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ML19346A119
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Category
NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT
Accession number
ML19346A119  +
Agency
Federal Emergency Management Agency +
Atomic Element
Lead +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +  and 10 CFR 50.47 +
Cornerstone
Emergency Preparedness +
Cross cutting aspect
H.1(i) +
Docket
00311  +  and 05000311  +
Emergency Facility
Emergency Operations Facility +
Equipment trip
Reactor Trip +
FR
45 FR 76602 +
From
Office of Nuclear Reactor Regulation +
General design criterion
GDC 3, Fire protection +
Generic letter
NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +
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>.
ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +, ML19346A119 +...
Hours
9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
In package
ML18086A623 +
Isotope
H-3 +
Issue date
May 31, 1981  +
Letter
ML18086A527 +, ML18085B069 +, ML18085A301 +, ML18085A206 +, IR 05000272/1981008 +, IR 05000272/1981004 +, IR 015000027/1981006 +, 05000272/LER-1979-057, Forwards Updated LER 79-057/01X-1 +, ML18081A539 +  and ML18082A630 +
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>.
11:58:34, 24 December 2024  +
NUREG
NUREG-07 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-517 +, NUREG-0517, Advises That Review of NUREG-0737 Item III-D.3.3 Re Input Radiation Monitoring Is Complete.Equipment & Procedures Described by Licensee Meet NRC Position in NUREGs 0578,0694 & 0737,per Suppl 5 to SER (NUREG-0517) +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
61  +
Power source
4kV +
Procedure
ST +
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.
ML19346A119 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
SSC
1HI-2 +
Site
Salem +
Site license
Salem +
Start date
May 31, 1981  +
State
Washington +, New Jersey +  and Delaware +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Remote shutdown +, Decay Heat Removal +, Safety Relief Valve +  and Control Rod +
Title
Safety Evaluation Report Related to the Operation of Salem Nuclear Generating Station,Unit No. 2.DOCKET No. 50-311. (Public Service Electric and Gas Company,Et Al.)  +
Topic
Hot Short +, Safe Shutdown +, Shutdown Margin +, Ultimate heat sink +, Fire Barrier +, Emergency Lighting +, Shift Technical Advisor +, Exemption Request +, Control of Heavy Loads +, Continuous fire watch +, Fire Protection Program +  and Fire Watch +
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http://pbadupws.nrc.gov/docs/ML1934/ML19346A119.pdf  +
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