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ML16342B243
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Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
ANSI code
ANSI N18.1-1971 +
Accession number
ML16342B243  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Boron +, Uranium +, Hydrogen +, Lead +, Silicon +, Silver +  and Tin +
CFR
10 CFR 50.72 +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 51 +, 10 CFR 50.49 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 5059 +, 10 CFR 5089 +, 10 CFR 2.714 +, 10 CFR 2.714#a1i +, 10 CFR 5092 +, 10 CFR 51.12#b +, 10 CFR 51.22#b +  and 10 CFR 50.92#c +
CR
LO-LAR-86-00008 +
Correspondence
L 97-415 +, L 85-43 +, DCL-86-038, Responds to NRC Re Violations Noted in Insp Rept 50-275/85-44.Corrective Actions:Snm Physical Inventory Performed & Administrative Procedure APD-751, Control & Accountability of SNM, Revised +, PLA-2720 +, PLA-2719 +  and DCL-88-036 +
DCL
DCL-86-038, Responds to NRC Re Violations Noted in Insp Rept 50-275/85-44.Corrective Actions:Snm Physical Inventory Performed & Administrative Procedure APD-751, Control & Accountability of SNM, Revised +  and DCL-88-036 +
Docket
05000275  +, 05000323  +, 00275  +, 00348  +, 00364  +, 00528  +, 00325  +, 00324  +, 00261  +, 00373  +, 00374  +, 00295  +, 00304  +, 00341  +, 00334  +, 00302  +, 00289  +, 00458  +, 00331  +, 00382  +, 00309  +, 00298  +, 00220  +, 00423  +, 00285  +, 00323  +, 00344  +, 00272  +, 00312  +, 00395  +...
Equipment trip
Reactor Trip +  and Turbine Trip +
FR
51 FR 7744 +, 51 FR 7751 +, 51 FR 11230 +, 51 FR 34169 +, 51 FR 28993 +, 51 FR 25768 +, 51 FR 28996 +, 51 FR 30564 +, 50 FR 25484 +, 51 FR 30567 +, 51 FR 27284 +, 51 FR 31740 +, 51 FR 29015 +, 51 FR 25771 +, 51 FR 29009 +, 51 FR 32383 +, 51 FR 27288 +, 50 FR 34994 +, 51 FR 27280 +, 51 FR 3711 +, 51 FR 30569 +, 51 FR 30589 +, 51 FR 30577 +, 49 FR 38410 +, 51 FR 24258 +, 51 FR 20307 +, 51 FR 36081 +, 51 FR 31179 +, 61 FR 30587 +, 51 FR 30581 +...
From
Office of Nuclear Reactor Regulation +
General design criterion
GDC 17, Electric power systems +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 82-10, Post-TMI Requirements +, NRC Generic Letter 82-18, Reactor Operator and Senior Reactor Operator Requalification Examinations +, NRC Generic Letter 82-16, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-13, Clarification of Survell. Req's for HEPA Filters and Charcoal Absorber Units In STD. Tech Specs on ESF Cleanup Systems +, NRC Generic Letter 85-10, Technical Specification for Generic Letter 83-28, Items 4.3 and 4.4 +  and NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +
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ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +, ML16342B243 +  and ML16342B243 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
November 4, 1986  +
L
L 85-43 +  and L 97-415 +
Letter
ML20134F973 +, ML20210S892 +  and 05000275/LER-1986-009-01, :on 860820,during Surveillance Test Procedure M-16N,inadvertent Actuation of Auxiliary Feedwater Pump 1-3 Occurred.Caused by Personnel Error.Individual Counseled. Procedure Will Be Revised +
Manufacturer
Westinghouse +  and General Electric +
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>.
22:10:27, 9 January 2025  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +
Page count
64  +
Procedure
RT +
Project stage
Other  +
Regulatory Guide
Regulatory Guide 1.97 +
SR
SR-4.5.1 +, SR-4.4.10.1.1 +, SR-4.4.3.2.2 +, SR-4.10.1.2 +, SR-4.3.C +  and SR-4.1.2.9.4 +
SSC
07-97-415 +, 07-60-388 +, 07-60-325 +, 07-60-272 +, 07-58-413 +, 07-60-458 +, 07-60-317 +, 07-60-413 +  and 5O-2y5 +
Scram
Automatic Scram +
Site
Diablo Canyon +
Site license
Oconee +, Palo Verde +, Grand Gulf +, Sequoyah +, Brunswick +, North Anna +, River Bend +, Diablo Canyon +, Farley +, McGuire +, LaSalle +, NPF-52 +, NPF-35 +, DPR-85 +, DPR-17 +, DPR-78 +  and Crane +
Start date
November 4, 1986  +
State
Tennessee +, Pennsylvania +, Connecticut +, Kansas +, Arizona +, Illinois +, Maryland +, North Carolina +, Washington +, California +, Massachusetts +, Alabama +, Virginia +, New Jersey +, South Carolina +, New York +, Michigan +, Florida +, Louisiana +, Oklahoma +, Missouri +, Mississippi +, Nebraska +, Arkansas +, New Hampshire +, Oregon +, Iowa +  and Maine +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Main Turbine +, Automatic Depressurization System +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +  and Containment Spray +
TS
TS-3.5.1 +, TS-3.3.1.1 +, TS-3.5.3 +, TS-3.14 +, TS-4.0.5 +, TS-3.10.1 +, TS-3.4.9.1 +, TS-3.1.2.3 +, TS-4.9 +, TS-6.4.1 +, TS-5.3.1 +, TS-3.3.C +, TS-6.13 +, TS-6.13.1 +, TS-4.7 +, TS-6.3.1 +, TS-6.23 +, TS-3.11 +, TS-3.1.2.9 +, TS-6.10.2 +, TS-4.5.2.i +, TS-4.7.9 +, TS-4.4.10.1 +, TS-3.15 +, TS-3.10.3.b +, TS-6.5.3.2 +, TS-8.2.3 +  and TS-4.9.8.1 +
Title
Forwards Biweekly Fr Notice Re Applications & Amends to OLs Involving NSHCs for Period Through 861022.Hearing Requests & Comments Must Be Received by 861121  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Stroke time +, Hydrostatic +, Locked High Radiation Area +, Shift Technical Advisor +, Earthquake +, Fire Protection Program +  and Operational leakage +
Trip
Turbine Control Valve Fast Closure +
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http://pbadupws.nrc.gov/docs/ML1634/ML16342B243.pdf  +
Ultimate Heat Sink
Cooling Tower +
WCAP
WCAP-10218-PA +  and WCAP-10216-PA +
Westinghouse report
WCAP-10218-PA +  and WCAP-10216-PA +
 
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