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Advance plant severe accident/thermal hydraulic issues for ACRS CONF-9405214-1 DE94 017700

Advance plant severe accident/thermal hydraulic issues for ACRS CONF-9405214-1 DE94 017700
紙マイクロ規格・テクニカルリポート類
Kress, T. S1994<LS-DE94/017700>
国立国会図書館全国の図書館

Summary of 436th ACRS meeting on 961107-09 re proposed rule & reg guide concerning SG integrity.Completed repts,ltrs, memos & draft repts listed.Highlights of key issues, considered by Committee,submitted.

Summary of 436th ACRS meeting on 961107-09 re proposed rule & reg guide concerning SG integrity.Completed repts,ltrs, memos & draft repts listed.Highlights of key issues, considered by Committee,submitted.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/12/19.
全国の図書館

Summary of 433rd ACRS meeting on 960808-10 re design changes proposed by ASEA Brown Boveri - C-E re certification of Sys 80+ design,SECY 96-128,proposed rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & rev 3 to Reg Guide 1.105.

Summary of 433rd ACRS meeting on 960808-10 re design changes proposed by ASEA Brown Boveri - C-E re certification of Sys 80+ design,SECY 96-128,proposed rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & rev 3 to Reg Guide 1.105.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/08/29.
全国の図書館

Summary of 434th meeting of ACRS on 960912-13 re capability of SCAP/RELAP5 code to predict SG temps during severe accidents.

Summary of 434th meeting of ACRS on 960912-13 re capability of SCAP/RELAP5 code to predict SG temps during severe accidents.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/10/04.
全国の図書館

Concludes that acceptable bases & requirements have been established in application to assure that US ABWR std design can be used to engineer & const plants w/assurance that plants can be operated w/o undue risk to safety of public.

Concludes that acceptable bases & requirements have been established in application to assure that US ABWR std design can be used to engineer & const plants w/assurance that plants can be operated w/o undue risk to safety of public.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/08/15.
全国の図書館

Summary of 437th meeting of ACRS on 961205-07 re ACRS review of GLs,bulletins & info requests issued on expedited basis.

Summary of 437th meeting of ACRS on 961205-07 re ACRS review of GLs,bulletins & info requests issued on expedited basis.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1997/01/22.
全国の図書館

Summary of ACRS 433rd meeting on 960808-10 re SECY 96-128, "Policy & Key Technical Issues Re Westinghouse AP600 Standardized Passive Reactor Design."

Summary of ACRS 433rd meeting on 960808-10 re SECY 96-128, "Policy & Key Technical Issues Re Westinghouse AP600 Standardized Passive Reactor Design."
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/08/15.
全国の図書館

Summary of 432nd ACRS meeting on 960612-14 re severe accident research,draft reg guide DG-1047,IPE insights rept, loss of offsite power at Catawba Unit 1,issues associated w/ SGs & shutdown of Browns Ferry Nuclear Plant Unit 3.

Summary of 432nd ACRS meeting on 960612-14 re severe accident research,draft reg guide DG-1047,IPE insights rept, loss of offsite power at Catawba Unit 1,issues associated w/ SGs & shutdown of Browns Ferry Nuclear Plant Unit 3.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/07/25.
全国の図書館

Summary of 429th meeting of ACRS on 960307-09 re NRC program on adequacy assessment of RELAP5/MOD3 code for simulation of AP600 passive plant behavior.

Summary of 429th meeting of ACRS on 960307-09 re NRC program on adequacy assessment of RELAP5/MOD3 code for simulation of AP600 passive plant behavior.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/03/19.
全国の図書館

Summary of 435th meeting of ACRS on 961009-12 re capability of NRC SCDAP/RELAP5 code to predict temps & flows in SGs under severe-accident conditions.

Summary of 435th meeting of ACRS on 961009-12 re capability of NRC SCDAP/RELAP5 code to predict temps & flows in SGs under severe-accident conditions.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/11/11.
全国の図書館

Summary of 431st meeting of ACRS w/Nuclear Energy Inst re proposed rule on shutdown operations & PRA studies performed for Surry & Grand Gulf Nuclear Power Plants.

Summary of 431st meeting of ACRS w/Nuclear Energy Inst re proposed rule on shutdown operations & PRA studies performed for Surry & Grand Gulf Nuclear Power Plants.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/06/04.
全国の図書館

Forwards repts ACRS provided to NRC during past yr re research program or suggestions needed research.

Forwards repts ACRS provided to NRC during past yr re research program or suggestions needed research.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/02/27.
全国の図書館

Summary of ACRS 433rd meeting on 960808-10 re design changes proposed by GE on certification of US advanced BWR design.

Summary of ACRS 433rd meeting on 960808-10 re design changes proposed by GE on certification of US advanced BWR design.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/08/15.
全国の図書館

Endorses postition recommended by staff in addressing listed policy issues re SECY-96-128, "Policy & Key Technical Issues Pertaining to Westinghouse AP600 Passive Reactor Design."

Endorses postition recommended by staff in addressing listed policy issues re SECY-96-128, "Policy & Key Technical Issues Pertaining to Westinghouse AP600 Passive Reactor Design."
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/08/15.
全国の図書館

Concludes that acceptable bases & requirements have been established in application to assure that Sys 80+ std design can be used to engineer & const plants w/assurance that plants can be operated w/o undue risk to safety of public.

Concludes that acceptable bases & requirements have been established in application to assure that Sys 80+ std design can be used to engineer & const plants w/assurance that plants can be operated w/o undue risk to safety of public.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/08/14.
全国の図書館

Summary of 431st ACRS meeting on 960523-25 re potential IPE/ IPEEE results to compare risk of current population of plants w/safety goals,resolution of multiple sys responses program issues & proposed rule on shutdown operations.

Summary of 431st ACRS meeting on 960523-25 re potential IPE/ IPEEE results to compare risk of current population of plants w/safety goals,resolution of multiple sys responses program issues & proposed rule on shutdown operations.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1996/06/26.
全国の図書館

Summary of 951005-07 ACRS 425th meeting re fatigue action plan,proposed final rev 1 to Reg Guide 1.152,shutdown cooling bypass event st Hope Creek Nuclear Plant,foreign reactor events & suppl 5 to GL 88-20.

Summary of 951005-07 ACRS 425th meeting re fatigue action plan,proposed final rev 1 to Reg Guide 1.152,shutdown cooling bypass event st Hope Creek Nuclear Plant,foreign reactor events & suppl 5 to GL 88-20.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1995/11/01.
全国の図書館

Summary of 421st meeting of ACRS on 950504-06 re proposed final GL, "Voltage-Based Repair Criteria for Westinghouse SG Tubes."

Summary of 421st meeting of ACRS on 950504-06 re proposed final GL, "Voltage-Based Repair Criteria for Westinghouse SG Tubes."
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1995/05/15.
全国の図書館

Summary of 421st meeting of ACRS on 950504-06 re regulatory reform initiatives & natl performance review Phase II.

Summary of 421st meeting of ACRS on 950504-06 re regulatory reform initiatives & natl performance review Phase II.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1995/05/10.
全国の図書館

Summary of 420th meeting of ACRS on 950406-07 re proposed final rule change to 10CFR50.36,tech specs.

Summary of 420th meeting of ACRS on 950406-07 re proposed final rule change to 10CFR50.36,tech specs.
紙図書
KRESS, T. S.NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)1995/04/13.
全国の図書館