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ML20197J910
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Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
ASME section
ASME Section XI +
Accession number
ML20197J910  +
Atomic Element
Boron +
CFR
10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +  and 10 CFR 50 Appendix B Criterion V +
Cornerstone
Emergency Preparedness +
Correspondence
L 15 +
Docket
05000282  +, 05000306  +  and 00282  +
Emergency Facility
Technical Support Center +  and Emergency Operations Facility +
Equipment trip
Reactor Trip +
From
Burgess B +  and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) +
Generic letter
NRC Generic Letter 98-01 +, NRC Generic Letter 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits +  and NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +, ML20197J910 +  and ML20197J910 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Inspection procedure
IP 73753 +, IP 83750 +  and IP 81700 +
Isotope
Cesium-137 +
Issue date
November 24, 1998  +
L
L 15 +
Manufacturer
Westinghouse +
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17:18:26, 10 December 2024  +
NUREG
NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +
Page count
41  +
Procedure
Emergency Operating Procedure +
SSC
1E-3 +, 1LT-426 +  and 1LT-433 +
Site
Prairie Island +
Start date
November 24, 1998  +
State
Minnesota +  and Wisconsin +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Residual Heat Removal +, Shield Building +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.13.A +, TS-4.6.A +, TS-6.5 +, TS-3.6.G +, TS-4.18.2 +, TS-4.18.1 +  and TS-6.5.C +
Title
Advises of Planned Insp Effort for Next 6 Months at Prairie Island Nuclear Plant.Encl Info Provided to Minimize Resource Impact on Staff & Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arriva  +
To
Wadley M +  and Northern States Power Company +
Topic
Hot Short +, Safe Shutdown +, Shutdown Margin +, High Radiation Area +, Fire Barrier +, Stroke time +, Post Accident Monitoring +, Nondestructive Examination +, Temporary Modification +, Condition Adverse to Quality +, Missed surveillance +, Notice of Violation +, Foreign Material Exclusion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Control of Heavy Loads +, Power change +, Operability Assessment +, Negative Flux Rate Trip +, Control Room Habitability +  and Pressure Temperature Limits Report +
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http://pbadupws.nrc.gov/docs/ML2019/ML20197J910.pdf  +
 
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