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ML070190094
Show incoming properties 
Category
Letter, Technical Specification  and Amendment
ASME section
ASME Section III +
Accession number
ML070190094  +
Atomic Element
Boron +, Oxygen +, Hydrogen +  and Lead +
CFR
10 CFR 20 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.4 +, 10 CFR 50.49 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.54#o +, 10 CFR 50.36#c2ii +, 10 CFR 50.55a#h +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 2.390#bX +, 10 CFR 50.92#c +  and 10 CFR 50.71#e +
CR
LO-LAR-07-00001 +  and LO-LAR-06-00004 +
Correspondence
DCL-06-130, Response to NRC Request for Additional Information Regarding License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) +, DCL-06-061, License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) +, DCL-05-090, Response to NRC Request for Additional Information Regarding License Amendment Request 05-01 Re Revision to Technical Specification 5.5.9, Steam Generator Tube Inspection Report +, ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project +, DCL-03-174, License Amendment Request 03-16 Regarding Revised Wedge Region Exclusion Zones for Steam Generator Tube Alternate Repair Criteria +, DCL-07-002, Response to Request for Additional Information on License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement +  and DCL-05-018, License Amendment Request 05-01 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program, and 5.6.10, Steam Generator Tube Inspection Report. to Allow Use of the W* Alternate Repair Criteria +
DCL
DCL-06-130, Response to NRC Request for Additional Information Regarding License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) +, DCL-06-061, License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) +, DCL-05-090, Response to NRC Request for Additional Information Regarding License Amendment Request 05-01 Re Revision to Technical Specification 5.5.9, Steam Generator Tube Inspection Report +, DCL-03-174, License Amendment Request 03-16 Regarding Revised Wedge Region Exclusion Zones for Steam Generator Tube Alternate Repair Criteria +, DCL-07-002, Response to Request for Additional Information on License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement +  and DCL-05-018, License Amendment Request 05-01 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program, and 5.6.10, Steam Generator Tube Inspection Report. to Allow Use of the W* Alternate Repair Criteria +
Docket
05000272  +, 05000323  +, 00275  +  and 00323  +
Equipment trip
Reactor Trip +
FR
70 FR 24126 +  and 70 FR 10298 +
From
Pacific Gas & Electric +  and Becker J +
General design criterion
GDC 20 +, GDC 21 +, GDC 13 +, GDC 25 +, GDC 22 +  and GDC 29 +
Generic letter
NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +
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>.
ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +, ML070190094 +...
Hours
0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +
IEEE
IEEE 279-1971 +  and IEEE-450 +
Inspection Manual Chapter
NRC Inspection Manual 4437 +
Issue date
January 11, 2007  +
Manufacturer
Westinghouse +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
09:04:43, 15 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
Page count
101  +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML070190094 +
Project
TAC:MD3992 +
Project reference
TAC:MC0893 +  and TAC:MD3180 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.163 +, Regulatory Guide 1.52 +, Regulatory Guide 1.121 +  and Regulatory Guide 1.24 +
Regulatory Issue Summary
RIS 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specification, with Respect to Limiting Safety System Settings (LSSS) During Periodic Testing and Calibration of Instrument Channels +
SR
SR-3.0.3 +, SR-3.3.2.8 +, SR-3.0.2 +, SR-3.3.2.6 +, SR-3.3.2.5 +, SR-3.3.2 +, SR-3.3.2.1 +, SR-3.3.2.2 +, SR-3.3.2.3 +, SR-3.3.2.4 +, SR-3.4.17.2 +, SR-3.3.2.7 +  and SR-3.3.2.9 +
SSC
L1X10-2 +
Site
Salem +  and Diablo Canyon +
Site license
NPF-30 +  and Diablo Canyon +
Start date
January 11, 2007  +
State
Texas +, Pennsylvania +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +  and Main Steam +
TS
TS-3.4.13 +, TS-5.5.9 +, TS-3.3.3 +, TS-3.4 +, TS-3.3.2 +, TS-3.3.1 +, TS-5.5.14 +, TS-3.0.6 +, TS-5.5.9.c +, TS-5.5.9.b +, TS-5.6.10 +, TS-5.5.9.d +  and TS-5.6.10.b +
TSTF
TSTF-493 +  and TSTF-449 +
Title
License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Shutdown Margin +, High Radiation Area +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Post Accident Monitoring +, Hydrostatic +, Probabilistic Risk Assessment +, Nondestructive Examination +, Annual Radiological Environmental Operating Report +, Process Control Program +, Stress corrosion cracking +, Eddy Current Testing +, Affidavit +, Operational leakage +  and Pressure Temperature Limits Report +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML0701/ML070190094.pdf  +
WCAP
WCAP-14036-P-A +, WCAP-9272-P-A +, WCAP-13632-P-A +, WCAP-10054-P-A +, WCAP-12945-P-A +, WCAP-8385 +, WCAP-14333-P-A +, WCAP-15376-P-A +, WCAP-14117 +, WCAP-14797-P +  and WCAP-15573 +
Westinghouse report
WCAP-14036-P-A +, WCAP-9272-P-A +, WCAP-13632-P-A +, WCAP-10054-P-A +, WCAP-12945-P-A +, WCAP-8385 +, WCAP-14333-P-A +, WCAP-15376-P-A +, WCAP-14117 +, WCAP-14797-P +  and WCAP-15573 +
 
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