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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given 1999-09-30
[Table view] Category:NRC TO ENGINEERING/CONSTRUCTION/CONSULTING FIRM
MONTHYEARML20154A1521988-08-17017 August 1988 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Also Available in Pdr. App B Documents Totally Withheld (Ref FOIA Exemption 5).App C Documents Partially Withheld (Ref FOIA Exemption 5) ML20235B2661987-07-0101 July 1987 Final Response to FOIA Request for Documents Re Tech Specs. Forwards App B Documents.App a & B Documents Also Available in PDR ML20237K4171987-06-30030 June 1987 Comments on Waste Form Qualification Testing Program for Bitumen NS-1 Decontamination Waste. Proposed Program Did Not Contain Suitable Indicators of Changes in Matl Properties.Specific Testing Methods Recommended in Encl ML20213H1481987-05-14014 May 1987 Partial Response to FOIA Request for Documents Re USI A-46, Seismic Qualification of Equipment in Operating Plants. Forwards App B Documents.App a & B Documents Available in PDR 1988-08-17
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given ML20154F6291998-10-0606 October 1998 Forwards Insp Rept 50-010/98-16 on 980723-0918.No Violations Noted.During Period Covered by Insp,Activities in Areas of Facility Mgt & Control,Spent Fuel Safety & Radiological Safety Examined ML20154B6761998-10-0101 October 1998 Informs That NRC Reviewed Comm Ed Submittals & Finds,Util Has Adequately Addressed Actions in GL 95-07,as Discussed in Encl SE ML20153C4941998-09-21021 September 1998 Forwards SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station IR 05000010/19980151998-08-13013 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Issued on 980629.Corrective Actions Will Be Examined During Future Insps ML20237B1321998-08-11011 August 1998 Forwards Corrected Copy of NOV Re Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Conducted on 980601-04.Notice Did Not Contain Safeguards Info.Administrative Error Resulted in Document Being Marked as Safeguards Info 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) ML20236L1151998-07-0606 July 1998 Forwards Insp Rept 50-010/98-13 on 980319-0630.No Violations Noted.Activities in Area of Facility Mgt & Control,Sf Safety & Radiological Safety Were Examined ML20236F1471998-06-29029 June 1998 Forwards Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18 on 980601-0604.Areas Examined within Security Program Were Identified ML20236G9961998-06-26026 June 1998 Forwards Insp Repts 50-237/98-14 & 50-249/98-14 on 980403- 0527.No Violations Noted.Unavailability of HPCI Sys Continued to Be Problem at Dresden During Insp Period ML20249C3121998-06-23023 June 1998 Inorms That Proposed Revision 66 to QA Topical Rept,CE-1-A, Not Acceptable.Requests That Licensee Refrain from Implementing Changes Until Formally Notified ML20248B9431998-05-27027 May 1998 Discusses 980520 Public Meeting Re Dresden Unit 1 Decommissioning Activities & Dry Cask Storage Project. Meeting Handouts Encl ML20247E3061998-05-0808 May 1998 Confirms Discussion W/B Snell Re Agreement to Have Meeting on 980520 at Plant,Training Bldg to Discuss Unit 1 Status & Plans,Problem Identification & Prevention & Dry Cask Storage Status IR 05000010/19980081998-05-0101 May 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-08, 50-237/98-08 & 50-249/98-08.Corrective Actions Will Be Examined During Future Insps ML20216G6311998-04-0909 April 1998 Summarizes 980312 Meeting Conducted at Region III Ofc in Lisle,Il,To Discuss Util Performance Re Action That Util Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance at Facilities.List of Attendees Encl ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217E8191998-03-26026 March 1998 Discusses Review of Dec 1997,rev 7K to Generating Stations Emergency Plan,Submitted Under Provisions 10CFR50.54(q).NRC Approval Not Required,Changes Do Not Decrease Effectiveness of Plan ML20217D5951998-03-25025 March 1998 Forwards Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08 Conducted Between 980302 & 11.Areas within Security Program Were Examined.Nov & Insp Details Being Withheld ML20248L7911998-03-18018 March 1998 Forwards Insp Rept 50-010/98-02 on 971215-980226 & Nov.Rp Program Exhibited Number of Weaknesses.Program Declined Through Most of 1997 Until Control Informal,Personnel Not Well Informed or Disciplined & Mgt Involvement Lacking ML20216B8321998-03-0606 March 1998 Forwards Decommissioning Insp Plan for Remainder of FY98 for Plant,Unit 1,for Info.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability ML20203H9651998-02-26026 February 1998 Confirms Discussion to Have Meeting on 980312 in Lisle,Il to Discuss Comed Nuclear Operating Division Performance as Relates to Actions Comed Taken in Response to NRC Ltr ,re Safety Performance at Comed Nuclear Facilities ML20203B1651998-02-0909 February 1998 Informs That Effective 980209 R Burrows Has Been Assigned as Project Manager for Plant,Unit 1 ML20202H1701998-02-0909 February 1998 Discusses 980114 Meeting W/Listed Attendees in Lisle,Il to Discuss Commonwealth Edison Co Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54(f) Ltr Concerning Safety Performance at Util Facilities IR 05000010/19970241998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-24, 50-237/97-24 & 50-249/97-24.Actions Will Be Examined During Future Insp ML20202C7821998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-19, 50-237/97-19 & 50-249/97-19.Corrective Actions Will Be Examined During Future Insp ML20198T4491998-01-20020 January 1998 Advises of Planned Insp Effort Resulting from Dresden Plant Performance Review.Details of Insp Plan for Next 6 Months Encl ML20198N7181998-01-15015 January 1998 Discusses Conversation Between I Johnson & J Gavula Re Cancellation of Planned Routine Mgt Meeting on 980122 in Lisle,Il ML20197H8761997-12-23023 December 1997 Forwards Insp Repts 50-010/97-26,50-237/97-26 & 50-249/97-26 on 971029 & 1106.No Violations Noted.Noncited Violation Re Failure to Implement FFD Provisions Contained in Plant Procedure Was Identified ML20197G5641997-12-19019 December 1997 Ask Receipt of Ltr Dated 971002,which Transmitted Changes Identified as Rev 56 to Dresden Nuclear Station Security Plan,Submitted Under Provisions of 10CFR50.54(p).Changes Do Not Decrease Overall Effectiveness of Plan ML20197E9681997-12-19019 December 1997 Forwards Insp Repts 50-010/97-24,50-237/97-24 & 50-249/97-24 on 971016-1122 & Notice of Violation ML20203J6481997-12-16016 December 1997 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Will Be Available in PDR ML20203J8091997-12-15015 December 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-20, 50-237/97-20 & 50-249/97-20 on 971030 1999-08-02
[Table view] |
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JUN 3 01987 M.: Rccad f;le y!" , c 7. . . _ _ _
- - - - - - u A..( 1 it), __
Mr. Steve Simpson y ~ ~ ~-~~
Chief Process Engineer g;"1.~"
Associated Technologies Inc. msg Suite 300, 212 South Tryon St. '~
Charlotte, North Carolina 28281 - ~~
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Deer Mr. Simpson: - i-We have reviewed your " Waste Form Qualification Testing Program for Bitumen NS-1 Decontamination Waste" and have provided comments on various sections of your plan. Specific comments are provided as an attachment to this letter.
Our general comments are provided below. If our comments are addressed satisfactorily and the test results meet the recommendations of this letter and the Technical Position on Waste Form (TP), the test program should be acceptable for demonstrating compliance with the waste form stability requirements of 10 CFR Part 61 for the Dresden Unit I decontamination waste, j We are prepared to review your actual test results following the execution of your waste qualification test program. 4 General Comments l l
To assess the stability of a waste form proposed for shallow land burial, the NRC bas recommended the tests and waste form criteria contained in l
the TP on Waste Form. The recommended tests are accelerated tests which are directly related to burial conditions and designed to measure the degradation of waste forms and container materiais. For the results of these tests to be useful, and in order to obtain a quantitative measure of any degradation that may take place following the testing, suitable indicators of changes in material properties must be chosen. These indicators must be capable, in some cases, of detecting small changes in material properties so that results may be extrapolated to long time frames (300 years). Due to l the lack of information on the behavior of waste solidified in bitumen, the l TP on Waste Form did not contain suitable indicators of changes in material l properties for this viscoelastic waste form. The specific comments contained l in the attachment to this letter recommend testing that NRC believes will give an adequate indication of the degradation of a bitumen waste form following the accelerated tests recommended in the T? on Waste Form.
8709040341 G70630 PDR ADOCK 05000010 P paa
t JUN 3 0 HG7 Steve Simpson 2 l
i These recommendations, like those in the TP on Waste Form are not requirements l and ATI may propose alternative testing or test indicators to NRC for review and approval.
Sincerely, Michael Tokar, Section Leader Engineering Section Technical Branch Division of Low-Level Waste and Decommissioning
Enclosure:
As stated i l
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DATE06/3D/87 :0680/87 :064M)/87 : : : :
OFFICIAL RECORD COPY
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1.0 INTRODUCTION
1 No comment. 1 2.0 SPECIMEN PREPARATION l J
No comment. :
3.0 COMPRESSIVE STRENGTH TESTING NRC feels that testing is required to demonstrate the long-term stability I characteristics of bitumen solidified waste. Of particular importance is the.
ability to determine that there will be no significant infiltration of bitumen {j '
into the pore voids of suitable backfill materials under the range of loads and ;
conditions that are likely to exist at the burial site, to the extent practical. The tests should be conducted on test specimens that are representative of actual wastes. _
Two types of tests are considered to be necessary and would include the ,
, I' establishment of the compressive strength of the solidified waste and a demonstration that the viscosity range of the proposed bitumen mixture would not result in filling of the pore voids of the backfill materials that are i specified in Appendix A of SRP 4.3 (NRC NUREG 1200, " Standard Review Plan for !
the Review of a Licence Application for a Low-Level Radioactive Waste Disposal 'l Facility").
)
Triaxial compression tests are recommended to measure the shear strength of the bituminized waste sample. This type of test is recommended in order to simulate the confining pressures which would exist in a backfilled waste disposal environment. The range of confining pressures to be used should cover the range of confining pressure's that would reasonably be expected for near surface waste disposal. The effect of changes in bitumen /iscosity and the compressive shear strength should be evaluated and an attempt made to i determine what minimum compressive shear strength could be anticipated for the !
range in viscosity to be permitted by the manufacturer. Depending on the results and observed trends of the testing it may be possible to select a ,
conservative " minimum acceptable" viscosity and to reduce or eliminate the need l for compressive strength testing as the material property to detect waste form 1 degradation. Test procedures to measure the extent of infiltration of the l bitumen solidification agent into the potential backfill materials would need to be developed by the manufacturer. It is suggested that agreement with the NRC staff for these test procedures be reached before actual testing is under-taken.
4.0 LEACH TESTING / IMMERSION TESTING Leach testing should include analysis of the leachate for the cumulative fractional release of any chelating agents contained in the NS-1 waste form. ;'
\
l m
/
i
, , . . . l I
2 This testing is necessary to assure that released chelates do not complex and mobilize radionuclides from waste placed in other areas of the trench. ,,
Following the immersion test, the " minimum acceptable viscosity" should be determined (from the recommended testing in section 3.0), this viscosity should not have changed more than 20 percent of the pre-test value. ,
5.0 RADIATION TESTING il i'
Will effects, such as swelling, due to gas generation be noticed when using an ll aluminum taped sample? How will ATI determine if there is significant i degradation from gas generation?
-t, Following this test, if the" minimum acceptable" viscosity is used (as ]'
determined from the recommended testing in section 3.0), then the viscosity [j should not have changed more than 20 percent of the pre-test value, t 1
6.0 BI0 DEGRADATION TESTING e
At the conclusion of the ASTM G21 and G22 test, if the samples are determined ' !
tohaveundergonesignificantbiodegradation,thenadditionaltesting(suchas the Barther Pramer test) should be instituted to determine the rate of biodegradation of the samples and whether this rate would cause stability ,? '
l problems (in a 300 year time frame). Following this test, if the minimum -
acceptable viscosity is used (as determined from the recommended testing in ;
section 3.0), then the viscosity should not have changed more than 20 percent !
of the pre-test value.
~
7.0 THERMAL DEGRADATION TESTING We do not recommend using an alcohol bath during thermal cyci'ng due to the damage it may cause to the form. If a temperature of 40 C can not be reached without the aid of the alcohol oath, we will accept data at a temperature of 30"C if you increase the number of thermal cycles from 30 to 50. Following this testing specimens should be checked for free standing liquid as well as indications of physical deformation. If the minimum acceptable viscosity is
, used (as determined from the recommended testing in section 3.0) to quantify
( the amount of degradation which has occurred, then the viscosity should not have changed more than 20 percent of the pre-test value..
8.0 FREE STANDING LIQUIDS /HOM0GENEITY ATI should note the physical appearance of the extracted (or cored specimens).
In addition, a determination that the minimum acceptable viscosity has been maintained in the full size specimen will be sufficient to assure homogeneity.
i 1
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