E-mail from H. Nieh, Oedo to A. Levin, Ocm, Et Al., Issuance of Information Notice 2002-13, Fwd: E-mail from D. Pickett T Davis-Besse Communication PlanML023570309 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
04/04/2002 |
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From: |
Ho Nieh NRC/EDO |
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To: |
Beall J, Croteau R, Gamberoni M, Hiltz T, Kerri Kavanagh, Levin A, Mccabe B, Sharkey J, Tschiltz M, Uhle J NRC/OCM |
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References |
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IN-02-013 |
Download: ML023570309 (7) |
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Category:E-Mail
MONTHYEARML23128A1612023-05-0808 May 2023 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing ML23086B9862023-03-27027 March 2023 NRR E-mail Capture - Davis-Besse, Unit No. 1 - Acceptance Review Results for Davis-Besse, Unit No. 1 - Proposed Alternative Request RP-5 ML23033A0322023-02-0101 February 2023 NRR E-mail Capture - Request for Additional Information for Davis-Besse's 2022 Steam Generator Inspection Report (L-2022-LRO-0115) ML22266A1102022-09-23023 September 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure ML22164A8572022-06-13013 June 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan ML22118A6862022-04-28028 April 2022 NRR E-mail Capture - 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Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Revise the Emergency Plan ML22040A1832022-02-0707 February 2022 LTR-22-0033 Tom Gurdziel, E-mail Event Number 55734 at Davis Besse, a Matter of Interpretation ML22034A9472022-02-0303 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Revised Review Estimates for Proposed Alternative to Extend the Steam Generator Weld Inspection Interval ML22033A0632022-02-0101 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Revise the Design Basis for the Shield Building Containment Structure ML21321A3782021-11-16016 November 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193 ML21321A3792021-11-16016 November 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML21287A0382021-10-14014 October 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of Requests for Relief from Certain Inservice Testing Requirements ML21271A1332021-09-28028 September 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of Proposed Alternative RR-A2 for Certain Steam Generator Weld Inspections ML21119A2152021-04-28028 April 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27 ML21041A5452021-02-10010 February 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20329A3832020-11-24024 November 2020 NRR E-mail Capture - Davis Besse Nuclear Power Station, Unit No. 1 - Request for an Exemption from the 2020 Force-on-Force Exercises ML20304A2842020-10-29029 October 2020 50.59 Inspection 2nd Request for Information ML20289A0992020-10-0505 October 2020 NRR E-mail Capture - Energy Harbor Fleet, Results of Acceptance Review Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, EPID-l-2020-LLR-0132 ML20281A3692020-10-0505 October 2020 Energy Harbor Fleet, Results of Acceptance Review Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, EPID-l-2020-LLR-0132 ML20239A7942020-08-25025 August 2020 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Incorporation of Applicable Standard in TS 5.2.2.e ML20203M3712020-07-21021 July 2020 Ultimate Heat Sink Request for Information Part 1 ML20203M3722020-07-21021 July 2020 Ultimate Heat Sink Request for Information Part 1 and Part 2 L-20-183, Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force2020-06-23023 June 2020 Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force ML20154K7642020-06-0202 June 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425 ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20058D3152020-02-27027 February 2020 Completion of License Transfer for the Beaver Valley, Davis-Besse and Perry Nuclear Units ML20024E0092020-01-23023 January 2020 NRR E-mail Capture - FENOC License Transfer - January 23, 2020 Call Summary ML20021A3162020-01-21021 January 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing ML19346B3972019-12-11011 December 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Adopt TSTF-425 ML19273A1132019-09-27027 September 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Acceptance of License Amendment Request to Extend Containment Leakage Rate Test Interval ML19179A1382019-06-28028 June 2019 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program ML19164A1532019-06-13013 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan ML19162A3922019-06-11011 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML19161A2132019-06-0606 June 2019 NRR E-mail Capture - Results of Acceptance Review - FENOC Fleet - Request for Approval of Request for Approval of Lrradiated Fuel Management Plans, EPID L-2019-LRO-0016 ML19149A6202019-05-29029 May 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Approval of the Decommissioning Quality Assurance Program ML19130A2082019-05-0808 May 2019 Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML19106A2512019-04-16016 April 2019 NRR E-mail Capture - Davis-Besse - Proposed License Condition and Draft Safety Evaluation for the License Amendment Request to Adopt NFPA 805 ML19073A1112019-03-14014 March 2019 NRR E-mail Capture - Davis-Besse - Acceptance of License Amendment Request for Permanently Defueled License and Technical Specifications ML19043A6962019-02-0808 February 2019 NRR E-mail Capture - Davis-Besse License Amendment Request for the Post-Shutdown Emergency Plan ML18320A1272018-11-16016 November 2018 NRR E-mail Capture - Davis-Besse LAR to Change TS Definitions and Administrative Controls for Permanently Defueled Conditions ML18282A1482018-10-0909 October 2018 NRR E-mail Capture - Results of Acceptance Review - FENOC Fleet - Request for Exemption Related to the Suspension of Security Measures in an Emergency or During Severe Weather, EPID L-2018-LLL-0016 ML18282A2422018-10-0808 October 2018 OEDO-18-00160, FENOC Fleet, 2.206 Petition, Submission of Supplement Dated October 8, 2018, from the Petitioners - PRB and Petitioners (Elpc), Includes Email, Cover Letter from Elpc, and the Attachments to the Email 2023-05-08
[Table view] |
SýM-ichae'-Tschiitz - Fwd: Issuace
lof"/nformat'on Notice 2002-13 Pagei
From: Ho Nieh
To: Alan Levin; Brian McCabe; James Beall; Jeffry Sharkey; Jennifer Uhle; Kerri
Kavanagh; Marsha Gamberoni; Michael Tschiltz; Rick Croteau; Thomas Hiltz
Date: Thu, Apr 4, 2002 2:28 PM
Subject: Fwd: Issuance of Information Notice 2002-13 For your info.
Ho
clO0 -o 046
F-Micha'e Tschiltz - Issuance of Information Notice 2002-13 Page 1 From: Douglas Pickett
To: Davis-Besse Com Plan
Date: Thu, Apr 4, 2002 1:58 PM
Subject: Issuance of Information Notice 2002-13 To the Davis-Besse Communications Team:
For your information, Information Notice 2002-13, "Possible Indicators of Ongoing Reactor Pressure
Vessel Head Degradation," was issued today.
Ea.tL - L, __.l.... -, .. .
iviicraei I scn11z - inTormation Noticeý~~~~~~~
.wDd
uu;-13 Ino I--_ - 2 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 April 4, 2002 NRC INFORMATION NOTICE 2002-13: POSSIBLE INDICATORS OF ONGOING
REACTOR PRESSURE VESSEL HEAD DEGRADATION
ADDRESSEES
All holders of operating licenses for pressurized water nuclear power reactors, except those
who have permanently ceased operations and certified that fuel has been permanently removed
from the reactor.
PURPOSE
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice on recent
Davis-Besse experience to alert addressees to possible indicators of reactor coolant pressure
boundary degradation including degradation of the reactor pressure vessel (RPV) head
material. The NRC anticipates that recipients will review this information for applicability to their
facilities and consider taking appropriate actions. However, the suggestions contained in this
information notice do not constitute NRC requirements and, therefore, no specific action or
written response is required.
DESCRIPTION OF CIRCUMSTANCES
The Davis-Besse nuclear power plant recently discovered a significant cavity in the RPV head
on the downhill side of control rod drive nozzle number 3 and some head wastage behind
nozzle number 2. In response, the NRC issued Information Notice 2002-11, "Recent
Experience With Degradation of Reactor Pressure Vessel Head," on March 12, 2002, and
Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure
Boundary Integrity," on March 18, 2002. NRC also sent an Augmented Inspection Team (AIT)
to the plant to investigate the circumstances of the degradation of the RPV head material.
Through the AIT, several possible indicators of reactor coolant pressure boundary degradation
such as was observed at Davis-Besse were identified. These indicators include unidentified
reactor coolant system (RCS) leakage and containment air cooler (CAC) and radiation element
(RE) filter fouling.
Until 1998, RCS unidentified leakage at Davis-Besse was normally less than 0.1 gallons per
minute (gpm). In October 1998, the licensee removed the rupture disks downstream of the
pressurizer relief valves and bypassed a drain line that collected leakage from the relief valves
in the quench tank (identified leakage). As a result, all leakage past the relief valves was
vented directly into the containment atmosphere and collected in the sump, increasing the
unidentified leakage to approximately 0.8 gpm. In May 1999, the licensee reinstalled the
ML020930617 IN 2002-13
........... .
.LMicnael I-scni!iz - InTormation Notice 2002-13.wpd P*n* 9
"Pn
- _ ! rupture disks and reconnected the drain line; however, the RCS unidentified leakage was only
reduced to approximately 0.2 gpm (or approximately 0.1 gpm higher than normal). This
elevated level of unidentified leakage was attributed by the licensee to control rod drive
mechanism (CRDM) flange leakage since the plant had a past history of flange leakage.
The Davis-Besse CACs control containment temperature and humidity. In November 1998, the
licensee identified increased CAC fouling caused by boron deposits. The licensee attributed
the increase in CAC fouling to the venting of the pressurizer relief valve leakage directly to
containment caused by the October 1998 modification discussed previously. The CACs were
cleaned many times between November 1998 and May 1999. In May 1999, the licensee
reinstalled the rupture disks and reconnected the drain line. After that modification, the
licensee cleaned the CACs again in June and July 1999. At that time, the licensee noticed that
the boric acid deposits removed from CAC number 1 exhibited a rust-like color. The licensee
attributed the discoloration to migration of the surface corrosion on the CACs into the boric acid
deposits and to the aging of the boric acid deposits. After the spring 2000 refueling outage, deposits again began to form on the CACs. Between June 2000 and May 2001, the licensee
cleaned the CACs eight times. No further CAC cleaning was needed until the current outage
when the licensee reported that fifteen 5-gallon buckets of boric acid were removed from the
CAC ductwork and plenum. A flow from the CACs also resulted in boric acid deposits
elsewhere within containment including on service water piping, stairwells, and other areas of
low ventilation.
Davis-Besse also has REs that are two identical air sampling systems in containment. The RE
filters accumulate particulates and may need to be changed to ensure acceptable system
operation. Licensee records correlate RE filter changes with past RCS leakage increases. In
March 1999, RE filter clogging from boric acid deposits was identified and attributed to the
pressurizer relief valve modification discussed previously. In November 1999, after identifying
yellowish brown deposits in the filters, the licensee obtained a chemical analysis of the filter
particulates which identified the presence of ferric oxide in addition to boric acid crystals.
Around this time, the licensee began changing the filters every one-to-three weeks. By
November 1999, the frequency of filter changes had again increased.
DISCUSSION
RCS leakage, boron deposits, and corrosion products like ferric oxide in CACs and RE filters
may indicate degradation of the reactor coolant pressure boundary materials. These indicators
do not provide clear evidence of the degradation; however, they may provide an opportunity for
licensees to suspect that degradation is ongoing. The NRC understands that the indications at
Davis-Besse were sometimes complicated by other events (e.g., flange leaks). Nonetheless, in
combination with other indicators, they may provide insights into whether degradation of the
reactor coolant pressure boundary materials is occurring.
The information in this notice is, in part, based on preliminary information. The safety
significance and generic implications of the information justify NRC's urgency to issue this
information notice.
.'Mic~hael Tschiltz -*Info~rmration No1tice 2026515.w.pdi Page "I
Michae! Tschiltz Information Notice 2002-1 3.wpd
-
Pace 3 This information notice does not require any 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 project manager from the NRC's Office of Nuclear Reactor
Regulation.
IRA!
William D. Beckner, Program Director
Operating Reactor Improvements Program
Division of Regulatory Improvement Programs
Office of Nuclear Reactor Regulation
Technical contacts: Ian Jung, NRR John Jacobson, Region III
(301) 415-1837 (630)829-9736 E-mail: ixi@nrc..qov E-mail: iml3@nrc..ov
Attachment: List of Recently Issued NRC Information Notices
ML020930617 TEMPLATE #: NRR-052 OFFICE RSE Tech Editor BC:EMCB (A)SC:RORP:DRIP PD:RORP:DRIP
NAME ICJung PKleene* WHBateman TKoshy WDBeckner
DATE 04/ /2002 04/04/2002 04/04/2002 04/04/2002 04/04/2002
t*Mi~hah~l Ttchilt'Z - Information Notice 20"0"2-13.wpdl Page 5 Micha.l Thchiltz information Notice 2002-1 3.wpd Pace 5 Attachment 1 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
99-28, Supp 1 Recall of Star Brand Fire 03/22/2002 All holders of licenses for nuclearr
Protection Sprinkler Heads power, research, and test
reactors and fuel cycle facilities.
2002-12 Submerged Safety-Related 03/21/2002 All holders of operating licenses
Electrical Cables or construction permits for
nuclear power reactors
2002-11 Recent Experience with 03/12/2002 All holders of operating licenses
Degradation of Reactor for pressurized-water reactors
Pressure Vessel Head (PWRs), except those who have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor.
2002-10 Nonconservative Water Level 03/07/2002 All holders of operating licenses
Setpoints on Steam for nuclear power reactors, Generators except those who have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor.
2002-09 Potential for Top Nozzle 02/13/2002 All holders of operating licenses
Separation and Dropping of for nuclear power reactors, and
Certain Type of Westinghouse non-power reactors and holders
Fuel Assembly of licenses for permanently
shutdown facilities with fuel
onsite.
2002-08 Pump Shaft Damage Due to 01/30/2002 All holders of operating licenses
Excessive Hardness of Shaft for nuclear power reactors, Sleeve except those who have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor.
OL =Operating License
OP = Construction Permit
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list | - Information Notice 2002-01, Metal Clad Switchgear Failures and Consequent Losses of Offsite Power (8 January 2002, Topic: Emergency Lighting)
- Information Notice 2002-02, Recent Experience with Plugged Steam Generator Tubes (17 July 2002)
- Information Notice 2002-03, Highly Radioactive Particle Control Problems During Spent Fuel Pool Cleanout (10 January 2002, Topic: Significance Determination Process)
- Information Notice 2002-04, Wire Degradation at Breaker Cubicle Door Hinges (10 January 2002)
- Information Notice 2002-06, Design Vulnerability in BWR Reactor Vessel Level Instrumentation Backfill Modification (18 January 2002, Topic: Reactor Vessel Water Level)
- Information Notice 2002-07, Use of Sodium Hypochlorite for Cleaning Diesel Fuel Oil Supply Tanks (28 January 2002)
- Information Notice 2002-09, Potential for Top Nozzle Separation and Dropping of a Certain Type of Westinghouse Fuel Assembly (13 February 2002)
- Information Notice 2002-10, Manual Reactor Trip and Steam Generator Water Level Setpoint Uncertainties (28 June 2002, Topic: Safe Shutdown, Unanalyzed Condition)
- Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head (12 March 2002, Topic: Boric Acid, Pressure Boundary Leakage)
- Information Notice 2002-12, Submerged Safety-Related Electrical Cables (21 March 2002)
- Information Notice 2002-13, E-mail from H. Nieh, Oedo to A. Levin, Ocm, Et Al., Issuance of Information Notice 2002-13, Fwd: E-mail from D. Pickett T Davis-Besse Communication Plan (4 April 2002, Topic: Boric Acid)
- Information Notice 2002-14, Ensuring a Capability to Evacuate Individuals, Including Members of the Public, from the Owner-Controlled Area (8 April 2002)
- Information Notice 2002-15, Hydrogen Combustion Events in Foreign BWR Piping (12 April 2002)
- Information Notice 2002-17, Attachment: Recent Misadministrations Caused by Incorrect Calibrations of STRONTIUM-90 Eye Applicators (30 May 2002, Topic: Brachytherapy)
- Information Notice 2002-18, Effect of Adding Gas Into Water Storage Tanks on the Net Positive Suction Head for Pumps (6 June 2002, Topic: Brachytherapy)
- Information Notice 2002-19, Medical Misadministrations Caused by Failure to Properly Perform Tests on Dose Calibrators for Beta-and-Low-Energy Photon-Emitting Radionuclides (14 June 2002, Topic: Brachytherapy)
- Information Notice 2002-21, Axial Outside-Diameter Crackling Affecting Thermally Treated Alloy 600 Steam Generator Tubing (1 April 2003, Topic: Boric Acid)
- Information Notice 2002-22, Degraded Bearing Surfaces in Gm/Emd Emergency Diesel Generators (28 June 2002, Topic: Brachytherapy)
- Information Notice 2002-23, Unauthorized Administration of Byproduct Material for Medical Use (21 March 2006)
- Information Notice 2002-24, Potential Problems with Heat Collectors on Fire Protection Sprinklers (19 July 2002, Topic: Fire Protection Program, Brachytherapy)
- Information Notice 2002-25, Challenges to Licensees' Ability to Provide Prompt Public Notification and Information During An Emergency Preparedness Event (26 August 2002, Topic: Inadvertent Siren Activation)
- Information Notice 2002-25, Challenges to Licensees' Ability to Provide Prompt Public Notification and Information During an Emergency Preparedness Event (26 August 2002, Topic: Inadvertent Siren Activation)
- Information Notice 2002-26, Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH 56, NRC Information Notice 2002-26, Supplement 2: Additional Flow-Induced Vibration Failures After a Recent Power Uprate (9 January 2004, Topic: Safe Shutdown)
- Information Notice 2002-27, Recent Fires at Commercial Nuclear Power Plants in the United States (20 September 2002, Topic: Safe Shutdown, Temporary Modification)
- Information Notice 2002-28, Appointment of Radiation Safety Officers and Authorized Users Under 10 CFR Part 35 (27 September 2002, Topic: Brachytherapy)
- Information Notice 2002-29, (Errata): Recent Design Problems in Safety Functions of Pneumatic Systems (6 November 2002)
- Information Notice 2002-30, Control and Surveillance of Portable Gauges During Field Operations (30 October 2002, Topic: Brachytherapy, Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 2002-31, Potentially Defective UF6 Cylinder Valves (1-inch) (24 March 2003)
- Information Notice 2002-31, Potentially Defective Uf6 Cylinder Valves (1-inch) (24 March 2003)
- Information Notice 2002-32, Electromigration on Semiconductor Integrated Circuits (31 October 2002)
- Information Notice 2002-33, Notification of Permanent Injunction Against Neutron Products Incorporated of Dickerson, Maryland (22 November 2002, Topic: Uranium Hexafluoride)
- Information Notice 2002-34, Failure of Safety-Related Circuit Breaker External Auxiliary Switches at Columbia Generating Station (25 November 2002)
- Information Notice 2002-35, Changes to 10 CFR Parts 71 and 72 Quality Assurance Programs (20 December 2002)
- Information Notice 2002-36, Incomplete or Inaccurate Information Provided to the Licensee And/Or NRC by Any Contractor or Subcontractor Employees (27 December 2002)
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