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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198Q8971998-12-17017 December 1998 Expresses Concerns Re License Renewal of Duke Energy,Oconee Nuclear Station,Units 1,2 & 3.Commends NRC on Steps Agency Has Undertaken to Conclude Renewal Process.With Certificate of Svc.Served on 990107 05000269/LER-1998-012, Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date1998-12-0303 December 1998 Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date 05000269/LER-1998-013, Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 9812021998-11-0202 November 1998 Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 981202 ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154B9421998-09-30030 September 1998 Amends Chattooga River Watershed Coalition Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew OLs for Oconee Nuclear Station,Units 1,2 & 3 ML20154A8971998-09-30030 September 1998 Requests That Submitted Info Be Attached to Amends to Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew Operating Licenses for Units 1,2 & 3 ML20153H6881998-09-27027 September 1998 Requests Consideration of Motion to Enlarge Time Required to Submit Amended Petition to Intervene in Proceeding Re Application of Duke Energy Corp to Renew OLs for Facilities ML20153E4721998-09-24024 September 1998 Forwards Notices of Appearances for Attorneys Representing Duke Energy Corp,Applicant in Proceeding for License Renewal of Oconee Units 1,2 & 3.With Certificate of Svc ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20151S7501998-08-31031 August 1998 Provides Update on Commitment Made by Licensee in Response to NOV & Imposition of Civil Penalty Re Valves in Ldst Instrument Lines That Were Incorrectly Translated Into Station Procedures ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236V9581998-07-27027 July 1998 Forwards Corrected Pages 3.5-30b of 961211 & 3.16-2 of 970205 TS Bases.Old Amend Numbers Were Left on Pages.Rev Changes Footer on Both Pages to Reflect Bases Changes ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20153D1961998-07-0909 July 1998 Requests NRC Reconsider & Grant Util Request for Exemption from Duplicative License Fee Under 10CFR171.11(d) for Storage of Spent Nuclear Fuel at Oconee Nuclear Station ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20247G0881998-05-14014 May 1998 Provides Rev 2 to Section 3.3, Instrumentation, in Support of TS-362 Amend Request.Position on Testing of Analog Trip Type Instruments W/Regard to Transition from CTS to ITS, Restated.Summary Description of Its/Bases Changes,Encl 05000269/LER-1998-002, Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown1998-04-30030 April 1998 Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown ML20217G0351998-03-26026 March 1998 Submits Ltr to Update Commitment Made by Oconee in Response to Subject Violation.Update Assures That Details of Particular CA Are Appropriately Contained in Docketed Correspondence ML20203J9301998-02-26026 February 1998 Submits Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Suppl 1 to Bulletin Attached & Contains Listed Commitments ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl 05000269/LER-1997-003, Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action1997-11-12012 November 1997 Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action ML20198Q5741997-11-0303 November 1997 Provides Suppl to Initial 971020 Application for Amend to TS Re SG Tubing Surveillance Requirements,In Response to NRC 971030 Request for Addl Info.Proprietary Rev 3 to BAW-2303P, OTSG Repair Roll Qualification Rept Encl.Rept Withheld ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20211F7981997-09-25025 September 1997 Submits Response to Violations Noted in Insp Repts 50-269/97-10,50-270/97-10 & 50-287/97-10 & Proposed Imposition of Civil Penalty in Amount of $330,000.Corrective Actions:Ldst Instrument Mods on All Three Units Completed ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20211C8021997-09-18018 September 1997 Forwards Revised TS Amend Re Reactor Bldg Structural Integrity.Previously Submitted TSs Contained Editorial Error ML20210T7121997-09-0404 September 1997 Informs That Representatives from Oconee Who Compose LERs Would Like to Meet W/Staff & AEOD at Convenient Place & Time to Facilitate Process.Concerns Addressed in Encl ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld 1999-08-10
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141C6191997-06-23023 June 1997 Forwards RAI Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Related Gate Valves ML20148E0001997-05-29029 May 1997 Forwards SER Re 960724 Request Relief from Volumetric Exam Coverage Requirements of ASME Code,Section XI,1989 Edition, for Certain Welds in SG & in Letdown Cooler Heat Exchangers for Oconee Units 1,2 & 3.Request Granted ML20140A7241997-05-27027 May 1997 Requests That Interim Response Be Provided to Encl Amended Questions Re High Pressure Injection/Makeup Line Crack Found at Plant,Unit 2.Response Requested by 970529 ML20137Z5171997-04-22022 April 1997 Forwards RAI Re Plants Response to NRR Draft Rept on Plant Emergency Power Sys ML20137R1641997-04-0808 April 1997 Forwards RAI Re 960819 Response to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation Casks ML20147G4521997-03-0404 March 1997 Forwards Responses to Four Questions Raised During Region II 1996 USNRC Training Managers Conference ML20135D3171996-12-0606 December 1996 Forwards RAI Re Licensee Responses to Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core,Or Over Safety-Related Equipment ML20134Q0761996-11-20020 November 1996 Conveys Results & Conclusions of Encl Operational Safeguards Response Evaluation,Conducted at Plant,Units 1,2 & 3 from 960520-23.W/o Encl ML20059F7201994-01-0606 January 1994 Forwards Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Failure to Protect Safeguards Info IR 05000269/19930281993-12-23023 December 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-28, 50-270/93-28 & 50-287/93-28 IR 05000269/19930291993-11-30030 November 1993 Discusses 931108 Enforcement Conference in Region II Ofc, Re Apparent Violation Noted in Insp Repts 50-269/93-29, 50-270/93-29 & 50-287/93-29 on 931019-27.List of Attendees, Meeting Summary & Licensee Presentation Encl IR 05000269/19930271993-11-18018 November 1993 Forwards Insp Repts 50-269/93-27,50-270/93-27 & 50-287/93-27.No Violations Identified ML20058B3811993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide to Facilitate Comments on Proposed Rule for Protection Against Malevolent Use of Vechicles at Nuclear Power Plants. W/O Encl IR 05000269/19930221993-11-0505 November 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-22, 50-270/93-22 & 50-287/93-22.Understands That Revised Response Will Be Provided by 931203 ML20062J5471993-10-29029 October 1993 Forwards SE of Util 930128 & 0714 Supplemental Responses to IE Bulletin 79-27.Concerns Specified in Bulletin Have Been Adequately Addressed IR 05000269/19930241993-10-19019 October 1993 Forwards Insp Repts 50-269/93-24,50-270/93-24 & 50-287/93-24 on 930829-0925 & Notice of Violation ML20057G2661993-10-15015 October 1993 Responds to Licensee 870407 Request for Relief from Certain Section XI ASME Code Requirements Re Pressure Testing of Purification Demineralizers.Informs That SE Will Not Be Supplemented Due to Relief Being Granted IR 05000269/19930231993-09-24024 September 1993 Forwards Insp Repts 50-269/93-23,50-270/93-23,50-287/93-23 & 72-0004/93-23 on 930823-28 & Notice of Violation ML20057C3451993-09-17017 September 1993 Forwards Insp Repts 50-269/93-22,50-270/93-22 & 50-287/93-22 on 930725-0828 & Notice of Deviation ML20059B5861993-09-10010 September 1993 Ltr Contract,Providing Incremental Funds to Task Order 73, Mod 1, Electrical Distribution Sys Functional Insp - Oconee, Under Contract NRC-03-90-031 IR 05000269/19930201993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-20, 50-270/93-20 & 50-287/93-20 IR 05000269/19930211993-08-18018 August 1993 Forwards Insp Repts 50-269/93-21,50-270/93-21 & 50-287/93-21 on 930627-0724 & Notice of Violation IR 05000269/19930171993-08-0909 August 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-17, 50-270/93-17 & 50-287/93-17.Response Meets Requirements of 10CFR2.201 1999-08-10
[Table view] |
Text
r-UNITED STATES q g
) ,, j - NUCLEAR REGULATORY COMMISSION
& WASHINGTON. D.C. - *1
\.' ***** April 8, 1997 Mr. J. W. Hampton-
- Vice President y Duke Power Company '
Oconee Nuclear Plant P.O. Box 1439 Seneca. SC 27679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - NRC BULLETIN NO. 96-04.
" CHEMICAL. GALVANIC. OR OTHER REACTIONS IN SPENT FUEL STORAGE AND
. TRANSPORTATION CASKS"
Dear Mr. Hampton:
This refers to your response dated August 19. 1996, to Nuclear Regulatory
' Commission Bulletin No. 96-04. " Chemical. Galvanic, or Other Reactions in Spent Fuel Storage and Trans)ortation Casks." Your submittal incorporated information prepared by VECTM Technologies. Inc. (VECTRA) in response to the bulletin. By letter dated March 24, 1997. NRC notified VECTRA that their response to the bulletin lacked sufficient information for NRC to confirm
. VECTRA's conclusion that hydrogen generated during loading and unloadino activities would not exceed the lower flammable limit. Therefore, we also believe that your submittal lacks the same information.
A notable concern is that VECTRA's August 16, 1996. submittal utilized a
" transfer resistance factor." to adjust test data to account for: (1) the hydrogen retained in the dry shielded canister water column due to diffusion transport resistance, and (2) hydrogen lost through the open vent. This conversion factor was develo)ed based on single samples taken during the loading of two different cascs. The staff does not believe sufficient information was obtained to accurately determine a conversion factor of this type. This is of concern because your staff used VECTRA's unclear and '
incomplete information as the basis for implementing procedural enhancements to minimize potentially hazardous conditions during cask loading and unloading.
Additionally, your August 19, 1996, submittal lacked sufficient detail for the staff to determine if hydrogen concentrations could accurately be detected and whether adequate actions would be taken to minimize hazardous conditions.
% hhN
[F488s 3n8jj[
- m. _s a ,,m, ~ -
. ._,4 . .4m4 r Mr..J. W. Hampton ,
Specifically, your submittal did not address monitoring hydrogen .
- concentrations during welding and cutting evolutions nor provide the specific hydrogen concentration at which corrective actions,-if necessary, would be implemented.
The staff acknowledges that ~aparoximately 60 NUHOMS canisters, at four '
different reactor sites, have 3een. loaded and welded without any type of ignition indications or incidents. Thus,~the staff does not have a safety issue. at this time, regarding the use of.the NUHOMS system. However, the technical analyses and engineering work submitted in response to NRC Bulletin -
No. 96-04 lacked a sufficient technical basis to support your conclusion that the hydrogen generated would not exceed the lower flammable limit. !
Enclosed is a request for additional information related to your submittal. ;
-If you have questions regarding this matter, please contact me at '
(301) 415-8538.
Sincerely.
Original signed by /s/
Timothy J. Kobetz. Project Manager Spent Fuel Licensing Section Spent Fuel Project Office Office of Nuclear Material Safety l and Safeguards 1
Dockets 72-4. 50-269/270/287 i i
Enclosure:
Request for Additional Information i
cc: NUHOM's Owners Group l Nuclear Energy Institute )
Service List l Distribution:.
' Docket 72-4 . ' ' ~w/ - .. NRC encl.File-Center PUBLIC NMSS r/f SFP0 r/f rDockets 50-269/270/287 S$hankman CHaughney WKane Region II DLaBarge NRR JDavis. NRR KBattige- VTharpe(2) MBailey BReckley, NRR WGloersen, RII !
- See attached concurrences
.Q OFC SFP0 W E NRR
- E SFP0 /E l NAME TKobetz:dd:vt ESullivan FSturz Eleeds N DATE- f /f /97 L/ / / /97 t/ / / /97 M/7/97 \
C - COVER E = COVER & ENCLOSURE N = NO COP ( }
OFFICIAL RECORD COPY G:\nuhams24\7210049 1.oco I ,
( i 4/8/97 :dd:
110055
I i
. Oconee Nuclear Station Units 1, 2,.and 3 cc: ,
. Mr. Paul R. Newton Mr. J. E. Burchfield, Jr.
i legal Department (PB05E) Compliance Manager Duke Power Company Duke Power Company-422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28242-0001 P. O. Box 1439 ;
Seneca, South Carolina 29679 J. Michael-McGarry, III Esquire
.Winston and Strawn Ms. Karen E. Long .
.1400 L Street. NW. Assistant Attorney General-Washington, DC 20005 North Carolina Department of l' Justice Mr. Robert B. Borsum P. O. Box 629 ;
Framatome Technologies Raleigh, North Carolina 27602 :
Suite 525
- 1700 Rockville Pike Mr. G. A. Copp i Rockville. Maryland 20852-1631 Licensing - EC050 ,
Duke Power Company :
Manager, LIS 526 South Church Street l NUS Corporation Charlotte, North Carolina 28242-0001 i 2650 McCormick Drive, 3rd Floor :
Clearwater. Florida 34619-1035 Senior Resident Inspector U. S. Nuclear Regulatory Commission '
Route 2. Box 610 Seneca. South Carolina 29678 Regional Administrator, Region II i U. S. Nuclear Regulatory Commission 101 Marietta Street NW. Suite 2900 ,
Atlanta, Georgia 30323 j Max Batavia, Chief Bureau of Radiological Health
-South Carolina Department of Health and Environmental Control ;
e 2600 Bull Street -
Columbia, South Carolina 29201 ;
County Supervisor of Oconee County -
Walhalla. South Carolina 29621 ,
- Mr. Dayne H. Brown, Director .
' Division of Radiation Protection North Carolina Department of Environment, Health and Natural Resources P. O. Box 27687 Raleigh,' North. Carolina 27611'-7687 ,
z 4
3
. Nuhoms Daners' Group.(72-1004) i (Mr. John P Stetz Mr J. W. Hampton Vice President - Nuclear. V,cd President .
Davis Besse- Duke Power Company !
Centierior Service Company Oconee Nuclear Site
.c/o Toledo Edison Company P. O. Box 1439 1 5501 North State Route 2 . Seneca. SC 29679 Oak Harbor. OH 43449 i Hr. Janes R. Shetler
' !v GPU Nuclear Corporation Deputy Assistant General Manager l
. Mr Michael B. Roche - Nuclear !
Vice President and Director Sacramento Municipal Utility. l Oyster Creek. Nuclear Station District !
~P. O. Box.388 6201 S Street Route 9 South - P. O. Box 15830 .
- Forked River,it) 08731-0388 Sacramento CA 95813 '
i Mr. Robert G. Byram Mr.'Jan Hagers :
Senior Vice President - Nuclear DEPARTMENT OF ENERGY ,
Pennsylvania Power and Light TMI/FSV Licensing Project Manager i Company .
Idaho Operations Office .
2 North Ninth Street 785 Doe Place Allentown PA 19101 Idaho Falls. ID 83403 .
Mr. William S. Crser Executive Vice President
' Nuclear Generation [ Brunswick] ;
Carolina Power and Light Company '
Sbuhp t, NC 28461 Mr. Charles H. Cruse Vice President - Nucl. ear Energy Calvert Cliffs Nuclear Plant 1650 Calvert Cliffs Parkway ,
Lusby MD P0657-4702 i
Mr. William B. Orser' '
. Executive Vice President Nuclear Generation H..B. Robinson 2 P. O. Box 1551-
' Rale 19h, NC. 27602 >
c
+ v -
r w
=
e REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE OCONEE NUCLEAR PLANT RL5PONSE TO NUCLEAR REGULATORY BULLETIN N0. 96 04 ,
IL. Provide justification that sufficient data was obtained from field experience and testing to support the methodology and calculations used in the computer simulation. Trio justification should support your conclusions.for pressurized water reactor (PWR) fuel storage. In addition.. provide the methodology and calculations used in the computer
lhis request is based on, but not limited to, the following information:
- VECTRA used data from only four canisters (0conee dry shielded canisters (DSCs) Nos. 37 through 40), loaded with PWR fuel, to justify that hydrogen concentrations will not reach the ;
' flammability limit. In addition, the hydrogen samples were not ,
taken by continuously monitoring the levels during the loading of l DSCs 37 through 40. Therefore, they may not be representative cf ;
the highest hydrogen concentrations obtained during cask loading. ,
. In the VECTRA August 16. 1996, submittal, a " transfer resistanca factor" was used to calculate the amount of hydrogen generated in the DSC air space. However, this conversion factor was developed based on single s:mples taken during the loading of two different 1
-casks. The staff does not believe sufficieni. information was l obtained to accurately determine a conversion factor of this type. !
Furthermore, when the transfer resistance factor is not used to adjust test data, the hydrogen levels )roduced exceed the lower flammability limit. It appears that t1e conversion factor was also used by the com) uter simulation discussed in VECTRA's October 18. 1996, su)mittel.
- The test methods and computer modeling used to obtain and evaluate data are vague and not presented in a manner that supports the final conclusions.
. Some tests are terminated at approximately 165 F even though !
the hydrogen production rate appears to still be increasing. )
The computer simulations were performed at temperatures i below 160*F. Therefore, the tests and computer simulations may not bound all conditions.
. There is no discussion of the maximum achievable hydrogen contentrations derived from the tests or computer simulations. All that is stated is that "H . concentrations 2
remain below the 4% flammability limit for water temperatures Delow 160'F."
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. 12. - Provide justification that a ' sufficient safety margin exists between the amount of hydrogen generated prior to welding and the lower flammability- ,
limit. ,
Data taken during the loading of the.four Oconee casks indicated that. :
in a flame sprayed aluminum and boric acid environment, hydrogen levels l could be generated in excess of 50% of the lower flammable limit. l However, there is no discussion of the recommended margin of safety that should exist between the amount of hydrogen produced and-the lower .
flammability limit. The staff has previously accepted a 0.4% limit of I hydrogen generation, which is 10% of the lower flammability limit. i
) 3. Describe the methods used to' monitor and control hydrogen during !
welding, grinding, or cutting operations associated with loading or ,
' unloading activities. ;
4 Provide the specific hydrogen concentration at which time the procedural ]
steps would implement corrective actions to minimize hazardous conditions. !
As stated in RAI Question No. 2. VECTRA's responses to NRC Bulletin No.
96-04 did not contain a discussion of the recommended margin of safety that.should exist between the amount of hydrogen produced and the flammability limit. The staff has previously accepted a 0.4% limit of hydrogen generation, which is 10% of the lower flammability limit.
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