/94 All U.S. Nuclear Regulatory
and Environmental Commission licensees.
Sampling Results
93-60, Reporting Fuel Cycle 10/20/94 All 10 CFR Part 70
Supp. 1 and Materials Events to fuel cycle licensees.
the NRC Operations Center
Attachment 2 IN 95-28 June 5, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-27 NRC Review of Nuclear 05/31/95 All holders of OLs or CPs
Energy Institute, for nuclear power plants.
"Thermo-Lag 330-1 Combustibility Evaluation
Methodology Plant Screening
Guide'
95-26 Defect in Safety- 05/31/95 All holders of OLs or CPs
Related Pump Parts due for nuclear power reactors.
to Inadequate Heat
Treatment
94-61, Corrosion of William 05/25/95 All holders of OLs or CPs
Supp. 1 Power Gate Valve Disc for nuclear power reactors.
Holders
95-25 Valve Failure during 05/11/95 All U.S. Nuclear Regulatory
Patient Treatment with Commission Medical
Gamma Stereotactic Licensees.
Radiosurgery Unit
95-24 Summary of Licensed 04/25/95 All holders of OLs or CPs
Operator Requalification for nuclear power reactors.
Inspection Program
Findings
95-23 Control Room Staffing 04/24/95 All holders of OLs or CPs
Below Minimum Regulatory for nuclear power reactors
Requirements and all licensed operators
and senior operators at
those reactors.
95-22 Hardened or Contaminated 04/21/95 All holders of OLs or CPs
Lubricants Cause Metal for nuclear power reactors.
Clad Circuit Breaker
Failures
95-21 Unexpected Degradation 04/20/95 All holders of OLs or CPs
of Lead Storage Batteries for nuclear power reactors.
OL = Operating License
CP = Construction Permit
IN 95-28 June 5, 1995 safety analysis report and the related NRC safety evaluation report to ensure
that the reactor site parameters are enveloped by the cask design bases. The
licensee is also required to perform a written evaluation that ensures that
the cask storage pad and areas are designed to support the static load of the
stored cask. The effects of a postulated earthquake based on the earthquake
ground motion used for the plant design-basis SSE is valid for the storage
casks without further analysis only if the foundation geology for the cask pad
is the same as that for the plant. A different soil amplification resulting
from SSE ground motion at the pad site could result in exceeding the cask
design basis.
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.
orig /s/'d by EKGrimes orig /s/'d by WDTravers
Brian K. Grimes, Director William D. Travers, Director
Division of ProJect Support Spent Fuel Program Office
Office of Nuclear Reactor Office of Nuclear Material
Regulation Safety and Safeguards
Technical contacts: F. Sturz, NMSS
(301) 415-7278 M. Gamberoni, NRR
(301) 415-3024 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
DOCUMENT NAME: 95-28.IN
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OFFICE OECB/DOPS l ADM:PUB i I i C:ECGB/DE I E PD3-III I
NAME
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NAME EFGoodwin* RJKiessel* WTravers AEChaffee*
DATE 05/25/95 05/2595 05/31/95 2595 UttILIAL KtLUKU LuFT
" '~ IN 95-28 June 2, 1995 Page 4 of
that the reactor site parameters are enveloped by the cask desi bases. The
licensee is also required to perform a written evaluation that nsures that
the cask storage pad and areas are designed to support the st ic load of the
stored cask. The effects of a postulated earthquake based the earthquake
ground motion used for the plant design-basis SSE is valid or the storage
casks without further analysis only if the foundation geo ogy for the cask pad
is the same as that for the plant. A different soil am ification resulting
from SSE ground motion at the pad site could result in xceeding the cask
design basis.
This information notice requires no specific actio or written response. If
you have any questions about the information in t is notice, please contact
one of the technical contacts listed below.
orig /s/'d by BKGrimes orig /s/'d by WDTravers
Brian K. Grimes, Director 1liam D. Travers, Director
Division of Project Support Spent Fuel Program Office
Office of Nuclear Reactor Office of Nuclear Material
Regulation Safety and Safeguards
Technical contacts: F. Sturz, NMSS
(301) 415-7278 M. Gamberoni NRR
(301) 415-3 24 Attachments:
1. List of Recently Issued N S Information Notices
2. List of Recently Issued R Information Notices
DOCUMEN T NAME: 95-28.IN
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DATE 105/25/95 05/25/95 05/31/95 /_9 6/ 195 5____
UOFILIAL Kt.UKU buPT
IN 95-xx
May xx, 1995 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.
Brian K. Grimes, Director William D. Travers, Director
Division of Project Support Spent Fuel Program Office
Office of Nuclear Reactor Office of Nuclear Material
Regulation Safety and Safeguards
Technical contacts: urz, NMSS
(301) 415-7278 M. Gamberoni, NRR
(301) 415-3024 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
DOCUMENT NAME: G:\SSK2\ISFSIPAD.IN
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NAME jEFGoodwin* RJKiessel* WT rs/ AEChaffee* BKGrimes
DATE 105/25/95 05/25/95 05/n /9 05/25/95 05/ /95 OFFIClA RECORD COPY
IN 95-xx
May xx, 1995 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.
William D. Travers, Director
Spent Fuel Program Office
Office of Nuclear Material Safety
and Safeguards
Brian Grimes, Director
Division of Operational Programs
Office of Nuclear Reactor Regulation
Technical Contacts: Fritz Sturz, NMSS
(301) 415-7278 M. Gamberoni, NRR
(301) 415-3024 Attachmients:
1. Lis t of Recently Issued NMSS Information Notices
2. Lis t of Recently Issued NRR Information Notices
pr
DOCUMENT NAME: G:\SSK2\ISFSIPAD.IN E
"E Copy with
To receive a copy of this document, indicate in the box: "C" = Copy without atte ment/enclosure
attachment/enclosure ."I,, = No copy I I I
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DNAME EFGoodwi nAt J5 l RJKir05 95r05/ /Chaffee BKGrimes
lDATE 05/b--505AM950//5 5,~/95 05/ /95
K> IN 95-xx
May xx, 1995 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.
Brian K. Grimes, Director William D. Travers, Director
Division of Project Support Spent Fuel Program Office
Office of Nuclear Reactor Office of Nuclear Material
Regulation Safety and Safeguards
Technical Contacts: Fritz Sturz, NMSS
(301) 415-7278 M. Gamberoni, NRR
(301) 415-3024 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
DOCUMENT NAME: G:\SSK2\ISFSIPAD.IN "E" = Copy with
To receive a copy of this documernt, Indicate in the box: "C' = Copy without attachment/enctosure
a ittaclhmenhJ
n9,grLWu*u C - - .u .,WY
OFFICE OECB/DOPS TECH ED* :EGB/DPD3-III
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CK
JDATE 05/ /95 05/ /95 05/ /95 1 05/ /950 5/ 9
I , -- 1.
I) IN 95-xx
May xx, 1995 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.
William D. Travers, Director
Spent Fuel Program Office
Office of Nuclear Material Safety
and Safeguards
Brian Grimes, Director
Division of Operational Programs
Office of Nuclear Reactor Regulation
Technical Contacts: Fritz Sturz, NMSS
(301) 415-7278 M. Gamberoni, NRR
(301) 415-3024 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
DOCUMENT NAME: G:\SSK2\ISFSIPAD.IN
To receive a copy of this docunent, indicate in the box: 'IC"= Copy without attachment/enclosure "E"= Copy with
attachment/enclosure "U" I No copy
OFFICE OECB/DOPS I_ :TEH
ED IG C:ECGB/DE I lPD3-III I
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NAME SSKoenick IJ i LGBa chi GHMarcus l
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NAME
DATE
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05/ /95 jRJKiessel
05/ /95 WTravers
05/ /95 AEChaffee
105/ /95 BKGrimes
05/ /95
-
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak, Water hammer)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995, Topic: Operability Determination)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995, Topic: High Energy Line Break)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995, Topic: Feedwater Heater)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown, Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995, Topic: Hardened grease)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995, Topic: Overdose)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves, Overspeed trip)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995, Topic: Overspeed)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier, Overspeed trip)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995, Topic: Overspeed trip)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995, Topic: Overspeed)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995, Topic: Overspeed)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Operator Manual Action, Emergency Lighting, Exemption Request, Overspeed)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy, Underdose)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Commercial Grade, Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
... further results |
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