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ML20210A243
Show incoming properties
Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
Accession number
ML20210A243  +
Docket
05000245  +  and 00245  +
FR
50 FR 32791 +, 51 FR 15404 +, 51 FR 8598 +  and 51 FR 15405 +
From
Office of Nuclear Reactor Regulation +  and James Shea +
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ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +, ML20210A243 +  and ML20210A243 +
In package
ML20210A248 +
Issue date
January 29, 1987  +
Letter
05000000/LER-1986-001, Partially Deleted LER 86-001-00:on 860105,loss of Dynamic Reporting of Vital Door Activity Occurred.Cause & Corrective Action Completely Deleted +, B11922, Proposed Tech Specs Deleting Requirement for Isolation Condenser Operability for Continued Power Operation When No Offsite 345-kV Power Available +, B11584, Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Changing Tech Specs Re Reportable Events & Reporting Requirements in Response to Revs to 10CFR50.72 & 73 & Generic Ltr 83-43.Proposed Tech Spec Revs Encl +  and 05000245/LER-1986-005-01, :on 860205,reactor Scrammed on APRM hi-hi Flux. Caused by Malfunction of Mechanical Pressure Regulator Sys. Sys Adjusted to Reduced Steady State Oscillation to 2 Psi. Overhaul of Sys Planned +
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>.
22:20:22, 6 December 2024  +
Page count
4  +
Procedure
SAP +
Regulatory Guide
Regulatory Guide 1.56 +
Site
Millstone +
Site license
DPR-21 +
Start date
January 29, 1987  +
State
Washington +  and Connecticut +
System
Core Spray +, Control Rod +  and Low Pressure Coolant Injection +
TS
TS-4.6.E +  and TS-3.9.B +
Title
Forwards Amend 1 to License DPR-21 & Safety Evaluations. Amend Consolidates Specs 3.5.F.7 & 3.5.F.8 Re Conditions for Work on CRD Mechanisms & Fuel Movement & Placement During Refuel Condition to Eliminate Redundancy  +
To
Mroczka E +  and Northeast Nuclear Energy +
Topic
Reserve Station Service Transformer +
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http://pbadupws.nrc.gov/docs/ML2021/ML20210A243.pdf  +
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