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ML022560447
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Category
Letter
ASME section
ASME Section III +  and ASME Section II +
Accession number
ML022560447  +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.90 +, 10 CFR 2.790 +  and 10 CFR 2.790#b4 +
Correspondence
PM 14 +, PM 10 +  and PM 26 +
Docket
05000529  +, 00529  +  and 00470  +
From
Arizona Public Service +  and Mauldin D +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +
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>.
ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +, ML022560447 +  and ML022560447 +
Issue date
September 6, 2002  +
Manufacturer
Westinghouse +  and Parker Hannifin +
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20:54:36, 16 January 2025  +
NUREG
NUREG-0857, Supplement No. 8 Safety Evaluate on Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 +  and NUREG-0852, Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values +
PM
PM 14 +, PM 10 +  and PM 26 +
Page count
29  +
Project reference
TAC:MB3695 +
Project stage
Response to RAI  +
Regulatory Guide
Regulatory Guide 1.92 +
Site
Palo Verde +
Start date
September 6, 2002  +
State
Texas +, Arizona +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Shutdown Cooling +, Main Steam Safety Valve +, Main Steam Line +  and Main Steam +
Title
Response to Request for Additional Information Regarding Steam Generator Replacement & Power Uprate License Amendment Request  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Stroke time +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Anchor Darling +, Operating Basis Earthquake +, Flow Induced Vibration +, Power Uprate +, Affidavit +, Thermal fatigue +, Leak-Before-Break +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML0225/ML022560447.pdf  +
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