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{{#Wiki_filter:7/2015 Timothy J. Griesbach Senior Associate Education M.S. Metallurgy and Materials Science, Case Western Reserve University (1974) B.S. Metallurgy and Materials Science, Case Western Reserve University (1972)  Professional Associat ions American Nuclear Society, 1982 to pre sent American Society of Mechanical Engineers, 1982 to pr esent   Professional Experience 2006 - Present Sr. Associate, Structural Integrity Associates, Inc. Mr. G riesbach is assi sting utilities on reactor vessel integrity issues, materials degradation management programs, PWR reactor vessel internals and plan t operating issues. 1993 - 2005 Director of Technical Se rvices, ATI Consulting. Mr. Griesbach is internationally known for his expertise in the a reas of reactor vessel embrittlement and vessel integrity management. Activities at ATI included component li fe assessment, li fe attainment and aging management strategies, ASME Code and regulatory issues concerning reactor vessel integrity, application of advanced fracture mechanics methods, utility cost control, a nd technical/management decision-making for long-term compone nt life. 1982 - 1993  Manager, Component Reliability Program, Electric Powe r Research Institute (1985 - 1993). Directed major research initiative to develop remedial measures for managing reactor vessel embrittlement. Man aged program to develop the on-line fatigue usage monitoring system for critical reactor system components.
{{#Wiki_filter:7/2 0 1 5 Tim othy J. Griesbach Senior A ss oci at e E d u c at ion M.S. Meta ll ur g y a nd Mate ria ls S c ienc e , Case W e ster n Rese rve Unive rsity (1974) B.S. Meta ll ur g y a nd Mate ria ls S c ienc e , Case W e ster n Rese rve Unive rsity (1972)  P r of e ssi on al Associat ion s Ame ric a n Nuc lea r Soc iety , 1982 to pre se nt Ame ric a n S oc iety of Me c ha nica l Eng inee rs, 1982 to pr e se nt   P r of e ssi on al E xp e r ience 2006 - P re se nt Sr. Assoc iat e , S truc tura l I nteg rity Assoc iate s, I nc. Mr. G rie sbac h is assi sti ng uti li ti e s on re a c tor ve ssel int e g rity iss ue s, mate ri a ls deg ra da ti on mana g e ment pr og ra ms, P W R r e a c tor ve ssel int e rna ls and plan t oper a ti ng iss ue s. 1993 - 2005 Direc tor of T e c hnical Se rv ice s, ATI C onsul ti ng. Mr. Gr iesba c h is int e rna ti ona ll y known f or his ex pe rtise in the a re a s of r e a c tor ve ssel e mbrit tl e men t and ve ssel int e g rity mana g e ment. Ac ti vit ies a t ATI include d c omponent li fe a ssessment, li fe a tt a inm e nt and a g ing mana g e ment st ra teg ies, ASM E Code a nd re g ulator y iss ue s con c e rning r e a c tor ve ssel int e g rity , a ppli c a ti on of a dva nc e d fr a c ture mec ha nics me thod s, ut il it y c ost control, a nd tec hnica l/mana g e ment de c isi on-making f or long-ter m compone nt l ife. 1982 - 1993  M anage r, C ompone nt Re li abil it y Program, Elec tric Powe r Re se a rc h I nsti tut e (1985 - 1993). Dire c ted ma jor r e se a rc h ini ti a ti ve to deve lop re media l m e a sure s for mana g ing r e a c tor ve ssel e mbrit tl e ment. Man a g e d pro g ra m t o de ve lop t he on-li ne f a ti g ue usag e moni toring sy stem for c ritica l re a c tor sy stem c omponents.
Project Manager, Nuclear Safety Analysis C enter (1982 to 1985). D eveloped methodolog ies to resolve generic safety issues includi ng pressurized thermal shock, BWR pipe cracking, steam generator tube cracking, and containment integrity. 1977 - 1982  Principal Engi neer, Nuclear Plant Engi neering, Combustion Engineering, Inc. Evaluated Response to NSSS components t o severe thermal, pressure and dynamic loads. 1974 - 1977 Materials Enginee r, Materials Enginee ring and Research Laboratory, Pratt and Whitney Aircraft. Developed dif fusion bonding process for fabrication of jet turbine blades.
Projec t Manage r, N uc lear Safety Analysis C e nter (1982 to 1985). D e ve loped methodolog ies to r e solve g e ne ric saf e ty iss ue s includi ng pre ssuriz e d ther mal shock , B W R pipe c ra c king , stea m g e ne ra tor tube c ra c king , a nd c ontainment int e g rity. 1977 - 1982  Principal Engi ne e r, N uc lear Plant Engi ne e ring, C ombus ti on Eng inee ring , I nc. Eva luate d Response to N S S S c omponents t o sev e re ther mal, pr e ssure a nd dy na mi c loads. 1974 - 1977 M aterial s Enginee r, Mate rial s Enginee ring a nd Re se arch L aborat ory, P ra tt a nd W hit ne y Airc ra ft. D e ve loped dif fusion bonding proc e ss for f a br ica ti on of jet turbine blade s.
T. J. Griesbach Page 2  7/2015   Related Experience Chairman, ASME Section XI Working Group on Ope rating Plant Criteria, 1984 to pr esent. Loaned employee to Commonwealth Edison, P WR Plant Engineering group, 1988. Participant, US/USSR Cooperative Program on Vessel Thermal Annealing, 1990 to 1993.
T. J. G ri es bach P age 2  7/2 0 1 5   Re late d E xp e r ience C ha irman , ASM E Sec ti on XI W or king Gr oup on Ope ra ti ng P lant C riter ia, 1984 to pr e se nt. L oa ne d e mpl oy e e to C omm onwe a lt h Edison, P W R P lant Eng inee ring g roup, 1988. P a rticipa nt, US/US S R C oope ra ti ve P rog ra m on Ve ssel The rma l Anne a li ng , 1990 to 1993.
Consultant to I AEA on Vessel Embritt lement and Ma terials Degradation, 1990 to 1996.
C onsul tant to I AEA on Ve ssel Embritt leme nt and Ma ter ials De g ra da ti on, 1990 to 1996.
Key Contributor to EPRI MRP Reactor Internals Issues Task Group, 2000  2015. Summary Mr. Griesbach has over 35 years of experience in materials behavior and structural integrity of major nuclear components. He specializes in technical consult ing utilizing state-of-the-art technologies for mitigating and resolving material degradation concerns in nuc lear reactor vessels, internals, piping, and other major components. Ke y accomplishments include:  In charge of numerous EPRI projects to develop tools for managing aging effects such as fatigue and reactor vessel embrittlement in nucle ar pressure vessels. Authored many reports and technical papers on maintaining structural integrity of nuclear plant components, m aterials toughness and embrittlement prediction m odels, databases for monitoring vessel mate rial properties, and strategic planning for license renewal. Interfaced with ut ilities, NEI, and NRC to resolve critical industry issues such as Pressurized Thermal Shock in PWRs and Integrated Surve illance Programs for BWRs Project team leader for successful competitive bids on m ajor indust ry projects for reactor vessel ther mal annealing, PWR internals aging management for license renewal, BWRVIP Integrated Surve illance Program, and pr obabilistic methods for developing operating P-T limit curves. Conducted workshops and util ity training classes for managing reactor vessel integrity, nuclear plant surveillance programs, fracture mechanics for nuclear applications, and calculating plant ope rating P-T limits. Participated in st rategic planning sessions, and de veloped technical justifications for resolving key plant is sues at Calvert Cliffs 1&2, H. B. Robinson 2, Kewaunee, Beaver Valley 1, D. C.
Ke y C ontribut or to EP R I MR P R e a c tor I nter na l s I ssues Ta sk Gr oup, 2000  2015. S u m m ar y Mr. G rie sbac h ha s ove r 35 y e a rs of e x pe rie nc e in m a ter ials be ha vior a nd st ruc tura l int e g rity of major nuc lea r c omponents. He spec ializ e s in t e c hnica l consult ing uti li z ing state-of-the-a rt tec hnolog ies f or mi ti g a ti ng a nd re solvi ng mate ria l deg ra da ti on c onc e rns in nuc lea r r e a c tor ve ssels, i nter na ls, pi ping , a nd other major c omponents. Ke y a c c ompl ishm e nts i nc lude:  I n c ha rg e of nu mer ous EP R I proje c ts t o de ve lop t ools for mana g ing a g ing e ff e c ts s uc h a s fa ti g ue a nd re a c tor ve ssel e mbrit tl e ment in nucle a r pr e ssure ve ssels. Author e d many r e ports a nd tec hnica l pape rs on ma int a ini ng struc tura l i n teg rity of nu c lea r plant c omponents, m a ter ials t oug hne ss and e mbrit tl e ment pr e diction m ode ls, data ba se s for moni toring ve ssel mate ria l prope rties, a nd st ra teg ic pla nning f or li c e nse r e ne wa l. I nter fa c e d with ut il it ies, N EI , a nd NRC to re solve c ritica l i ndus try iss ue s such a s P re ssuriz e d The rma l S hoc k in P W R s and I nteg ra ted Surve il lanc e P rog ra ms for B W R s P roje c t t e a m l e a de r f or succ e ssful c ompetit ive bids on m a jor indust ry proje c ts for r e a c tor ve ssel ther mal a nne a li ng , P W R int e rna ls ag ing mana g e ment f or li c e n se r e ne wa l, B W R VI P I nteg ra ted Surve il lanc e P rog ra m, and pr oba bil ist ic me thods f or de ve lopi ng ope ra ti ng P-T li mi t c ur ve s. C onduc ted w or kshops and util it y tra ini ng c lasse s for mana g ing r e a c tor ve ssel int e g rity , nuc lea r pla nt surve il lanc e prog ra ms, fr a c ture mec ha nics f or nuc lea r a ppli c a ti ons, a nd c a lcula ti ng plant ope ra ti ng P-T li mi ts. P a rticipa ted in st ra teg ic pla nning sessions, and de ve loped te c hnica l j usti fic a ti ons for r e solvi ng ke y plant is sues a t C a lver t C li ff s 1&2, H. B. Rob inson 2, Ke wa une e , B e a ve r V a l ley 1, D. C.
Cook 1&2, McGuire 1&2, Catawba 1&2, and Farley Unit 2. Part of the team that developed indust ry strategic plan for aging management of PWR vessel internals under the EPRI Materials Reliability Program. Member of the ASME Section XI Standards Committee. Selected Publications 1. Simple Mixing Model for Pressurized Thermal Shock Applications Nuclear Engineering and Design, Volume 74, I ssue 2, February 1983. pp 193197.
C ook 1&2, Mc Guire 1&2, Cata wba 1&2, a nd F a rle y Unit 2. P a rt of the te a m t ha t deve loped indust ry stra teg ic pla n for a g ing mana g e ment of P W R ve ssel int e rna ls und e r the EPR I Mate ria ls R e li a bil it y P rog ra m. Membe r of the A S ME S e c ti on XI S tanda rds C omm it tee. S e lec te d P u b li c at ion s 1. Simple M ixing M ode l f or Pre ssuri ze d T he rmal Shoc k Appli c ati ons Nuc lea r Eng inee ring a nd De sig n , Volume 74, I ssue 2 , F e br ua ry 1983. pp 193197.
T. J. Griesbach Page 3  7/2015 2. Griesbach, T. J., Riccardell Application of Fat igue Monitoring to the Evaluation of Pressurizer Surge Li nes Issue 2, August 1991. pp 163176. 3. Dynamic Elastic-Plastic Behavior of Circumferential Cracks in a Pipe Subject to Seismic Loading ConditionsJournal of Pressure Vessel Technology, Vol. 105, No. 1, February 1983. pp 63-72. 4. Timothy J. Griesbach, Dilip Dedhia, David O. Ha rris, Nathaniel G. Cofie, Kyle Amberge and Aparna AlleshwaramThe Influence of Flow Strength and Fracture Toughness on the Computed Reliability of Thermally Aged Grade CF-8M Cast Austeniti c Stainless Stee l Piping, ASME 2014 Pressure Vessels and Piping Conference, Paper No. PVP2014-28089, Anaheim, CA (2014)
T. J. G r i e sb ac h P age 3  7/2 0 1 5 2. Gr iesba c h , T. J., R icc a rde ll Appli c ati on of Fat igue M onit oring to t he Ev aluat ion of Pre ssuri ze r Surge Li ne s I ssue 2 , Aug ust 19 91. pp 163176. 3. Dy namic Elast ic-Plast ic Be hav ior of C ircum fere nti al C rack s in a Pipe Subjec t t o Se ismi c L oading C ondit ionsJ ourna l of P re ssure Ve ssel Te c hnolog y , Vol. 105, No. 1, F e br ua ry 198 3. pp 63-72. 4. Timo thy J. Gr iesba c h , Dili p De dhia , Da vid O. Ha rr is , Na thanie l G. C of ie , Ky le A mber g e a nd Apa rna Alleshw a ra mT he I nfl ue nc e of Fl ow St re ngth and Fracture T oughne ss on t he C ompute d Re li abil it y of T he rmall y Age d Gra de C F-8M Cast Austeniti c Stai nless Stee l Pipi ng , ASM E 2014 P re ssure Ve ssels a nd P ipi ng C onfe re nc e , P a pe r N o. P VP2014-28089, Ana he im , CA (2014)
. 5. H. S. Mehta, G. L. Stevens; D. V. S ommerville; M. B enson; M. Kirk, T. J
. 5. H. S. M e hta, G. L. S teve ns; D. V. S omm e rville; M. B e nson; M. Kirk, T. J. Gr iesba c h, a nd J.
. Griesbach, and J.
T re atme nt of Stresse s Ex c e e ding Mate rial Y ield Str e ngth i n ASM E Code Se c ti on XI Appe ndix G Frac ture T oughne ss Ev aluat ions , ASM E 2014 P re ssure Ve ssels a nd P ipi ng C onfe re nc e , P a pe r N o. P VP2014-28397, Ana he im , CA (2014)
Treatment of Stresses Exceeding Mate rial Yield Strength in ASME Code Se ction XI Appendix G Fracture Toughness Evaluations, ASME 2014 Pressure Vessels and Piping Conference, Paper No. PVP2014-28397, Ana heim, CA (2014)
. 6. T he Eff e c t of I rradi ati on and Aging on Pre ssure Ve ssel Stee l Embrit tl e me ntNuc lea r Pl a n t Ag ing , Ava il a bil it y F a c tor, a nd Reli a bil it y Ana ly sis , S a n Die g o, CA, J uly 7, 1985, Ame ric a n S oc iety f or Meta ls, (1986). p. 375 7.
. 6. The Effect of Irradiation and Aging on Pressure Vessel Stee l EmbrittlementNuclear Plant Aging, Availability Factor, and Reliability Analysis, San Diego, CA, July 7, 1985, Ame rican Society for Metals, (1986)
M aterial s Aging Manage me nt Progr ams at N uc lear Power Plants in t he United States , I AEA 2 nd I nter na ti ona l S y mpos ium on Nuc lea r Powe r P lant L ife Man a g e ment, Oc tober , 2007, S ha ng ha i, C hina. 8.
. p. 375
A Probabil ist ic Ap proac h to Baf fl e Bolt IASCC Pre dictionsrd I nter na ti ona l C onfe re nc e on Nuc lea r Po we r Pl a nt L ife Mana g e ment (P L iM) f or L ong Te rm O pe ra ti ons (L TO), May , 2012 , S a lt L a ke C it y , Uta h, USA. 9. Fatig ue L if e ti me Mon it oring in Power Plants n F a ti g ue L ife ti me Pre dictive 473. I nter na ti ona l J ourna l of F a ti g ue , 12 (1), 65 (1993). 10. Kuo, A.-Y., R icc a rde ll a , P. C., a nd Gr iesba c h, T. J., De v e lopme nt and Usage of P-T C alculator a PC-Base d Com puter Program for C onst ructing P-T L imit C urve sof a P re ssure Ve ssel a nd P ipi ng C onfe re nc e , Vol. 195: AS ME, Ne w Y or k (19 90). p p 141-148. 11.
: 7.
Aging Manage me nt Strat e gies for Pr e ssuri ze d W ater Re ac tor Vesse l Inte rnal s a nd P ipi ng C onfe re nc e , P a pe r N o. P VP2004-3055, J uly 2004. pp. 37  41.
Materials Aging Manage ment Programs at Nuclear Power Plants in the United States
T. J. G r i e sb ac h P age 4  7/2 0 1 5   12. Ope ning and Ex tension of C ircum fere nti al C rack s in a Pipe Su b jec t t o Dy namic L oadsP a pe r F 5/1, S truc tura l Mec ha nics in R e a c tor Te c hnolog y , S Mi R T-5, B e rlin, Ge rma ny , (1979). 13. Radiat ion Embrit tl e me nt Me c hanis ti c M ode li ng 17 0. 14. Gr iesba c h, T. J., a nd S e rve r, W. L., A Consi de ra ti on of S c a tt e r in Radia ti on Da mag e Tr e nd Effec ts of Radiat ion on Mate rial s: 18 th Inte rnat ional Sy mposium, ASTM ST P 1325 , R. K. Na nstad, M. L. Ha mi lt on, F. A. G a rne r, a nd A. S. Kumar , Eds., Ame ric a n S oc iety f or Te sti ng a nd Mate ria ls, (1999). pp 500  507. 15. An O v e rv iew of Radiat ion Embritt lem e nt Mode li ng for Re ac tor Vesse l St e e ls t of N uc lea r R e a c tor Pre ssure Ve ssel S tee ls: An I nter na ti ona l R e view (F ourth V olum e), A S TM S TP 1170, L. E. S tee le, Ed., Ame ric a n S oc iety f or Te sti ng a nd Mate ria ls, (1993). pp 99  117.}}
, IAEA 2nd International Symposium on Nuclear Power Plant Life Management, October, 2007, S hanghai, China. 8.
A Probabil istic Approach to Baffle Bolt IASCC Predictionsrd International Conference on Nuclear Power Plant Life Management (PLiM) for Long Term Operations (LTO), May, 2012, Salt Lake City, Utah, USA. 9. Fatigue Lifetime Monitoring in Power Plantsn Fatigue Lifetime Predictive 473. International Journal of Fatigue, 12 (1), 65 (1993). 10. Kuo, A.-Y., Riccardella, P. C., and Griesbach, T. J., Development and Usage of P-T Calculator a PC-Based Computer Program for C onstructing P
-T Limit Curvesof a Pressure Vessel and Piping Conference, Vol. 195: AS ME, New York (1990). pp 141-148. 11.
Aging Manage ment Strategies for Pr essurized Water Reactor Vesse l Internals and Piping Conference, Paper No. PVP2004-3055, July 2004. pp. 37  41.
T. J. Griesbach Page 4  7/2015   12. Opening and Ex tension of Circumferential Cracks in a Pipe Subject to Dynamic LoadsPaper F5/1, Structural Mechanics in R eactor Technology, SMiRT-5, Berlin, Germany, (1979). 13. Radiation Embrit tlement Mechanistic Modeling 170. 14. Griesbach, T. J., and Server, W. L., A Consideration of Scatter in Radia tion Damage Trend Effects of Radiation on Mate rials: 18th International Symposium, ASTM ST P 1325, R. K. Na nstad, M. L
. Hamilton, F. A. Garner, and A. S. Kumar
, Eds., Ame rican Society for Testing and Materials, (1999)
. pp 500  507. 15. An Overview of Radiation Embrittlement Modeling for Reactor Vesse l Steelst of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume), ASTM STP 1170, L. E. Steele, Ed., American Society for Testing and Materials, (1993)
. pp 99  117.}}

Revision as of 00:55, 9 July 2018

ENT000617 - Curriculum Vitae of Timothy J. Griesbach
ML15222A821
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 08/10/2015
From:
Entergy Nuclear Operations
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 28133, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
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7/2 0 1 5 Tim othy J. Griesbach Senior A ss oci at e E d u c at ion M.S. Meta ll ur g y a nd Mate ria ls S c ienc e , Case W e ster n Rese rve Unive rsity (1974) B.S. Meta ll ur g y a nd Mate ria ls S c ienc e , Case W e ster n Rese rve Unive rsity (1972) P r of e ssi on al Associat ion s Ame ric a n Nuc lea r Soc iety , 1982 to pre se nt Ame ric a n S oc iety of Me c ha nica l Eng inee rs, 1982 to pr e se nt P r of e ssi on al E xp e r ience 2006 - P re se nt Sr. Assoc iat e , S truc tura l I nteg rity Assoc iate s, I nc. Mr. G rie sbac h is assi sti ng uti li ti e s on re a c tor ve ssel int e g rity iss ue s, mate ri a ls deg ra da ti on mana g e ment pr og ra ms, P W R r e a c tor ve ssel int e rna ls and plan t oper a ti ng iss ue s. 1993 - 2005 Direc tor of T e c hnical Se rv ice s, ATI C onsul ti ng. Mr. Gr iesba c h is int e rna ti ona ll y known f or his ex pe rtise in the a re a s of r e a c tor ve ssel e mbrit tl e men t and ve ssel int e g rity mana g e ment. Ac ti vit ies a t ATI include d c omponent li fe a ssessment, li fe a tt a inm e nt and a g ing mana g e ment st ra teg ies, ASM E Code a nd re g ulator y iss ue s con c e rning r e a c tor ve ssel int e g rity , a ppli c a ti on of a dva nc e d fr a c ture mec ha nics me thod s, ut il it y c ost control, a nd tec hnica l/mana g e ment de c isi on-making f or long-ter m compone nt l ife. 1982 - 1993 M anage r, C ompone nt Re li abil it y Program, Elec tric Powe r Re se a rc h I nsti tut e (1985 - 1993). Dire c ted ma jor r e se a rc h ini ti a ti ve to deve lop re media l m e a sure s for mana g ing r e a c tor ve ssel e mbrit tl e ment. Man a g e d pro g ra m t o de ve lop t he on-li ne f a ti g ue usag e moni toring sy stem for c ritica l re a c tor sy stem c omponents.

Projec t Manage r, N uc lear Safety Analysis C e nter (1982 to 1985). D e ve loped methodolog ies to r e solve g e ne ric saf e ty iss ue s includi ng pre ssuriz e d ther mal shock , B W R pipe c ra c king , stea m g e ne ra tor tube c ra c king , a nd c ontainment int e g rity. 1977 - 1982 Principal Engi ne e r, N uc lear Plant Engi ne e ring, C ombus ti on Eng inee ring , I nc. Eva luate d Response to N S S S c omponents t o sev e re ther mal, pr e ssure a nd dy na mi c loads. 1974 - 1977 M aterial s Enginee r, Mate rial s Enginee ring a nd Re se arch L aborat ory, P ra tt a nd W hit ne y Airc ra ft. D e ve loped dif fusion bonding proc e ss for f a br ica ti on of jet turbine blade s.

T. J. G ri es bach P age 2 7/2 0 1 5 Re late d E xp e r ience C ha irman , ASM E Sec ti on XI W or king Gr oup on Ope ra ti ng P lant C riter ia, 1984 to pr e se nt. L oa ne d e mpl oy e e to C omm onwe a lt h Edison, P W R P lant Eng inee ring g roup, 1988. P a rticipa nt, US/US S R C oope ra ti ve P rog ra m on Ve ssel The rma l Anne a li ng , 1990 to 1993.

C onsul tant to I AEA on Ve ssel Embritt leme nt and Ma ter ials De g ra da ti on, 1990 to 1996.

Ke y C ontribut or to EP R I MR P R e a c tor I nter na l s I ssues Ta sk Gr oup, 2000 2015. S u m m ar y Mr. G rie sbac h ha s ove r 35 y e a rs of e x pe rie nc e in m a ter ials be ha vior a nd st ruc tura l int e g rity of major nuc lea r c omponents. He spec ializ e s in t e c hnica l consult ing uti li z ing state-of-the-a rt tec hnolog ies f or mi ti g a ti ng a nd re solvi ng mate ria l deg ra da ti on c onc e rns in nuc lea r r e a c tor ve ssels, i nter na ls, pi ping , a nd other major c omponents. Ke y a c c ompl ishm e nts i nc lude: I n c ha rg e of nu mer ous EP R I proje c ts t o de ve lop t ools for mana g ing a g ing e ff e c ts s uc h a s fa ti g ue a nd re a c tor ve ssel e mbrit tl e ment in nucle a r pr e ssure ve ssels. Author e d many r e ports a nd tec hnica l pape rs on ma int a ini ng struc tura l i n teg rity of nu c lea r plant c omponents, m a ter ials t oug hne ss and e mbrit tl e ment pr e diction m ode ls, data ba se s for moni toring ve ssel mate ria l prope rties, a nd st ra teg ic pla nning f or li c e nse r e ne wa l. I nter fa c e d with ut il it ies, N EI , a nd NRC to re solve c ritica l i ndus try iss ue s such a s P re ssuriz e d The rma l S hoc k in P W R s and I nteg ra ted Surve il lanc e P rog ra ms for B W R s P roje c t t e a m l e a de r f or succ e ssful c ompetit ive bids on m a jor indust ry proje c ts for r e a c tor ve ssel ther mal a nne a li ng , P W R int e rna ls ag ing mana g e ment f or li c e n se r e ne wa l, B W R VI P I nteg ra ted Surve il lanc e P rog ra m, and pr oba bil ist ic me thods f or de ve lopi ng ope ra ti ng P-T li mi t c ur ve s. C onduc ted w or kshops and util it y tra ini ng c lasse s for mana g ing r e a c tor ve ssel int e g rity , nuc lea r pla nt surve il lanc e prog ra ms, fr a c ture mec ha nics f or nuc lea r a ppli c a ti ons, a nd c a lcula ti ng plant ope ra ti ng P-T li mi ts. P a rticipa ted in st ra teg ic pla nning sessions, and de ve loped te c hnica l j usti fic a ti ons for r e solvi ng ke y plant is sues a t C a lver t C li ff s 1&2, H. B. Rob inson 2, Ke wa une e , B e a ve r V a l ley 1, D. C.

C ook 1&2, Mc Guire 1&2, Cata wba 1&2, a nd F a rle y Unit 2. P a rt of the te a m t ha t deve loped indust ry stra teg ic pla n for a g ing mana g e ment of P W R ve ssel int e rna ls und e r the EPR I Mate ria ls R e li a bil it y P rog ra m. Membe r of the A S ME S e c ti on XI S tanda rds C omm it tee. S e lec te d P u b li c at ion s 1. Simple M ixing M ode l f or Pre ssuri ze d T he rmal Shoc k Appli c ati ons Nuc lea r Eng inee ring a nd De sig n , Volume 74, I ssue 2 , F e br ua ry 1983. pp 193197.

T. J. G r i e sb ac h P age 3 7/2 0 1 5 2. Gr iesba c h , T. J., R icc a rde ll Appli c ati on of Fat igue M onit oring to t he Ev aluat ion of Pre ssuri ze r Surge Li ne s I ssue 2 , Aug ust 19 91. pp 163176. 3. Dy namic Elast ic-Plast ic Be hav ior of C ircum fere nti al C rack s in a Pipe Subjec t t o Se ismi c L oading C ondit ionsJ ourna l of P re ssure Ve ssel Te c hnolog y , Vol. 105, No. 1, F e br ua ry 198 3. pp 63-72. 4. Timo thy J. Gr iesba c h , Dili p De dhia , Da vid O. Ha rr is , Na thanie l G. C of ie , Ky le A mber g e a nd Apa rna Alleshw a ra mT he I nfl ue nc e of Fl ow St re ngth and Fracture T oughne ss on t he C ompute d Re li abil it y of T he rmall y Age d Gra de C F-8M Cast Austeniti c Stai nless Stee l Pipi ng , ASM E 2014 P re ssure Ve ssels a nd P ipi ng C onfe re nc e , P a pe r N o. P VP2014-28089, Ana he im , CA (2014)

. 5. H. S. M e hta, G. L. S teve ns; D. V. S omm e rville; M. B e nson; M. Kirk, T. J. Gr iesba c h, a nd J.

T re atme nt of Stresse s Ex c e e ding Mate rial Y ield Str e ngth i n ASM E Code Se c ti on XI Appe ndix G Frac ture T oughne ss Ev aluat ions , ASM E 2014 P re ssure Ve ssels a nd P ipi ng C onfe re nc e , P a pe r N o. P VP2014-28397, Ana he im , CA (2014)

. 6. T he Eff e c t of I rradi ati on and Aging on Pre ssure Ve ssel Stee l Embrit tl e me ntNuc lea r Pl a n t Ag ing , Ava il a bil it y F a c tor, a nd Reli a bil it y Ana ly sis , S a n Die g o, CA, J uly 7, 1985, Ame ric a n S oc iety f or Meta ls, (1986). p. 375 7.

M aterial s Aging Manage me nt Progr ams at N uc lear Power Plants in t he United States , I AEA 2 nd I nter na ti ona l S y mpos ium on Nuc lea r Powe r P lant L ife Man a g e ment, Oc tober , 2007, S ha ng ha i, C hina. 8.

A Probabil ist ic Ap proac h to Baf fl e Bolt IASCC Pre dictionsrd I nter na ti ona l C onfe re nc e on Nuc lea r Po we r Pl a nt L ife Mana g e ment (P L iM) f or L ong Te rm O pe ra ti ons (L TO), May , 2012 , S a lt L a ke C it y , Uta h, USA. 9. Fatig ue L if e ti me Mon it oring in Power Plants n F a ti g ue L ife ti me Pre dictive 473. I nter na ti ona l J ourna l of F a ti g ue , 12 (1), 65 (1993). 10. Kuo, A.-Y., R icc a rde ll a , P. C., a nd Gr iesba c h, T. J., De v e lopme nt and Usage of P-T C alculator a PC-Base d Com puter Program for C onst ructing P-T L imit C urve sof a P re ssure Ve ssel a nd P ipi ng C onfe re nc e , Vol. 195: AS ME, Ne w Y or k (19 90). p p 141-148. 11.

Aging Manage me nt Strat e gies for Pr e ssuri ze d W ater Re ac tor Vesse l Inte rnal s a nd P ipi ng C onfe re nc e , P a pe r N o. P VP2004-3055, J uly 2004. pp. 37 41.

T. J. G r i e sb ac h P age 4 7/2 0 1 5 12. Ope ning and Ex tension of C ircum fere nti al C rack s in a Pipe Su b jec t t o Dy namic L oadsP a pe r F 5/1, S truc tura l Mec ha nics in R e a c tor Te c hnolog y , S Mi R T-5, B e rlin, Ge rma ny , (1979). 13. Radiat ion Embrit tl e me nt Me c hanis ti c M ode li ng 17 0. 14. Gr iesba c h, T. J., a nd S e rve r, W. L., A Consi de ra ti on of S c a tt e r in Radia ti on Da mag e Tr e nd Effec ts of Radiat ion on Mate rial s: 18 th Inte rnat ional Sy mposium, ASTM ST P 1325 , R. K. Na nstad, M. L. Ha mi lt on, F. A. G a rne r, a nd A. S. Kumar , Eds., Ame ric a n S oc iety f or Te sti ng a nd Mate ria ls, (1999). pp 500 507. 15. An O v e rv iew of Radiat ion Embritt lem e nt Mode li ng for Re ac tor Vesse l St e e ls t of N uc lea r R e a c tor Pre ssure Ve ssel S tee ls: An I nter na ti ona l R e view (F ourth V olum e), A S TM S TP 1170, L. E. S tee le, Ed., Ame ric a n S oc iety f or Te sti ng a nd Mate ria ls, (1993). pp 99 117.

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