ACRS CRS MEE MEETING TING WITH WITH THE THE U.S. .S. NUCLE - PowerPoint PPT Presentation

ACRS CRS MEE MEETING TING WITH WITH THE THE U.S. .S. NUCLE NUCLEAR AR REGU REGULA LATOR ORY Y COMM COMMISSION ISSION March 5, 2015

Ov Over erview view John W. Stetkar 2

Accomplishments • Since our last meeting with the Commission on October 2, 2014, we issued 8 Reports • Topics: – Watts Bar Unit 2 Operating License – Draft Branch Technical Position 8-9 on Open Phase Conditions in Electric Power Systems – Assessment of the Quality of Selected NRC Research Projects – FY 2014 3 3

• Topics (cont.): – Report on the Safety Aspects of the Nuclear Innovation North America, LLC Combined License Application for South Texas Project Nuclear Station, Units 3 and 4 – Report of the Safety Aspects of the License Renewal Application of the Callaway Plant, Unit 1 4 4

• Topics (cont.): – Commission Paper, “Integration of Mitigating Strategies for Beyond- Design-Basis External Events and the Reevaluation of Flooding Hazards” – Standard Review Plan Chapter 19 and Section 17.4 – Draft Generic Letter 20XX-XX, “Treatment of Natural Phenomena Hazards in Fuel Cycle Facilities” 5 5

Ongoing / Future Reviews • New Plants – Design Certification Application for US EPR – Reference COLA for US EPR (Calvert Cliffs) – Subsequent COLAs for AP1000 (Levy) and ESBWR (North Anna) 6 6

Ongoing / Future Reviews • PSEG Early Site Permit • Small Modular Reactors (NuScale) • SHINE Medical Radioisotope Production Facility • License Renewal – Sequoyah – Byron/Braidwood – Seabrook – Davis-Besse – Indian Point 7 7

Ongoing / Future Reviews • Technical Issues for Subsequent License Renewal – Concrete Structures – Reactor Vessel and Internals – Electrical Cables – Others as Identified • Risk-Informed Resolution of GSI-191, “ Ex Experimenta perimental l Stu Studies of dies of Los Loss-of of- Coolant Coolant-Accident Accident-Gener Generated De ted Debris bris Accumula Accumulation and tion and Head Loss wit Head Loss with h Emp Emphas hasis is on the E on the Effects ects of of Calcium Calcium Silicate Insulation” 8 8

Ongoing / Future Reviews • Fukushima Proposed Rulemaking – Mitigation Strategies for Beyond- Design-Basis External Events – Interim Staff Guidance in Support of Order EA-13-109 (Reliable Hardened Vents) Phase 2 – Containment Protection and Release Reduction for BWRs with Mark I and Mark II Containments 9 9

Ongoing / Future Reviews • Grand Gulf MELLLA+ • Nine Mile Point Unit 2 MELLLA+ • Topical Report NEDE- 33766P , “GEH Simplified Stability Solution (GS3)” • Westinghouse Realistic Full Spectrum LOCA Methodology 10 10

Ongoing / Future Reviews • Risk Prioritization Initiative / Cumulative Effects of Regulation • Risk Management Regulatory Framework • Updated Regulatory Analysis Guidance • Level 3 PRA • Human Reliability Analysis Methods 11 11

Review view of of TV TVA A Oper Operating ting License A License Applica pplication tion for or Watts tts Bar Nuc Bar Nuclear lear Plan Plant, t, Unit Unit 2 Harold B. Ray 12

Background • Watt tts s Bar Bar Unit Unit 2 (WBN 2 (WBN 2) i 2) is s th the e se seco cond nd un unit it of of a a du dual al-un unit it plan plant • Par art t 50 50 co cons nstr truc uctio tion n pe permit mit for or bo both th un units its issu issued ed in in 1973 1973 • Watt tts s Bar Bar Unit Unit 1 (WBN 1 (WBN 1) be 1) bega gan n op oper eration tion in in 1996 1996 • Co Cons nstr truc uctio tion n of of W WBN BN 2 w 2 was as su susp spen ende ded d 1985 1985 – 2006 2006 • SRM SRM in 200 in 2007 7 af affi firmed med tha that t th the e li lice cens nsing ing ba basis sis for or WBN WBN 2 w 2 wou ould ld be be th the e sa same me as as WBN WBN 1, 1, co cons nsiste istent nt with pr with prior ior du dual al-un unit it plan plants ts 13

Background (cont.) • TV TVA sub A submitted the op mitted the oper erating license ting license applica pplication f tion for WB or WBN 2 in N 2 in 2009 2009 • ACR CRS S has has held held 10 10 sub subcommittee committee meetings meetings betw between een Mar March 2009 h 2009 and and Januar anuary y 2015 2015 • An inte An interim lette rim letter w r was as issued issued in in No November ember 2013 2013 • The he interim interim letter letter listed spec listed specifi ific c issues issues f for fur or further ther ACR CRS S review view 14

Final letter in Final letter in Febr bruar uary y 201 2015 5 reflected eflected luding : our comp our completed leted review view inc including • Gen Generic eric Letter Letter (GL) (GL) 200 2004- 02, “Potential Im Impact pact of of De Debris bris Bloc Blocka kage ge on on Emer Emergenc gency y Recir ecircula culation tion during during Des Design ign Bas Basis is Acc Accidents idents at t Pr Pres essu suriz rized ed-Water ter Reactors” • GSI GSI-191 191 issues issues, , inc including luding in in-vess essel el ef effects ects, r , res esolv olved ed bas based ed on lo on low w la latent tent de debris bris le levels els 15

Final l Final letter in etter in Febr bruar uary y 2015 2015 reflected eflected our com our completed r pleted review view inc including luding: : (co (cont.) nt.) • Compliance Compliance with Gener with General al Design Design Criter Cri terion ion 5 5 concer concerning shar ning shared ed systems systems • Cyber Cyber secu security rity desig design n and and confir confirma mator tory y testing testing 16

Febr bruar uary y 2015 2015 ACR CRS S letter r letter reflected eflected further fur ther review view of of spe specific issues cific issues (cont (cont.) .): • Calcula Calculation tion of of cor core fuel e fuel temperatur temper ture • Site Site licensing licensing basis basis hy hydr drolog ology • Fir Fire e pr protection r otection rela elated to ted to oper operator tor manual manual actions actions • Oper Operational r tional readiness eadiness pr prepar eparations tions 17

Our conc Our conclusion lusion: Ther here e is is reaso easona nable ble assu assurance ance • tha that t WBN WBN 2 2 can oper can operate te as as the the seco second nd unit unit of of th the e dual dual unit unit Watts tts Bar Bar Nuc Nuclear lear Plant Plant wi withou thout t undu undue e risk risk to to the health the health and saf and safety ety of of the the pub publi lic c The he oper operating ting li licens cense e for WBN or WBN 2 2 • shou should ld be a be appr pproved ed foll ollowi wing ng completion completion of of r remaini emaining ng staf staff inspections and inspections and closur losure e of of remaini emaining ng open open items items 18

• The he revise vised d Watt tts s Ba Bar r site site licen licensing sing ba basis sis reflect eflects s a a de dete terministica ministicall lly y es esta tablishe blished d Pr Prob obable ble Max Maximum imum Flood lood, , co cons nsiste istent nt with cu with curren ent t pr prac actice tice • We e disc discus usse sed d with NR with NRC C st staf aff t the he de develo elopm pmen ent t of of a a Pr Prob obabilistic bilistic Flood looding ing Hazar Hazard d Ana Analys ysis is metho met hodo dolog logy y for or f fut utur ure us e use • Sta Staff has has a 5 a 5-yea ear r res esea earch h plan plan; ; we su e supp ppor ort t th this is ef effor ort an t and d welco elcome me en enga gage gemen ment t with th with the e st staf aff 19

Assessment of the Quality of NRC Research Projects Michael L. Corradini

Bac Backgro kground und • Throughout its history, an essential activity of the ACRS has been reviewing the research sponsored by the NRC. Currently, such review includes: – Review of research conducted in support of specific regulatory activities – Episodic review of particularly important ongoing research – Biennial review of the overall reactor safety research program – Research Quality Reviews 21

Motivation Motiv ation for Quality for Quality Rev Review iew • Independent evaluation of the quality and utility of research programs • GPRA requirement • ACRS agreed to undertake this task in partial fulfillment of the Commission direction for ACRS to assume role previously performed by NSRRC 22

Quality Review P Quality Review Process rocess • Review criteria originally developed by ACRS & RES • ACRS typically selects two or three Projects from a list proposed by RES • A panel of three ACRS members assigned to each project to do an in- depth review 23