ML092870289

Exhibit B - Statement of Professional Qualifications of Robert L. Palla

ML092870289
Person / Time
Site:	Indian Point
Issue date:	10/13/2009
From:	Palla R Office of Nuclear Reactor Regulation
To:	Atomic Safety and Licensing Board Panel
SECY RAS
Shared Package
ML092870100	List: ML092870115 ML092870154 ML092870206 ML092870215 ML092870265 ML092870274 ML092870289 ML092870335 ML092870361 ML092870433 ML092870444 ML092870586 ML092870592 ML092870631 ML092870640 ML092870644 ML092870672 ML092870677 ML092870678 ML092870679 ML092870685
References
50-247-LR, 50-286-LR
Download: ML092870289 (3)

Text

Indian Point Nuclear Generating Units 2 and 3 Docket Nos. 50-247/ 50-286-LR NRC Staff's Response in Opposition to State of New York's Motion for Partial Summary Disposition of NYS Contention 16116A Exhibit B

Robert L. Palla Senior Reactor Engineer Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Education M.S., Mechanical Engineering, University of Maryland, 1981 B.S., Mechanical Engineering, University of Maryland, 1975 Employment U.S. Nuclear Regulatory Commission, 1981 - present Performs technical evaluations of license applications and policy issues in the areas of severe accident progression and phenomena, containment performance, offsite consequences, and probabilistic risk assessment.

NRC lead on the following:

review of Severe Accident Mitigation Alternatives (SAMAs) for all license renewal applications to date, including Indian Point, all certified advanced reactor designs (ABWR, CE System 80+,

AP600 and AP1000); and initial plant licenses (Limerick, Comanche Peak, Watts Bar Unit 1) development of sections of Generic Environmental Impact Statement for License Renewal (NUREG-1437, Revision 1, Draft for Comment) related to severe accidents NRC headquarters support to NRC regions for Signifance Determination Process issueslfindings related to containment performance and large early release frequency development of NRC staff guidance on use of risk information in review of non-risk-informed license amendment requests, and all key documents, including SECY-99-246, Regulatory lssue Summaries 2000-7 and 2001-02, and Appendix D to SRP Chapter 19 review of industry severe accident management guidelines (SAMG) and severe accident management program implementation (including issuance of Generic Letter 88-20, Supp. 2) review of Level 2 (containment performance) and Level 3 (offsite consequences) portions of PRA and severe accident evaluations for all certified advanced reactor designs risk evaluation for Generic Safety Issue 189-Susceptibility of Ice Condenser and Mark Ill Containments to Early Failure from Hydrogen Combustion During a Severe Accident Task force member and contributing author on the following:

Review of petitions for rulemaking related to treatment of Spent Fuel Pool (SFP) fires and terrorism in environmental assessments NRC response to 911 1 in areas related to strategies for responding to loss of large areas of the plant (Item B.5.b), including development of Safeguards Advisories and Security Orders Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants (NUREG-1738)

NRC staff affidavit regarding the risk implications of a proposed expansion of spent fuel storage at Shearon Harris (Docket 50-400-LA; ASLBP No. 99-762-02-LA)

Risk Assessment of Severe Accident-Induced Steam Generator Tube Rupture (NUREG-1570)

Significance Determination Process for assessing risk significance of containment-related inspection findings as part of the Reactor Oversight Process (Manual Chapter 0609, Appendix H).

Member of Reactor Safety Team, USNRC Emergency Operations Center Professional Societies American Society of Mechanical Engineers