Testimony of Wa Boyd on Contention 6.* Testimony of Wa Boyd on Contention 6 Re Impact of Postulated Gaps in Boraflex Neutron Absorbing Matl Utilized in Spent Fuel Storage Racks. W/Certificate of Svc.Related CorrespondenceML20238A273 |
Person / Time |
---|
Site: |
Turkey Point |
---|
Issue date: |
08/31/1987 |
---|
From: |
Boyd W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
---|
To: |
|
---|
Shared Package |
---|
ML20237L743 |
List: |
---|
References |
---|
OLA-2, NUDOCS 8709090226 |
Download: ML20238A273 (16) |
|
|
---|
Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEAR3F0999-05, Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors & Draft NUREG-1022, Rev 2, Event Reporting Guidelines1999-09-14014 September 1999 Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors & Draft NUREG-1022, Rev 2, Event Reporting Guidelines L-99-201, Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors.Fpl Followed Development of NEI Comments on Rulemaking & Endorse These Comments1999-09-0707 September 1999 Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors.Fpl Followed Development of NEI Comments on Rulemaking & Endorse These Comments ML20206H4441999-05-0303 May 1999 Comment Opposing Proposed Rules 10CFR170 & 10CFR171 Re Rev of Fy 1999 Fee Schedules ML20205J0461999-04-0101 April 1999 Comment Supporting Proposed Draft Std Review Plan on Foreign Ownership,Control & Domination.Util Supports Approach Set Forth in SRP Toward Reviewing Whether Applicant for NRC License Owned by Foreign Corp.Endorses NEI Comments ML20205B3771999-03-16016 March 1999 Comment Opposing PRM 50-64 Re Liability of Joint Owners of Npps.Util Endorses Comments of NEI & Urges Commission to Deny Petition for Rulemaking ML17355A2511999-03-0909 March 1999 Comment Supporting Amend to Policy & Procedure for NRC Enforcement Actions Re Treatment of Severity Level IV Violations at Power Reactors.Util Also Endorses Comments of NEI on Revs L-98-306, Comment Opposing Proposed Rule 10CFR50 Re Requirements for Monitoring Effectiveness of Maint at NPP1998-12-10010 December 1998 Comment Opposing Proposed Rule 10CFR50 Re Requirements for Monitoring Effectiveness of Maint at NPP L-98-272, Comment on Draft Reg Guide DG-4005, Preparation of Suppl Environ Repts for Applications to Renew Nuclear Power Plant Operating Licenses1998-10-28028 October 1998 Comment on Draft Reg Guide DG-4005, Preparation of Suppl Environ Repts for Applications to Renew Nuclear Power Plant Operating Licenses L-98-252, Comment Supporting Proposed Rules 10CFR2 & 51 Re Streamlined Hearing Process for NRC Approval of License Transfers.Fpl Also Endorses Comments of NEI on Proposed Rule1998-10-0606 October 1998 Comment Supporting Proposed Rules 10CFR2 & 51 Re Streamlined Hearing Process for NRC Approval of License Transfers.Fpl Also Endorses Comments of NEI on Proposed Rule L-98-248, Comment Supporting Statement of Policy on Conduct of Adjudicatory Proceedings.Fpl Also Endorses Comments of NEI on Policy Statement1998-10-0505 October 1998 Comment Supporting Statement of Policy on Conduct of Adjudicatory Proceedings.Fpl Also Endorses Comments of NEI on Policy Statement ML17354A8741998-03-27027 March 1998 Comment Opposing Proposed Generic Communication,Lab Testing of nuclear-grade Activated Charcoal (M97978) ML17354B1061998-02-26026 February 1998 Submits Listed Requests for NRC EA Per 10CFR2.206 to Modify OLs for All FPL NPPs Until Licensee Can Demonstrate Open Communication Channels Exist Between NRC & Licensee.Also Requests EA to Address Alleged Discriminatory Practices ML20217M0751997-08-13013 August 1997 Licensee Response to Supplemental 10CFR2.206 Petitions Filed by Tj Saporito & National Litigation Consultants.Petition Provides No Basis for Extraordinary Relief Requested. Petition Should Be Denied.W/Certificate of Svc ML20217J4321997-08-0707 August 1997 Memorandum & Order.* Grants Staff Petition for Review & Reverses Presiding Officer Decision Requiring Staff to Issue Tetrick SRO License.Order Disapproved by Commissioner Diaz. W/Certificate of Svc.Served on 970807 ML20148P8461997-06-25025 June 1997 Memorandum & Order (Determination of Remand Question).* Concludes That Presiding Officer Reaffirms Determination That Response of Rl Tetrick to Question 63 of Exam to Be SRO Was Incorrect.W/Certificate of Svc.Served on 970626 ML17354A5521997-06-18018 June 1997 Comment Opposing Proposed NRC Bulletin 96-001,suppl 1, CR Insertion Problems. ML20141F5441997-06-13013 June 1997 NRC Staff Response to Presiding Officer Memorandum & Order (Questions Relevant to Remand).* Staff Submits That Tetrick Request for Reconsideration of Grading of Question 63 on SRO License Written Exam Should Be Denied ML20141F5711997-06-13013 June 1997 Supplemental Affidavit of B Hughes & Ta Peebles.* Affidavit Re Tetrick Request for Reconsideration of Grading of Question 63 on SRO License Written Exam.W/Certificate of Svc ML17354A5181997-05-27027 May 1997 Licensee Response to 10CFR2.206 Petition Filed by Tj Saporito & National Litigation Consultants.Petition Should Be Denied,Based on Listed Info.W/Certificate of Svc ML20148G6531997-05-27027 May 1997 Notice.* Forwards Documents Received & Read by Author from Rl Tetrick on 970317 W/O Being Served as Required Under Procedural Rules.W/Certificate of Svc.Served on 970527 ML20148G7071997-05-27027 May 1997 Memorandum & Order (Questions Relevant to Remand).* Rl Tetrick May Respond to Questions W/Filing Served Pursuant to Procedural Regulations W/Notarized Statement to Be Received by 970617.Certificate of Svc Encl.Served on 970527 ML20148G7501997-05-20020 May 1997 Memorandum & Order CLI-97-05.* Staff May Withhold Issuance of SRO License to Rl Tetrick Pending Further Order of Commission.W/Certificate of Svc.Served on 970520 ML17354A5631997-05-17017 May 1997 Second Suppl to 970423 Petition Requesting Enforcement Against Listed Util Employees by Imposing Civil Penalties, Restricting Employees from Licensed Activities & Revoking Unescorted Access ML20141C7331997-05-16016 May 1997 Order Extending Until 970616,time within Which Commission May Rule on NRC Staff 970416 Petition for Review of Presiding Officer Initial Decision.W/Certificate of Svc. Served on 970516 ML17354A5611997-05-11011 May 1997 Suppl to 970423 Petition Requesting Enforcement Action Against Util Former Executive Vice President,Site Vice President & Maint Superintendent by Imposing Civil Monetary Penalty ML20138J2331997-05-0202 May 1997 Affidavit.* Affidavit of B Hughes Re Denial of Application for SRO License for Rl Tetrick.W/Certificate of Svc ML20138J2271997-05-0202 May 1997 NRC Staff Response to Questions Posed in Commission Order of 970425.* Staff Respectfully Submits That Commission Should Undertake Review of Presiding Officer Decisions in Proceedings LBP-97-2 & LBP-97-6 ML20138J2241997-05-0202 May 1997 Line (Providing Omitted Citation).* Informs That Submitted Citation Inadvertently Omitted from Response to Questions Posed in Commission Order of 970425.W/Certificate of Svc ML20138J2401997-04-25025 April 1997 Scheduling Order.* Staff Instructed to File W/Commission,By COB 970502,response to Tetrick Argument Re Question 63 & Discussion of Legal Significance of Consistent Staff Practices.W/Certificate of Svc.Served on 970425 ML17354A5651997-04-23023 April 1997 Requests That NRC Take EA to Modify,Suspend or Revoke FPL Operating Licenses for All Four Nuclear Reactors Until Licensee Can Sufficiently Demonstrate to NRC & Public That Employees Encouraged to Freely Raise Safety Concerns ML20137X5921997-04-16016 April 1997 NRC Staff Petition for Commission Review of Presiding Officer Decisions in Proceeding (LBP-97-2 & LBP-97-6).* Commission Should Undertake Review of Presiding Officer Decisions in Proceeding.W/Certificate of Svc ML20137X5511997-04-11011 April 1997 NRC Request for Issuance of Order Staying Effectiveness of Presiding Officer Decisions in Proceeding (LBP-97-2 & LBP-97-6).* Commission Should Stay Effectiveness of Decision in Subj Proceeding.W/Certificate of Svc ML20137R3531997-03-27027 March 1997 Correct Copy of Memorandum & Order (Denial of Reconsideration,Stay).* Denies NRC Staff Motion for Reconsideration.W/Certificate of Svc.Served on 970327 ML20137F5551997-03-25025 March 1997 NRC Staff Response to Memorandum & Order of 970321.* Presiding Officer Should Grant Staff 970310 Motion for Reconsideration.W/Certificate of Svc ML20137F8251997-03-21021 March 1997 Memorandum & Order (Grant of Housekeeping Stay).* Orders That Effect of Initial Decision Postponed Until Close of Business on 970326.W/Certificate of Svc.Served on 970321 ML20137F5081997-03-17017 March 1997 NRC Staff Motion for Issuance of Stay.* Requests That Presiding Officer Deny NRC Staff Request for Issuance of Stay in Matter of Issuance of SRO License ML20137F5371997-03-17017 March 1997 NRC Staff Motion for Reconsideration in Matter of Rl Tetrick.* Requests That Presiding Officer Deny NRC Staff Request for Reconsideration ML20136F2981997-03-12012 March 1997 Memorandum & Order (Grant of Housekeeping Stay).* Informs That Initial Decision Issued by Presiding Officer on 970228 Postponed Until 970321 & Rl Tetrick May File Response by 970318.W/Certificate of Svc.Served on 970312 ML20136F2351997-03-10010 March 1997 NRC Staff Motion for Reconsideration Introduction.* Requests That Presiding Officer Reconsider Determination That Tetrick Passed Written Exam & Find,Instead,That Tetrick Failed Written Exam ML20136F3411997-03-10010 March 1997 NRC Staff Request for Issuance of Order Staying Effectiveness of Presiding Officers Initial Decision LBP-97-2.* Staff Submits That Presiding Officer Should Stay Effectiveness of Initial Decision.W/Certificate of Svc ML20136F2721997-03-0606 March 1997 Supplemental Affidavit of B Hughes.* Supports Staff Motion for Reconsideration of Presiding Officer Initial Decision of 970228.W/Certificate of Svc ML20138Q0191997-02-28028 February 1997 Initial Decision.* Concludes That Rl Tetrick Had Passing Score of 80% & Should Be Granted License as Sro. W/Certificate of Svc.Served on 970228 ML20134A6551997-01-23023 January 1997 Written Presentation of NRC Staff.* Staff Concludes That SE Turk Failed Written Exam & Did Not Establish Sufficient Cause to Change Grading of Answers to Listed Questions. Denial of Application for SRO License Should Be Sustained ML20134A6661997-01-23023 January 1997 Affidavit of B Hughes & Ta Peebles Re Denial of Application for SRO License.W/Certificate of Svc.Served on 970124 ML20129J5681996-10-23023 October 1996 Memorandum & Order (Error).* Informs of Incorrect Caption Identified in Order .W/Certificate of Svc.Served on 961023 ML20129D4981996-10-21021 October 1996 Memorandum & Order (Grant of Request for Hearing Scheduling).* Requests for Hearing Hereby Granted. W/Certificate of Svc.Served on 961021 ML20129D6681996-10-18018 October 1996 NRC Staff Answer to Rl Tetrick Request for Hearing.* Staff Does Not Oppose Request & Will Be Prepared to Submit Hearing File.W/Certificate of Svc & Notice of Appearance ML20129D4401996-10-0909 October 1996 Designating of Presiding Officer.* Pb Bloch Designated to Serve as Presiding Officer to Conduct Informal Adjudicatory Hearing in Proceeding of Rl Tetrick Re Denial of SRO License.W/Certificate of Svc.Served on 961010 ML17353A6311996-01-19019 January 1996 Decision & Remand Order Re FPL Discrimination Against RR Diaz-Robainas.FPL Ordered to Offer Reinstatement to RR Diaz-Robainas W/Comparable Pay & Benefits,To Pay Him Back Pay W/Interest & to Pay His Costs & Expenses Re Complaint ML17353A2471995-06-27027 June 1995 Comments on Proposed Rule Re, Review of NRC Insp Rept Content,Format & Style. 1999-09-07
[Table view] Category:TRANSCRIPTS
MONTHYEARML20247D4431989-03-21021 March 1989 Transcript of 890321 Hearing in Miami,Fl.Pp 1-91 ML20234E0771987-09-16016 September 1987 Transcript of 870916 Hearing in Miami,Fl.Pp 262-378. Supporting Documentation Encl ML20234D9241987-09-15015 September 1987 Transcript of 870915 Court Hearing in Miami,Fl Re Spent Fuel Expansion.Pp 81-260.Supporting Documentation Encl ML20238A2731987-08-31031 August 1987 Testimony of Wa Boyd on Contention 6.* Testimony of Wa Boyd on Contention 6 Re Impact of Postulated Gaps in Boraflex Neutron Absorbing Matl Utilized in Spent Fuel Storage Racks. W/Certificate of Svc.Related Correspondence ML20238A2361987-08-31031 August 1987 Testimony of Gr Kilp & R Gouldy on Contention 6.* Testimony of Gr Kilp & R Gouldy on Contention 6 Re Matls Integrity of Fuel Assemblies & Spent Fuel Storage Racks in Spent Fuel Pool Environ.Related Correspondence ML20238A1301987-08-31031 August 1987 Testimony of Wc Hopkins on Contention 6.* Testimony of Wc Hopkins on Contention 6 Re Potential for Matls Deterioration or Failure of Pool Liner & Concrete Pool Structure Due to Radiation.Related Correspondence ML20238A0751987-08-31031 August 1987 Testimony of Ew Thomas on Contention 6.* Testimony of Ew Thomas on Contention 6 Re Matl Deterioration or Failure in Matls Integrity of Spent Fuel Pool Liner & Concrete Pool Structure Due to Heat.Related Correspondence ML20238A0421987-08-31031 August 1987 Testimony of R Gouldy on Contention 5.* Testimony of R Gouldy on Contention 5 Re Administrative Controls for Loading Spent Fuel Into Spent Fuel Pool Storage Racks. Related Correspondence ML20238A0211987-08-31031 August 1987 Testimony of Ee Demario on Contention 5.* Testimony of Ee Demario on Contention 5 Re Effects of Seismic Loads That Spent Fuel Storage Racks Could Exert Upon Fuel Assemblies within Spent Fuel Storage Rack.Related Correspondence ML20237L8161987-08-31031 August 1987 Testimony of He Flanders on Contention 5.* Testimony of He Flanders on Contention 5 Re Structural Integrity of Spent Fuel Pool Storage Racks.Related Correspondence ML20237L8041987-08-31031 August 1987 Testimony of Cd Sellers Re Contention 6.* Related Correspondence ML20237L7991987-08-31031 August 1987 Testimony of SB Kim & DG Mcdonald Re Contention 5.* Related Correspondence ML20138J0131985-12-12012 December 1985 Transcript of 851212 Evidentiary Hearing in Miami,Fl. Pp 603-913.Supporting Documentation Encl ML20138J1501985-12-11011 December 1985 Transcript of 851211 Evidentiary Hearing in Miami,Fl.Pp 441-602 ML20137M0981985-12-10010 December 1985 Prefiled Outline of Testimony of G Edwards Supporting Intervenor Contention That DNBR Limit of 1.17 for Optimized Fuel Assembly in Transitional Mix Core Will Reduce Safety Margin.Certificate of Svc Encl.Related Correspondence ML20138H8531985-12-10010 December 1985 Transcript of 851210 Evidentiary Hearing in Miami,Fl. Pp 234-440.Supporting Documentation Encl ML20137H9101985-11-26026 November 1985 Testimony of EA Dzenis Re Board 850816 Order Denying Licensee Motion for Summary Disposition of Contention (D). DNBR Acceptance Limit of 1.17 w/WRB-1 Correlation Meets 95/95 Std.W/Certificate of Svc.Related Correspondence ML17340B2481981-05-18018 May 1981 Affidavit & Testimony of G Edwards Contentions 1 & 4b Re NUREG-0743,FES for Steam Generator Repair.Related Correspondence ML17340B2421981-05-15015 May 1981 Testimony on Contention 4B.Postulated Radioactive Releases Not Likely to Occur.Prof Qualifications Encl ML17340B2811981-05-12012 May 1981 Testimony Supporting Contention 1.Outlines Conservation Strategies That Offer Cost Alternatives to Facility Repair. Prof Qualifications Encl 1989-03-21
[Table view] Category:DEPOSITIONS
MONTHYEARML20247D4431989-03-21021 March 1989 Transcript of 890321 Hearing in Miami,Fl.Pp 1-91 ML20234E0771987-09-16016 September 1987 Transcript of 870916 Hearing in Miami,Fl.Pp 262-378. Supporting Documentation Encl ML20234D9241987-09-15015 September 1987 Transcript of 870915 Court Hearing in Miami,Fl Re Spent Fuel Expansion.Pp 81-260.Supporting Documentation Encl ML20238A2731987-08-31031 August 1987 Testimony of Wa Boyd on Contention 6.* Testimony of Wa Boyd on Contention 6 Re Impact of Postulated Gaps in Boraflex Neutron Absorbing Matl Utilized in Spent Fuel Storage Racks. W/Certificate of Svc.Related Correspondence ML20238A2361987-08-31031 August 1987 Testimony of Gr Kilp & R Gouldy on Contention 6.* Testimony of Gr Kilp & R Gouldy on Contention 6 Re Matls Integrity of Fuel Assemblies & Spent Fuel Storage Racks in Spent Fuel Pool Environ.Related Correspondence ML20238A1301987-08-31031 August 1987 Testimony of Wc Hopkins on Contention 6.* Testimony of Wc Hopkins on Contention 6 Re Potential for Matls Deterioration or Failure of Pool Liner & Concrete Pool Structure Due to Radiation.Related Correspondence ML20238A0751987-08-31031 August 1987 Testimony of Ew Thomas on Contention 6.* Testimony of Ew Thomas on Contention 6 Re Matl Deterioration or Failure in Matls Integrity of Spent Fuel Pool Liner & Concrete Pool Structure Due to Heat.Related Correspondence ML20238A0421987-08-31031 August 1987 Testimony of R Gouldy on Contention 5.* Testimony of R Gouldy on Contention 5 Re Administrative Controls for Loading Spent Fuel Into Spent Fuel Pool Storage Racks. Related Correspondence ML20238A0211987-08-31031 August 1987 Testimony of Ee Demario on Contention 5.* Testimony of Ee Demario on Contention 5 Re Effects of Seismic Loads That Spent Fuel Storage Racks Could Exert Upon Fuel Assemblies within Spent Fuel Storage Rack.Related Correspondence ML20237L8161987-08-31031 August 1987 Testimony of He Flanders on Contention 5.* Testimony of He Flanders on Contention 5 Re Structural Integrity of Spent Fuel Pool Storage Racks.Related Correspondence ML20237L8041987-08-31031 August 1987 Testimony of Cd Sellers Re Contention 6.* Related Correspondence ML20237L7991987-08-31031 August 1987 Testimony of SB Kim & DG Mcdonald Re Contention 5.* Related Correspondence ML20138J0131985-12-12012 December 1985 Transcript of 851212 Evidentiary Hearing in Miami,Fl. Pp 603-913.Supporting Documentation Encl ML20138J1501985-12-11011 December 1985 Transcript of 851211 Evidentiary Hearing in Miami,Fl.Pp 441-602 ML20137M0981985-12-10010 December 1985 Prefiled Outline of Testimony of G Edwards Supporting Intervenor Contention That DNBR Limit of 1.17 for Optimized Fuel Assembly in Transitional Mix Core Will Reduce Safety Margin.Certificate of Svc Encl.Related Correspondence ML20138H8531985-12-10010 December 1985 Transcript of 851210 Evidentiary Hearing in Miami,Fl. Pp 234-440.Supporting Documentation Encl ML20137H9101985-11-26026 November 1985 Testimony of EA Dzenis Re Board 850816 Order Denying Licensee Motion for Summary Disposition of Contention (D). DNBR Acceptance Limit of 1.17 w/WRB-1 Correlation Meets 95/95 Std.W/Certificate of Svc.Related Correspondence ML17340B2481981-05-18018 May 1981 Affidavit & Testimony of G Edwards Contentions 1 & 4b Re NUREG-0743,FES for Steam Generator Repair.Related Correspondence ML17340B2421981-05-15015 May 1981 Testimony on Contention 4B.Postulated Radioactive Releases Not Likely to Occur.Prof Qualifications Encl ML17340B2811981-05-12012 May 1981 Testimony Supporting Contention 1.Outlines Conservation Strategies That Offer Cost Alternatives to Facility Repair. Prof Qualifications Encl 1989-03-21
[Table view] Category:NARRATIVE TESTIMONY
MONTHYEARML20247D4431989-03-21021 March 1989 Transcript of 890321 Hearing in Miami,Fl.Pp 1-91 ML20234E0771987-09-16016 September 1987 Transcript of 870916 Hearing in Miami,Fl.Pp 262-378. Supporting Documentation Encl ML20234D9241987-09-15015 September 1987 Transcript of 870915 Court Hearing in Miami,Fl Re Spent Fuel Expansion.Pp 81-260.Supporting Documentation Encl ML20238A2731987-08-31031 August 1987 Testimony of Wa Boyd on Contention 6.* Testimony of Wa Boyd on Contention 6 Re Impact of Postulated Gaps in Boraflex Neutron Absorbing Matl Utilized in Spent Fuel Storage Racks. W/Certificate of Svc.Related Correspondence ML20238A2361987-08-31031 August 1987 Testimony of Gr Kilp & R Gouldy on Contention 6.* Testimony of Gr Kilp & R Gouldy on Contention 6 Re Matls Integrity of Fuel Assemblies & Spent Fuel Storage Racks in Spent Fuel Pool Environ.Related Correspondence ML20238A1301987-08-31031 August 1987 Testimony of Wc Hopkins on Contention 6.* Testimony of Wc Hopkins on Contention 6 Re Potential for Matls Deterioration or Failure of Pool Liner & Concrete Pool Structure Due to Radiation.Related Correspondence ML20238A0751987-08-31031 August 1987 Testimony of Ew Thomas on Contention 6.* Testimony of Ew Thomas on Contention 6 Re Matl Deterioration or Failure in Matls Integrity of Spent Fuel Pool Liner & Concrete Pool Structure Due to Heat.Related Correspondence ML20238A0421987-08-31031 August 1987 Testimony of R Gouldy on Contention 5.* Testimony of R Gouldy on Contention 5 Re Administrative Controls for Loading Spent Fuel Into Spent Fuel Pool Storage Racks. Related Correspondence ML20238A0211987-08-31031 August 1987 Testimony of Ee Demario on Contention 5.* Testimony of Ee Demario on Contention 5 Re Effects of Seismic Loads That Spent Fuel Storage Racks Could Exert Upon Fuel Assemblies within Spent Fuel Storage Rack.Related Correspondence ML20237L8161987-08-31031 August 1987 Testimony of He Flanders on Contention 5.* Testimony of He Flanders on Contention 5 Re Structural Integrity of Spent Fuel Pool Storage Racks.Related Correspondence ML20237L8041987-08-31031 August 1987 Testimony of Cd Sellers Re Contention 6.* Related Correspondence ML20237L7991987-08-31031 August 1987 Testimony of SB Kim & DG Mcdonald Re Contention 5.* Related Correspondence ML20138J0131985-12-12012 December 1985 Transcript of 851212 Evidentiary Hearing in Miami,Fl. Pp 603-913.Supporting Documentation Encl ML20138J1501985-12-11011 December 1985 Transcript of 851211 Evidentiary Hearing in Miami,Fl.Pp 441-602 ML20137M0981985-12-10010 December 1985 Prefiled Outline of Testimony of G Edwards Supporting Intervenor Contention That DNBR Limit of 1.17 for Optimized Fuel Assembly in Transitional Mix Core Will Reduce Safety Margin.Certificate of Svc Encl.Related Correspondence ML20138H8531985-12-10010 December 1985 Transcript of 851210 Evidentiary Hearing in Miami,Fl. Pp 234-440.Supporting Documentation Encl ML20137H9101985-11-26026 November 1985 Testimony of EA Dzenis Re Board 850816 Order Denying Licensee Motion for Summary Disposition of Contention (D). DNBR Acceptance Limit of 1.17 w/WRB-1 Correlation Meets 95/95 Std.W/Certificate of Svc.Related Correspondence ML17340B2481981-05-18018 May 1981 Affidavit & Testimony of G Edwards Contentions 1 & 4b Re NUREG-0743,FES for Steam Generator Repair.Related Correspondence ML17340B2421981-05-15015 May 1981 Testimony on Contention 4B.Postulated Radioactive Releases Not Likely to Occur.Prof Qualifications Encl ML17340B2811981-05-12012 May 1981 Testimony Supporting Contention 1.Outlines Conservation Strategies That Offer Cost Alternatives to Facility Repair. Prof Qualifications Encl 1989-03-21
[Table view] |
Text
- - - _ _ - _ - _ _ _ - _ _ _
4 1 2
UNITED STATES OF AMERICA 3 NUCLEAR hEGULATORY COMMISSION 4 BFFORE THE ATOMIC SAFETY AND LICENSING BOARD 5
b 6 )
In the Matter of )
7 )
FLORIDA POWER & LIGHT COMPANY ) Docket Nos. 50-250, OLA-2 8 (Turkey Point Nuclear ) 50-251, OLA-2 Generating Station c ) (Spent Fuel Pool Expansion) 9 Units 3 & 4) )
) i 10 !
11 Testimony of William A. Boyd ,
on Contention Number 6 12 13 01: Please state your name, occupation and business 14 address.
15 A1: My name is William A. Boyd. I am a Senior Engineer ,
16 in Nuclear Design for the Nuclear Fuel Division of 17 Westinghouse Electric Corporation. My business 18 address is Westinghouse Electric Corporation, 19 Monroeville Mall Office Building, P.O. Box 3912, 20 Pittsburgh, PA, 15320.
21 Q2: Please describe your professional qualifications.
22 A2: A summary of my professional qualifications and 23 experience is attached as Exhibit A, and is incor-24 porated herein by reference.
25 03: What is the purpose of your testimony?
26 27 28 9709090226 B70831 DR ADOCK05000ggO
,: 1 2 A3:- -The purpose of my testimony is to. address
.3 ' Contention 6. Contention 6 and the bases for that
-4 contention are as follows:
'S Contention 6 6 The Licensee and Staff have not ade-quately considered or analyzed 7 materials deterioration or failure in materials integrity resulting 8 from. increased generation.and heat and radioactivity, as a result of 9 increased capacity and long-term storage, in the spent fuel pool.
Bases for Contention 11 The spent fuel facility at Turkey 12 Point was originally designed to store a lesser amount of fuel for a 13 short period of time. Some of the problems.that have not been. analyzed 14 properly are:
15 (a) deterioration of fuel cladding and decay heat and radiation levels 16 during extended periods of pool storage.
(b) loss of materials integrity of 18 storage rack and pool liner as a result of exposure to higher levels 19 of radiation over longer periods.
20 (c) deterioration of concrete' pool structure as a result of exposure to j 21 increased heat over extended periods of time.
22
}
In particular, the purpose of my testi-23 mony is to address the impact of postulated gaps in the Boraflex neutron absorbing material utilized in 25 l the Turkey Point spent fuel storage racks. The Testimony of William C. Hopkins on Contention 28 L________-___-__-____--_
~,.
)
e- 1 I
2 Number 6 and the Testimony of Eugene W. Thomas on l 3
Contention Number 6 discuss the materials integrity 4
of the spent fuel pool liner and the spent fuel
.5 - pool concrete structure. The testimony of Dr.
6 Gerald R. Kilp and Russell Gouldy on Contention 7 Number 6 discusses the materials integrity of the 8 fuel assemblies and spent fuel storage racks in the
- 9 spent fuel pool environment.
10 04: Have you previously prepared an affidavit in this 11 proceeding?
12- A4: Yes. I prepared the Affidavit of William A. Boyd 13 on Contention 10 (January 20, 1986), which was 14 submitted in support of Licensee's Motion for 15 Summary Disposition of Interveners' Contentions 16 (January 23, 1986). The purpose of that affidavit 17 was to describe the criticality analyses performed 18 by me for the Turkey Point spent fuel pool expan-19 sion amendments, to demonstrate that the analyses I 20- conformed with applicable industry standards and 21 employed methods accepted by the Nuclear Regulatory 22- Commission (NRC), and to show that the results of l 23 the analyses satisfy applicable NRC criteria. As a H24 result of these analyses, the K-effective of Region 25 I was calculated to be 0.9403 and the K-effective 26 of Region II was calculated to be 0.9304, 27 accounting for all uncertainties and assuming the I t
28 )
)
4-
. 1 2 absence of boron in the spent fuel pool water.
3 These values satisfy various NRC guidelines and 4 industry standards which state that the K-effective l 5 of the spent fuel pools should be less than or 6 equal to 0.95. At pages 53-61 of its Memorandum 7 and Order of March 25, 1987, the Licensing Board 8 granted summary disposition of Contention 10 based j 9 upon my affidavit and those submitted by the NRC 10 Staff.
11 05: What assumptions did the analyses described in your 12 affidavit ma'.e t with respect to the Boraflex in the 13 spent fuel racks?
14 AS: The analyses included an assumption that the 15 Boraflex panels in the spent fuel racks would 16 remain intact and would not develop gaps.
17 06: How are Boraflex panels arranged in the Turkey 18 Point spent fuel pool racks?
19 A6: There are two regions in the Turkey Point spent 20 fuel pools. Tha Region I racks are designed to 21 hold fuel assemblies with a maximum Uranium-235 22 enrichment of 4.5%, and the Region II racks are 23 designed to hold fuel assemblies with a maximum !
24 reactivity equivalent to the reactivity of assem-25 blies having an initial enrichment of 1.5%.
26 27 28
1 2 The Region I spent fuel storage racks at 3 Turkey Point are each composed of a number of 4 cells. The cells are essentially square vertical 5 tubes. A cross-section of a storage cell, viewed 6 from directly above the cell, is depicted in Figure 7 1. Each cell is composed of a stainless steel cell 8 enclosure, Boraflex panels which run along the 9 length of the cell outside the cell enclosure on 10 each of the four sides of the cell, and thin steel l
11 wrappers which hold the Boraflex in place. thus, 12 the Boraflex panels provide neutron absorbing 13 capability on all sides of the cell. The Region II 14 racks have a somewhat similar structure, but 15 spacing between individual cells is smaller and the 16 density of the Boraflex panels is lower than in the 2
17 Pegicn I racks (Boron-10 area density of 0.02gm/cm 18 for Region I versus 0.012 gm/cm 2 ist Region II).
19 Q7: Have you made any analyses of the impact on K-20 effective of postulated gaps in the Boraflex 21 plates?
22 A7: Yes. After the reports of gaps in the Boraflex in 23 the storage racks at Quad Cites in Spring 1987, 24 Florida Power & Light Company (FPL) requested that 25 Westinghouse perform a sensitivity analysis to 26 determine the impact of postulating the existence 27 of various types of gaps in the Boraflex panels.
28
l
' =
r )
a .
6 2
0 1 1
_ A
(
N f- ;
_ _ E I T
8 N G E
4 E C R 1 -
O
- _ T E
- /
- - - /
R T S
) = E L
" 1
' T RL E 5 .. N OE 7 E 1 FC 0 C
)
_ " 0 j L E SE L R NG
( 2 2 x M E 0
E ) C C U OA
( R " / G I R SO U 50 I E
T S
O 7 8 1
1 F ESNT A L C X M
/ . M L I P N G " D E 8 5 R 7 2 7 =
E L 0 0 l ' l L
P L E 8 1
A P ( 0 .
N A C (
I R X H E M
\
L O F
R 1 N R
O B
z 1
n =
- - ' - s : '
1ll1 \l l l i1
1 t
i l
.i 1
2 This analysis was performed for the Region I 3
storage racks, because (1) the K-effective (K,gg) j I
4 is higher for Region I than for Region II, and l l
5 (2) the Region I spent fuel racks utilize a greater 6 thickness of Boraflex (Boron-10 area density of 2
7 0.020 gm/cm ) than the Region II racks (Boron-10 j 8 area density of 0.012 gm/cm 2). Thus, any gaps .in 9 the Boraflex in Region I racks would have more of ]
1 10 an effect on K eff levels than similar gaps in the 11 Region II racks and would be more likely to cause '
12 spent fuel pool K,gg levels to exceed the 0.95 13 limit.
14 08: What assumptions concerning the maximum enrichment 15 of fuel in the Turkey Point spent fuel pool were 16 made in your analysis?
17 A8: Two sets of calculations of K,gg were performed.
18 One set of calculations assumed that the stored >
19 fuel has a maximum fuel enrichment of 4.5% of )
20 Uranium 235, which is the maximum level of fuel 21 enrichment authorized to be stored at Turkey Point. j l
22 The second set of calculations assumed a maximum j 23 fuel enrichment of 4.1% of Uranium 235, which is j
24 the maximum fuel enrichment planned to be used at 25 Turkey Point prior to the next surveillance and I 26 27 a
28
-y- .
. 1 ,
2 testing of the Boraflex. The enrichment of the 3 fuel currently used at Turkey Point ranges from 4 3.4% to 3.6%.
5 09: What assumptions were made concerning the condition 6 of the Boraflex neutron absorbing material?
7 A9: Two cases were analyzed. First, gaps were postul-8 ated to exist in every Boraflex panel and to be
~
9 aligned at the mid-point of the fuel assemblies. )
10 Second, gaps were postulated to exist in half of 11 the Boraflex panels and to be aligned at the mid-12 point of the fuel assemblies. In both cases, the
^
13 gap size in the analysis was varied from 0 to 10 14 inches.
15 010: What method did you use to calculate the resulting 16 g ?
eff 17 A10: The method used to calculate K,gg was the same as 18 that described on pages 10 to 17 of my affidavit.
19 This method was accepted by the Board in its 20 March 25, 1987 Memorandum and Order, which granted -
21 summary disposition of Contention 10.
22 Oll: What were the results of your calculations?
23 All: If a 4.5% fuel enrichment level is assumed, the 24 calculations demonstrate that the Turkey Point 25 design basis K,ff limit of 0.95 is not exceeded in 26 the Region I racks even if aligned gaps up to 2" in 27 length are postulated to exist in all of the 28
._8-4 1 I 2 Boraflex panels. If gaps are postulated to exist 3 in only one-half of the panels, aligned gaps of up 4 to 3.5" may exist without exceeding the 0.95 K eff 5- limit. These results are depicted on Figure 2.
i 6 If a fuel enrichment level of 4.1% is assumed, 7 the calculations demonstrate that aligned gaps of j 8 up to 3.5" may exist in all panels without 9 exceeding the 0.95 K,gg limit, and aligned gaps of l 10 up to 7" may exist in one-half of the panels 11 without exceeding the 0.95 K,gg limit. These 12 results are depicted on Figure 3.
13 fr 2 : Are the assumptions used in your calculations ones 14 which can reasonably be expected to exist in the 15 Turkey Point spent fuel pools?
16 A12: No. The assumptions upon which these calculations 17 were based are very conservative and unrealistic 18 given the experience at Quad Cites. For example:
19 o Less than a third of the Boraflex panels 20- examined at Quad Cities had cracks. Assuming 21 gaps in more of the Boraflex plates results in 22 an increase in K,gg.
23 o For those Boraflex panels at Quad Cities which 24 had gaps, the average cumulative gap size (sum 25 of the length of all gaps on a single Boraflex '
I 26 27 l
28 l
6 y > ,
c -
s u
/
e t
+. :
a ,
S ./ 1 3
5 4
y f
- o ,
t 2 i -
5 n v :
3 '
i 4
i :
s s 2 : 2 .. e h
L i
- , c n
es c
U ,
I n
r r i o / 3 i
u -
e z
gS i
w .
i S
F.l E ,
p a
a 5 G 2
G 1 ,
X ,
E ,
_ t -
1 r i m
A i
L R .
S 0 T 3
- : _[ : - : - ~ : : __~ 0 0 0 0 0 0 0 0 0 9 8 7 6 5 3 0 9 9 9 9 9 9
. . . . ~ .
1 0 0 0 0 0 0 mm ~ a ; 8O c~-
!)il iij l
,i!l. l:i;) ;IIjll!1 I 11a,IIi1 .
0
/'
y ,
1 c .
u 9 t .
S s t
e.
a 8
y l . s ,
t P e ,
t i
4 l
a ,
v 5 7
1 .
P ,
l i
3 A 4 ,
.3t i
2 f i.
n
[ f o
6 h s
e c
U s p j 2 .
n es .a n I
r n /
G , i .
n
- u. o -
s P .
5 i
e z
gS G
,i w ,
i S
4 p p
[
/
_- a a'.
. G
.G 4 ,
3
/
.X ,
E t 2
_ i ,
m
/
i A L ,
1 R S ,
O T B 5 : _ ~ - i [ ..- _: _ - : 0 0 0 0 0 0 0 0 8 6 4 2 0 0 9 9 9 9 9 1
0 0 0 0 O
o5n [
<!illll l
-9_
. 1 2 panel) was 1.5 inches. Assuming gap sizes 3 greater than 1.5 inches results in an increase 4 in K eff*
5 o The gaps were located at different' elevations 6 along the Boraflex at Quad Cities and were not 7 aligned at the center of the fuel assembly.
8 Assuming alignment of the gaps results in an 9 increase in K Gaps which are out of eff.
10 alignment by more than approximately 5" (along 11 the 139" length of the Boraflex panels) would.
12 have a much smaller effect on K,gg levels.
13 Finally, the method utilized to calculate the 14 K,gg levels under these conditions contained a 15 number of other conservatism. These were 16 described in my affidavit and noted by the Board on 17 page 56 of its March 25, 1987 Memorandum and Order.
18 Q13: Do you have any conclusions with respect to the j 19 impact of postulated gaps in the Boraflex in the 20 Turkey Point spent fuel storage racks?
21 A13: Yes. Based on my calculations, the Turkey Point 22 spent fuel pools would remain within the 0.95 K,gg 23 limit even with a conservative estimate of 24 postulated gaps in the Boraflex panels. i
-25 26 27 28
t
, 1 EXHIBIT A 2
STATEMENT OF PROFESSIONAL QUALIFICATIONS 3 OF WILLIAM A. BOYD
~
4 My name is William A. Boyd, and my business address 5
is Westinghouse Electric Corporation, P.O. Box 3912, k 6
l '
Pittsburgh, Pennsylvania, 15230. I am a Senior Engineer in 7
the Core Engineering section of the Westinghouse Nuclear Fuel l
8 1 Division.
I graduated from Alliance College in 1973 with a \
10 Bachelors Degree in Mathematics. In 1975, I received a 11 Masters Degree from Drexel University in Electrical Engineering. I received a Masters Degree in Nuclear Engineering from the Massachusetts Institute of Technology in 1977.
15 From 1977 to 1981, I was a Design Engineer at the 16 General Electric Knolls Atomic Power Laboratory in -
Schenectedy, New York. My duties included the nuclear design and evaluation of a light water breeder reactor and certain navy propulsion reactors.
In June of 1981, I joined Westinghouse in the Nuclear Design section of the Nuclear Fuel Division, as a Senior Engineer B. My duties included the reload nuclear
- core design of the Turkey Point Unit 4 reactor. I was later given the added responsibility of fuel rack and shipping container criticality coordinator of the Nuclear Fuel Division. As the criticality coordinator my duties included 28
1 the direction, coordination, development and review of the methods used to perform all fuel rack and shipping container criticality analysis for the Nuclear Fuel Division. In 1984, 4
I was promoted to the position of Lead Engineer with the technical responsibility for the efforts of several engineers and technicians in the reload core nuclear design and anal-7 l ysis of the Point Beach Units 1&2, R. G. Ginna, and Prairie l 8 Island Units 1&2.
(
In 1986, I was transferred to the lead engineer position for Turkey Point Units 3 and 4.
12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28
f a
i
" fiOC K! IE UNITED STATES OF AMERICA t:g t NUCLEAR REGULATORY COMMISSION-
'BEFORE THE ATOMIC SA'FETY AND LICENSING BOARD '87 SEP -1 P2:29
)- Grrt tycKE Ok 4 <
vf i E h r W-
)
.In the Matter of ).
) Docket Nos. 50-250 OLA-2 FLORIDA POWER.& LIGHT COMPANY ) 50-251 OLA-2
)
(Turkey Point' Nuclear Generating )
Units ~3 & 4). )
)
CERTIFICATE OF SERVICE I hereby certify that' copies of the attached letter and:
Testimony of Harry E. Flanders, Jr. on Contention Number 5; Testimony of Edmund E. DeMario on Contention Number 5;
' Testimony of Russell Gouldy on Contention Number 5; Testimony of Eugene W. Thomas on Contention Number 6;
Testimony of William C. Hopkins on Contention Number 6; Testimony of Dr. Gerald R. Kilp and Russell Gouldy on Contention Number 6; Testimony of William A. Boyd on Contention Number 6 in the-above captioned proceeding were served on the following by deposit in the. United States mail, first class, properly stamped and' addressed, on the date shown below.
Dr. Robert M. Lazo, Chairman Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555
- J Dr. Emmeth A. Luebke L Atomic Safety and Licensing Board Panel L U.S. Nuclear Regulatory Commission I
- Washington, D.C. 20555 l
l
f L DrL Richard.F. Cole l- ' Atomic Safety and Licensing Board Panel U .' S . Nuclear Regulatory Commission
- Washingtony
- D.C. 20555 g Atomic Safety and' Licensing Board Panel H U.S.1 Nuclear Regulatory Commission Washington, D.C. 20555
' Atomic Safetyfand Licensing Appeal Board Panel U.S. Nuclear Regulatory Commission Washington, .D.C. 20555~
office of Secretary U.S. Nuclear RegulatoryfCommission Washington, D.C. ~20555-Attention: Chief, Docketing and' Service Section (Original plus two copies)
Joette.Lorion 7210 Red Road #208 Miami,'FL. 33143 Colleen P. Woodhead.
Office ~of' Executive Legal Director U.S.-Nuclear Regulatory Commission Washington. D.C. 20555 Norman-A. Coll
' Coll, Davidson, Carter, Smith, Salter & Barkett 3200 Miami Center 100 Chopin Plaza Miami, FL 33131 S
Steven.P. Frantz d Newman & Holtzinger, P.C.
1615 L Street, N.W.
Washington, D.C. 20036 Dated: . August 31, 1987
_ _ . _ _ _ . _ _ _ _ . _ _ _ . . _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _