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ML20079A020
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Category
CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS
ASME section
ASME Section XI +
Accession number
ML20079A020  +
Atomic Element
Boron +, Nitrogen +, Oxygen +, Hydrogen +  and Lead +
CFR
10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 4 +, 10 CFR 50.12 +, 10 CFR 56 +, 10 CFR 50.55a +, 10 CFR 50.55a#a3 +, 10 CFR 50 Appendix J#0 +, 10 CFR 50 Appendix J#10 +, 10 CFR 50.12#a2 +, 10 CFR 50.12#a2ii +  and 10 CFR 50.12#a1 +
Docket
05000354  +  and 00354  +
Drawing
SK-HV-4953 +
Equipment trip
Turbine Trip +  and Reactor Trip +
FR
50 FR 50764 +
From
INC. +, EG&G IDAHO +  and Hartley R +
Generic letter
NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +
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>.
ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +, ML20079A020 +  and ML20079A020 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +
In package
ML20079A025 +
Issue date
August 31, 1990  +
Letter
ML20235E146 +
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>.
05:04:23, 15 December 2024  +
NUREG
NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +
Page count
79  +
Procedure
CP-401 +
Project reference
TAC:65730 +
Site
Hope Creek +
Start date
August 31, 1990  +
State
Washington +  and Idaho +
System
Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +
TS
TS-3.1.3.2 +, TS-4.8.1.1 +, TS-4.4.2.2 +, TS-4.6.1.2 +, TS-4.6.3.4 +, TS-4.1.3.2 +, TS-4.5.1.d +  and TS-4.1.5.d +
Title
Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Hope Creek Generating Station  +
To
NRC +
Topic
High Radiation Area +, Stroke time +, Probabilistic Risk Assessment +, Squib +, Excess Flow Check Valve +, Exemption Request +  and Power Operated Valves +
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http://pbadupws.nrc.gov/docs/ML2007/ML20079A020.pdf  +
Ultimate Heat Sink
Cooling Tower +
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