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ML18152B374
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Category
CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE
Accession number
ML18152B374  +
Agency
Virginia Department of Health +
CFR
10 CFR 50.73 +, 10 CFR 50 +, 10 CFR 50.73#a2 +, 10 CFR 50.72#a1i +  and 10 CFR 50.72#b1iA +
Cornerstone
Initiating Events +
Docket
05000280  +  and 00280  +
Equipment trip
Reactor Trip +
From
Edison G +  and NRC (Affiliation Not Assigned) +
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>.
ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +, ML18152B374 +  and ML18152B374 +
Issue date
August 11, 1999  +
LER
05000280/LER-98-009 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
00:39:35, 6 January 2025  +
NRC form
NRC Form 366A +  and NRC Form 311M +
NUREG
NUREG/CR-2300 +, NUREG/CR-6004 +, NUREG/CR-6582, Forwards,For Review & Comments,Draft Rept, Assessment of Pressurized Water Reactor Primary System Leaks, NUREG/CR-6582,to Meet Planned Issuance Schedule.Comments Requested to Be Submitted by 980130 +  and NUREG/CR-4674, Forwards NUREG/CR-4674,Vols 9 & 10, 1988 Accident Sequence Precursor Rept. Rept Describes & Evaluates Significant Operational Events Reported by LERs for CY88. W/O Encl +
Page count
25  +
Procedure
RT +
Site
Surry +
Site license
Surry +
Start date
August 11, 1999  +
State
Tennessee +, Georgia +, Washington +, Virginia +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +  and Containment Spray +
TS
TS-3.1.C +
Title
Forwards Preliminary Accident Sequence Precursor Analysis of Operational Condition Which Was Discovered at Surry Power Station,Unit 1 on 980509 & Reported in LER for Review & Comment  +
To
Ohanlon J +  and Dominion +
Topic
Probabilistic Risk Assessment +, Loss of Offsite Power +, Through Wall Leak +, Unidentified leakage +  and Thermal fatigue +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML1815/ML18152B374.pdf  +
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