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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail L-99-021, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-022, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E0451990-11-13013 November 1990 Discusses 901106 Meeting Re Alternative Tube Plugging Criteria for Facility Steam Generators ML20062D6911990-11-0909 November 1990 Forwards SER Re Response to Generic Ltr 88-11 Concerning NRC Position on Radiation Embrittlement of Reactor Vessel. Compliance w/10CFR50,Appendix G,For Min Upper Shelf Energy Could Not Be Verified.Operation for 16 EFPY Acceptable ML20058F7931990-11-0606 November 1990 Forwards Summary of NRC Understanding of Current Status of Unimplemented Generic Safety Issues for Plant,Per Util 900627 Response to Generic Ltr 90-04 ML20058B4021990-10-19019 October 1990 Forwards Summary of 900913 Mgt Meeting Re Emergency Preparedness Program & Onsite Technical Support Ctr ML20058B1391990-10-16016 October 1990 Forwards Insp Repts 50-348/90-28 & 50-364/90-28 on 900911-1012.No Violations or Deviations Noted ML20062B7031990-10-12012 October 1990 Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20058B2581990-10-12012 October 1990 Ack Receipt of 900807 & 0904 Ltrs Transmitting Objectives & Scenario Package for Exercise Scheduled on 901024 ML20062C6601990-10-0909 October 1990 Ack Receipt of 900913 Response to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19 ML20059N6721990-10-0909 October 1990 Responds to Util 900702 Request for Authorization to Use ASME Boiler & Pressure Vessel Code Case N-395.Request Acceptable IR 05000348/19900181990-10-0909 October 1990 Ack Receipt of 900926 Response Re Violations Noted in Insp Repts 50-348/90-18 & 50-364/90-18 ML20059N3481990-09-24024 September 1990 Forwards Insp Repts 50-348/90-24 & 50-364/90-24 on 900827-31.No Violations or Deviations Noted ML20059K1311990-08-28028 August 1990 Confirms Mgt Meeting on 900913 to Discuss Timeliness of Activation of Emergency Response Facilities ML20059H0921990-08-23023 August 1990 Forwards Insp Repts 50-348/90-20 & 50-364/90-20 on 900711-0810.No Violations or Deviations Noted ML20059B3421990-08-23023 August 1990 Advises That Util 900131 Response to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations,Satisfactory ML20056B3721990-08-21021 August 1990 Forwards Order Imposing Civil Monetary Penalty in Amount of $450,000 Re Violations,Per 870914-18,1102-06 & 16-21 Insps. Violations Include Failure to Demonstrate Splice Qualification & Failure to Maintain Environ Qualification ML20058M9441990-08-0303 August 1990 Forwards Insp Repts 50-348/90-19 & 50-364/90-19 on 900711-13 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21) ML20058P8661990-07-31031 July 1990 Forwards Insp Repts 50-348/90-21 & 50-364/90-21 on 900709-13.No Violations or Deviations Noted ML20055H4251990-07-13013 July 1990 Forwards Insp Repts 50-348/90-16 & 50-364/90-16 on 900611-0710.Violations Noted,But Not Cited ML20055H6501990-07-13013 July 1990 Forwards Insp Repts 50-348/90-17 & 50-364/90-17 on 900618-22.No Violations or Deviations Noted ML20044B0881990-07-0303 July 1990 Forwards Insp Repts 50-348/90-13 & 50-364/90-13 on 900511-0610.No Violations or Deviations Noted ML20044B1231990-07-0202 July 1990 Forwards Insp Repts 50-348/90-14 & 50-364/90-14 on 900611-15.No Violations or Deviations Identified ML20059M8061990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl IR 05000348/19900021990-06-0707 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/90-02 & 50-364/90-02 ML20043G8021990-06-0606 June 1990 Forwards Insp Repts 50-348/90-03 & 50-364/90-03 on 900423-27 & 0514.No Violations or Deviations Noted ML20043D8151990-05-29029 May 1990 Forwards Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510 & Notice of Violation NUREG-0845, Forwards NUREG-0845 & NRC Info Notice 86-018, NRC On-Scene Response During Major Emergency Describing NRC Role in Emergency & to Support NRC Participation in 1990 Emergency Preparedness Exercise to Be Conducted on 901024.W/o Encls1990-05-15015 May 1990 Forwards NUREG-0845 & NRC Info Notice 86-018, NRC On-Scene Response During Major Emergency Describing NRC Role in Emergency & to Support NRC Participation in 1990 Emergency Preparedness Exercise to Be Conducted on 901024.W/o Encls ML20043A9471990-05-11011 May 1990 Forwards Insp Repts 50-348/90-09 & 50-364/90-09 on 900416-20.No Violations or Deviations Noted ML20042G8731990-05-0404 May 1990 Forwards Requalification Retake Exam Rept 50-348/OL-90-01 for Units 1 & 2 Administered During Wk of 900129.Comments Made by Util Training Personnel Re Accuracy of Answers to Questions in Written Exam Also Encl ML20034C6761990-05-0101 May 1990 Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 2.2.1, Equipment Classification Program for All Safety-Related Components ML20034C3521990-04-24024 April 1990 Provides Info Re Interpretation of Bioassay Measurements to Assess Intakes of Radioactive Matl.Nrc Memo Updating Position Taken in Info Notice 82-18, Interpretation of Bioassay Measurements;Assessment of Intakes Encl ML20034C3791990-04-23023 April 1990 Forwards Insp Repts 50-348/90-10 & 50-364/90-10 on 900311-0410.No Violations or Deviations Noted ML20012F3011990-03-29029 March 1990 Forwards Insp Repts 50-348/90-08 & 50-364/90-08 on 900226-0302 & Notice of Violation IR 05000348/19900111990-03-27027 March 1990 Forwards Insp Repts 50-348/90-11 & 50-364/90-11 on 900319-21.No Violations or Deviations Identified.Repts Withheld (Ref 10CFR2.790 & 73.21) ML20033F7701990-03-23023 March 1990 Requests Util Provide Matls Including,Existing Learning Objectives,Job Performance Measures,Lesson Plans,Complete Procedure Index,Administrative & Integrated Plant Procedures for Operator Licensing Exam Scheduled for Wk of 900625 ML20042D7511990-03-23023 March 1990 Forwards Insp Repts 50-348/90-07 & 50-364/90-07 on 900211-0310.Violations Noted But Not Cited ML20033F7371990-03-19019 March 1990 Provides NRC Understanding of Current Status of Unimplemented USIs at Plant,Per Util 891129 Response to Generic Ltr 89-21 ML20033F3381990-03-0909 March 1990 Forwards Insp Repts 50-348/90-06 & 50-364/90-06 on 900220- 23.No Violations or Deviations Noted ML20012C3421990-03-0202 March 1990 Forwards Insp Repts 50-348/90-01 & 50-364/90-01 on 900111-0210.No Violations or Deviations Noted ML20055C3961990-02-23023 February 1990 Forwards Insp Repts 50-348/90-04 & 50-364/90-04 on 900129-0202.No Violations or Deviations Noted ML20011F2911990-02-13013 February 1990 Forwards Page 4 to Insp Repts 50-348/89-31 & 50-364/89-31 on 891111-1210.Page Inadvertently Omitted from Original Rept ML20006E6021990-02-0202 February 1990 Forwards Exam Rept 50-348/OL-89-02 on 891023-26.Exams,answer Keys & Facility Comments Also Encl ML20011E2661990-02-0101 February 1990 Forwards Insp Repts 50-348/89-32 & 50-364/89-32 on 891212-15,20 & 29.No Violations or Deviations Noted.Four Exercise Weaknesses in Need of Corrective Action Identified. Corrective Actions Discussed During 891229 Telcon ML20011E3551990-01-30030 January 1990 Forwards Insp Repts 50-348/89-34 & 50-364/89-34 on 891211-900110.Violations Noted But Not Cited ML20011E1931990-01-25025 January 1990 Advises That 891018 Rev 17 to Emergency Plan Consistent W/ 10CFR50.54(q) & Acceptable ML20005H1331990-01-16016 January 1990 Advises That Individual Plant Exam Approach,Methodology & Schedule Acceptable,Per 891027 Response to Generic Ltr 88-20 ML20006A0441990-01-16016 January 1990 Informs of Temporary Rotational Assignment of Eg Adensam to Regional Ofc.Author Will Be Acting as Project Director from 900108-0220 ML20005G1571990-01-10010 January 1990 Ack Receipt of Util Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 ML20005G1871990-01-0404 January 1990 Forwards Insp Repts 50-348/89-31 & 50-364/89-31 on 891111-1210.Violations Noted But Not Cited ML20005E8621989-12-28028 December 1989 Forwards Insp Repts 50-348/89-33 & 50-364/89-33 on 891206.No Violations or Deviations Noted ML20042D4731989-12-20020 December 1989 Confirms Telcon W/R Wiggins & R Mcwhorter Re Evaluations of Requalification Exam Failures for Licensed Personnel Scheduled for Wk of 900129.Exam Schedule & Process Will Be Discussed W/Appropriate Facility Personnel & Operators 1990-09-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20206R4741999-05-13013 May 1999 Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC ML20206M2321999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created ML20206G7341999-05-0404 May 1999 Forwards Safety Evaluation Re Completion of GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206G2411999-04-30030 April 1999 Forwards Revised RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Farley.Requests to Be Notified of Rev to Original Target Date of 990521 ML20206R2031999-04-29029 April 1999 Forwards Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted ML20205T1931999-04-0909 April 1999 Informs That on 990316,J Deavers & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Farley NPP for Y2K.Initial Exam Dates Are Wks of 000508 & 22 for Approx 12 Candidates.Chief Examiner Will Be C Ernstes ML20205Q1541999-04-0606 April 1999 Forwards Insp Repts 50-348/99-09 & 50-364/99-09 on 990308-10.One non-cited Violation Identified ML20205M2831999-04-0202 April 1999 Forwards Errata Ltr for Farley Nuclear Power Plant FEMA Exercise Rept.Page 19 of Original Rept Should Be Replaced with Encl Corrected Page 19 ML20205A2611999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Farley Plant Performance Review on 980202.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20196K4881999-03-19019 March 1999 Forwards Insp Repts 50-348/99-01 & 50-364/99-01 on 990110- 0220.One Violation of NRC Requirements Occurred.Violation Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20204C9561999-03-17017 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Plant,Units 1 & 2.Response Requested by 990521 ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207M2181999-03-11011 March 1999 Advises That Info Contained in 990125 Application CAW-99-1318 & Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20207M1991999-03-0808 March 1999 Partially Withheld Info Re Meeting Held on 990129 at Region II Ofc in Atlanta,Ga to Discuss Physical Protection Measure for Svc Water Intake Structure Located at Facility (Ref 10CFR73.21).List of Attendees Encl ML20206U1831999-02-0909 February 1999 Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed ML20203G5541999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 940407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203G3921999-02-0202 February 1999 Forwards Insp Repts 50-348/98-08 & 50-364/98-08 on 981129- 990109 ML20199L4451999-01-25025 January 1999 Forwards for Review & Comment Revised Draft Info Notice Re Inservice Testing of A-4 Multimatic Deluge Valve for Farley NPP Units 1 & 2.Informs That Comments Submitted on 981120 Were Reviewed & Incorporated Where Appropriate ML20199K7351999-01-21021 January 1999 Responds to 981123 Request by Providing Copy of Latest Draft of Info Notice Being Prepared Which Discusses Failure of Several Preaction Sprinker Sys Deluge Valves.Requests Submittal of Comments by 981120 ML20199K7231999-01-20020 January 1999 Confirms 990119 Telcon Re Informational Meeting Scheduled for 990129 to Be Held in Atlanta,Ga to Discuss Security Related Issues at Plant.Meeting Will Be Closed to Public,Due to Sensitive Nature of Issues ML20199D8541999-01-12012 January 1999 Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20199C9361999-01-0808 January 1999 Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted ML20198S2741999-01-0606 January 1999 Informs That Staff Reviewed SG 90-day Rept, Farley Unit 2 1998 Voltage Based Repair Criteria 90 Day Rept, & Found Assessment to Be Acceptable.Staff Review Encl 1999-09-09
[Table view] |
Inspection Report - Farley - 1987037 |
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AU6191888
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Alabama Power Company (#ITN: Mr. W. G. Hairston, III Senior Vice President-Nuclear Operations P. O. Box 2641 Birmingham, AL 35291-0400 Gentlemen:
'
SUBJECT: CONFIRMATORY MEASUREMENT RESULTS, SUPPLEMENT TO INSPECTION REPORT NOS. 50-348/87-37 AND 50-364/87-37 During the inspection uf December 16-18, 1987, the inspector requested your Farley facility to perfonn smear surveys of selected areas within the radiation controlled area (RCA) and analyze them for alpha, beta, and gama radioactivity.
These surveys were taken in the Unit 1 Spent Fuel Pool Area,
Waste Sorting Area. Unit 1 Primary Sample Room, and the Radwaste Solidification
,
Area, t
The inspector also informed licensee management representatives that these smear samples (approximately 213) would be analyzed for alpha, beta, gama radioactivity by the NRC Region li office to compare the results achieved by
the licensee. The results of this comparison are presented in the enclosure.
Although differences were noted for gross beta results, these variations were f
"
attributed to differences in counting methodologies and instrument
!
calibrations.
The NRC laboratory utilized a Gama Products Alpha-Beta l
Proportional Counter which was calibrated for gross beta efficiency using a l
Cesium-137 (Cs-137) standard.
The operating voltage was selected to maximize i
efficiency and to minimize the beta to alpha crosstalk.
(Beta to alpha
'
'
crosstalk is defined as beta particles that are counted in the alpha region.)
!
i Smears which indicated possible alpha activity were additionally counted on a l
SAC-4, a alpha scintillation counter.
The SAC-4 detected only alpha particles I
and therefore eliminated the interferences of crosstalk.
Smears that were
!
considered to contain too high a level of radioactivity were counted for gross t
alpha and beta activity using a RM-14 with a HP-210 detector so as to avoid l
.
possible contamination of the alpha-beta counter.
The licensee's NMC-4 I
alpha-beta counter was calibrated using Tc-99 which would result in a lower counting efficiency than that determined using Cs-137.
Final activity (disintegrations / minute (dpm)) calculated using the lower efficiency would
'
result in higher reported dpm.
a Additional differences between NRC and licensee results were attributed to isotopic decay.
A time interval of approximately two weeks elapsed between licensee and NRC counting, and gross activity determinations could not be decay l
corrected.
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Alabama Power Company
The NRC's lower limits of detection (LLDs) were reported as less than 2 dpm/ smear for alpha activity and less than 4 dpm/ smear for beta activity.
The licensee's "less than" reselts of less than 20 dpm/ smear for gross alpha and less than 200 dpm/ smear for gross beta were based on action limits for controlling surface radioactivity within the RCA.
If you have any questions regarding these results, please contact us.
Sincerely, MI Ginc tl us t <;ned
'
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'
T 'O cCCcr Douglas M. Collins, Chief Emergency Preparedness and Radiological Protection Branch Divuion of Radiation Safety ano Safeguards Enclosure:
Gross Alpha / Beta Analyses cc w/ enc 1:
GI M. Guthrie, Executive Vice President LF. H. Morey, General Manager -
Nuclear Plant p'. D. Woodard, Vice President -
Nuclear Generation
): W. McGowan, Manager-Safety Audit and Engineering Review (Sr Fulmer, Supervisor-Safety Audit and Engineering Review bec w/ encl:
(RRC hesident Inspector DRS Technical Assistant E. Reeves Project Manager, NRR State of Alabama Document Control Desk RII 91 i RII Cs'd,)
c/
MR1M e+D s
TColTins CHo y /WJKahle HDance
%/88
}g /S!f
$//7/88 Mg/88 s
.
~ -
LNct_03uRz Cross Alpha / Beta Analyses of" Smears
-
.
Cros_s Alpha, dpefjmes_r Gro_ss_lieja dpm/ smea.r lamp _1_e l0 f4RQ lscenseg NRC QCensee SN 1182 ( Rad Wa ste Bu i Id ing Smea r #1 )
<?
< 20
<4
< ?f M; 201383 (Rad Waste Building Smear #2)
<2
< 20 71 3
< 200 SN 1384 (Rad waste BuiIding Smear #3)
<2
< 70
<4
< 200 SN 13P5 (Rad Waste Building Smear #4)
<2
< 20
< 8s
< 200 30 1386 ( Ra d Wa s t e Bas i l d i r.g Smea r #5 )
<2
< 20
<4
< PfM3 SN 1387 (Rad Waste Ruilding Smear #6)
<2
< 20
<4
< 200 SN 1388 (Rad Waste Building Smear #1)
<2
< 20
<4
< ?tHP SN 1389 ( Rad Wa ste Bu i Id i ng Sw.ca r #8 )
<2
< 20
<4
< 700 SN 1390 (Rad Waste Building Smear #9)
<?
< 20
<4
< ?fdl SN 1391 (Rad Waste Basilding Smear #11)
<?
< 70
< 8s
< 700 SN 1392 ( Rad Wa s te Bu i ld i ng Smea r # 12 )
<2
< 70
<4
< 200 SN 1393 (Rad Waste Building Smear #13)
<2
< 20
<4
< 200 SN 1394 (Rad Waste Building Swear #18s)
<2
< 20
<88
< 200 EN 1395 (Rad Waste (SuiIding Smear #15)
<?
< 20 5t 3
< ?(H)
SN 13"6 ( Rad Wa s te Bu i I d ing Smea r # 16 )
<?
< 20
< 4
< 200 SN 1397 (Rad Waste tsuildiesg Smea r #11)
<2
< 20
< 4
< Pim SN 1398 (Rad Waste Building Smear #18)
<2
< 20
< 4
< 200 SN 1399 (Rad Waste Building Smear #19)
<2
< 20
< is
< 200 SN 1400 (Rad Waste Building Smear #20)
<2
< 20
< 4
< 200 SN 1401 ( Rad Wa s te 15u i l d i ng Smea r #21 )
<?
< 20
<4
< 700 SN 1402 (Hati *a*se Bas i I d i ng Smea r #23 )
<2
< PO
< 4
< 700 SN 1403 (Rad Waste Busi4 69 Smea r f24 )
<2
< 20 523
< 200
.
301404 (Rad waste Building Smear ;25)
<2
< 20
<4
< 200 SN 1405 (Rad Waste Build.ng Smear #26)
<2
< 20
<4
< 200 SN 1406 ( Rad Wa s te Basi l d i ng Smea r #21 )
<?
< 20
<4
< ?fM)
SN 140 T ( Rad Wa s te Bu i l d i ng Smea r #28 )
<2
< 20
<4
< 200 18 08 ( Rad Wa ste Bui lding Smea r #29)
21?
< 20 12 t 4
< 200 SN
SN 1409 ( Rad Wa s te Bu i l d i ng Smea r # 30 )
<2
< 20
<4
< 200 SN 1410 ( Rad Wa s te Bui ld ing Smea r #31 )
222
< 20
<4
< 20f)
SM 1411 ( Rad Wa ste f5ui l d i ng Smea r #32 )
<2
< 20
<84
< 2fM)
SO 1412 (Rad Waste Building Smear #33)
<2
< 20 11 14
< 700 SN 1413 ( Rad Wa ste Bu i ld i ng Smea r #34 )
<2
< 20
<4
< 2fx)
SN 11:14 ( Rad Wa ste Bu i ld ing Smea r # 35 )
<2
< 20
< 84
< 700 SN 1415 ( Rad Wa s te flu i Id i ng Smea r # 36 )
<2
< 20
<4
< 200 SN 1416 ( Rad Wa ste Cu i ld ing Smea r # 3 7 )
<?
< 20
<4
< 200 1817 (Rad Waste fluilding Smeer #38)
<2
< 20
<4
< 700 SN
SN 1418 ( Rad Waste tiui Eding Smea r #39)
312
< 70 2615
< 200 SN 1419 (Rad Waste Building Smear #40)
<2
< 20 s
<4
< 7tN)
SN 1420 ( Rad Wa ste ISui ld i ng Smea r #ta l )
<2
< 20
<4
< PfM)
50 1421 (Rad Waste Building Smear #42)
<2
< 20
<4
< 200 E3 1422 ( Ra d Wa ste Bu i l d i ng Smea r # 883 )
<2
< 20
<4
< ?(#)
SN 1423 (Rad Waste Building Smear #44)
<2
< 20
< Is
< 200 SN lis24 (Rad waste BuiIding Smear #t:5)
<2
< 20
< 8:
< Puf)
EN 1425 (Rad Waste Bu t Iding Smear #46)
<2
< 20
< 4
< 200 50 1426 ( Rad Wa s te flu i I d i ng Smea r fis 7 )
<2
< 20 7t 3
< 200 SO 1427 (Rad Waste Building Smear #fs8)
<2
< 20
<4
< 200 SN tis 28 (Rad Waste Building Smear #49)
<2
< 20
<8
< Pfxp SN 1429 (Rad Waste Building Smear #50)
<2
< 70
< 4
< 200 SO 18:30 ( Rad Wa ste Bui ld i ng Smea r #51 )
<2
< 20
< 4
< 200 18 31 (Rad Wa ste Bu s id ing Smea r #52)
<2
< 20
< 4
< 200 SN
SN 1432 (Rad Waste BuiIding Smear #53)
<2
< 20
< 200
-
.
- -
.
-
- -
-
e
.
s
[nclosure (Cont'd )
m pef _ smear
d Gross Alpha, dpm/3mear Gross Beta
$ ample 80 NR9 Licensgg NJG Licensee
,
SN 1433 (Rad Waste Building Smear #54)
<2
< 20
$f3
< 200 SN 18:34 (Rad Waste Building Smear #55)
<2
< 20
<4
< 700 SN 1435 (Rad Waste Building Smear #56)
<2
< 20
<4
< ?OO SN Ita36 (Rad Waste Building Smear #57)
<2
< 20
<4
< 200 SN If 3T (Rad Wiste P911 ding Smear #$8)
<2
< 20
<4
< 200 SN 1438 (Rad Waste B silding Smear #$9)
<2
< 20
<4
< 200
C 2
< 20
<4
< 200 SN 1439 ( Rad Wa ste BL i Id ing Smea r #60)
SN 1440 ( So l i d i f i ca t i on Bu i l d i rv, Smea r # 1 )
<2
< 20
<4
< 200 SN 1481 (Solidification Building Smear #?)
<2
< 20
<4
< 2fM)
SN 1442 (Sulidification Building Smear #3)
<2
< 20
<4
< 200
18 4 3 ( So l i d i f i ca t i on fio s i d i ng Smea r #4 )
<2
< 70
<4
< 200 SN SN 1444 (Solidification Building Smear #5)
<2
< 20 61 3
< POn
SN 14885 ( So l i d i f i ca t i on Bu i I d i ng Smea r g6 )
<?
< 20
<4
< Poe, 14f 6 (Solidification Building Smear #1)
<2
< 20
<4
< POO SN
SN 144T (Solidification Building Smear #8)
(1) < 2
< 20 1080 1 31 7940 SN 1448 ( So l i d i f ica t i on Bu i l d i ng Smea r #9 )
<2
< 20 13 1 4
< 700
.
S3 1449 (Solidi fication Building Smea r #10)
<2
< 20 42 3
< 200 SN 1450 ( So l i d i f i ca t ion Bu i l d i ng Smea r # 11 )
<2
< 20 to 2 4
< 200 SN 1451 (Solidification tsuilding Smear #12)
<2
< 20
$t 3
< 200 SQ 1457 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 13 )
222
< 20 48 i 5
< 2170 SN 1453 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 184 )
<2
< 20
<4
< 200
< 2
< 20
<4
< 2fsts
-
SN 1845f4 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 15 )
18 55 ( So l idi ficat ion f%si lding Smea r #16)
<2
< 70
<4
< 700 SN
< 2
< 20
<4
< 2tMs SN 11s56 (Solidi ficsLion Building Smear #11)
< ?
< 20
<8
< 200 18 5T (Solidification Building Smear #18)
SN SN 1458 (Solidification Buildjng Smear #19)
<2
< 20
<4
< 700
Sfl 1459 ( So l i d i f i ca t i on Bu i l d i ng Smea r #70 )
<2
< 20
<4
< ?OO
< 2
< 20
<4
< ?oO Sil 1460 (Solidification Building Smear #71)
< 2
< 20
<4
< 200 SN lis61 ( So l i d i f i ca t i on Bu i l d i ng Smea r #72 )
Sf4 1462 ( So l i d i f ica t i on Bu i l d i ng Smea r #23 )
<2
< 20
<4
< 200
< 2
< 70
<4
< 2 fin 18 6 3 (Sol idi fica tion Building Smea r #24 )
SN
< 2
< 20
< 84
< 200
SN 1464 (Solidification Building Smear #25)
SN 1465 (Solidification BuiIding Smear #76)
<2
< 20
< fa
< Pf WJ
< 2
< 20
< 88
< 700 SN 1466 ( So l i d i f i ca t i on Bu i l d i ng Smea r #77 )
< 2
< 20
< 84
< 2(W)
SN 1467 (Solidification building Smear #28)
< 2
< 20
< 4
< PfM)
SN 1468 ( So l i d i f i ca t i on Bu i 9 d i ng Smea r #29 )
< 2
< 20
< 4
< 200 SN 1469 (Solidification Building Smear #30)
< 2
< 20
< 84
< ?s W)
SN 184 70 ( So l i d i f i ca t i on Bu i l d i ng Smea r #31 )
< 2
< 20
< 4
< 200 SN 1471 (Solidification Building Smear #32)
.
< 2
< 20
< 4
< ?OO SN 1412 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 33 )
< 2
< 20
< 4
< 200 SN 18s73 (Solidification Building Smear #34)
< 2
< 20
< as
< 200 18 74 (Solidification Building Smear #35)
SN
< 2
< 20
< 4
< 200 SN 1475 (Solidification Building Smear #36)
< 2
< 20
< 8
< 200 SN 18s 16 ( So l id i f i ca t i on Bu i l d i ng Smea r # 37 )
< 2
< 20
< 4
< 2fN)
SN 1477 (Solidification Building Smear #38)
< 2
< 20
< 4
< 200 SN 1478 (Solidification Building Smear #39)
< 2
< 20
< 4
< 200 SN 1479 ( So l i d i f i ca t i on Bu i I d i ng Smea r #40 )
< 2
< 20
< 84
< 200
$3 1480 (Solidification BuiIding Smea r #41)
< 2
< 20
< 4
< 200 SN 1481 (Solidification Building Smear #42)
< 2
< 70
< 4
< 200 SN 1482 ( So l i d i f i ca t ion Bu i l d i ng Smea r #43 )
SN 1483 (Solidification Building Smear #1:4)
< 2
< 20
<4
< 200 SN 18484 (Solidification Building Smear #t:5)
< 2
< 20
<4
< 200
< 2
< 20
< 8s
< 200 SN 1485 ( So l i d i f i ca t ion Bu i l d i ng Smea r #f 6 )
< 2
< 20
< is
< 200 SN 1486 ( So l i d i f i ca t i on Bu i l d i ng Smea r #ts T )
-
~ ~ ~^
- -
--
-,,,.,,,, - _,
-..._.
-
-....
-.-.
- - _ __ -
.
-. - -
. - -
- _ - _ -
._
.
_
f
.
-
.
Enclosure (Cont'd)
- Gross Alpha, dpefjLuca r Cross Bejadpef_smea r
} ample ID N_fiQ Qqensee Niig Qcensee
,
S:s 18 87 ( So l i d i f i ca t i on Bu i l d i tM Smea r #48 )
<2
< 20
<as
< 200 SN 1488 (Solidification Duilding Smear #49)
<2
< 20
<4
< 200
'
SN 1489 ( So l id i f i ca t i on stu i l d i ng Smea r #50 )
<2
< 20
<4
< 200 SN 1490 ( So l i d i f i ca t i on Bu i l d i ng Smea r #51 )
<2
< 20
< is
< 200 SN 1491 (Solidification Building Smear #>2)
<2
< 20
<4
< 200
,
SN 1492 (Solidification Building Smear #53)
<2
< 20
<4
< 200 5:3 1493 (Solidification Building Smear g54)
<2
< 20
<4
< 200 SN 18s94 ( So l id i f ica t i on Bo i E d i ng Smea r #55 )
<2
< 20
< As
< 200 SN 1495 (Solidification BoiIding Smear #S6)
<2
< 20
< is
< 200 5:3 1496 ( Sol id i f ica t ion Bu i ld i ng Smea r g5 7 )
<2
< 20
<4
< 200 SN 1497 ( So l i d i f i ca t i on Bu i l d i ng Smea r g58 )
<2
< 2e
<4
< ?OO SN 1498 ( So l i d i f i ca t i on Bu i l d i ng Smea r #$9 ]
<2
< 20
<4
< 200 SN 1499 ( So l i d i f i ca t i on Bui l d i ng Smea r g60 )
<2
< 20
<4
< 200 i
SN ISff ( So l i d i f i ca t i on Bu i I d i ng Smea r #61 )
<2
< 20
<4
< 200 SN 150; (Solidification Building Smear #62)
<2
< 20
<4
< 203 SN 1502 ( So l i d i f i ca t i on Bu i l d i ng Smea r #63 )
<2
< 20
<4
< 2tMJ SN 1503 (Solidif ication Building Smear #64)
<2
< 20
< 1;
< 200 5:31504 (Solidification Building Smear g65)
<2
< 20
< is
< ?oo SN 1505 ( So l i d i f i c a t i on Bu i l d i ng Smea r g66 )
<2
< 20
<4
< 200 l
SN 1506 ( So l i d i f i ca t i on Sc i l d i ng Smea r # 67 )
<2
< 20
<4
< 200 l
SN 1507 1 Solidification Building Smear #68)
<?
< 20
<4
< psM
!
SN 1908 ( So l i d i f i ca t i on Bu i l d i ng Smea r g69 )
<2
< 20
<as
< 200 I
SN 1$09 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 70 )
<2
< 20
<4
< 200 l
S:t 1510 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 71 )
<2
< 20
<4
< 200 (
SQ 1$11 (Solidification DuiIding Smear #12)
<2
< 20
<4
< 200 l
SN 1512 (Solidification Building Smear #73)
<2
< 20
<4
< 200 l
5:3 1513 ( So l id i f ica t ion Bu i ldi ng Smea r # 74 )
<2
< 20 61 3
< 200 SN 1514 ( So l i d i f i ca t i c n Bu i l d i ng Smea r g 75 )
<2
< 20
<4
< 200 SN 1515 (Solidification Building Smear 176)
<2
< 20
<4
< 200 S:t 1516 ( So l i d i f i ca t i on Gu i l d i ng Smea r # 77 )
<2
< 20
<4
< 200 SN 1$17 (Solidification Building Smear 178)
<2
< 20
<as
< 200 SN 1518 ( So l i d i f i ca t i on Bu i l d i ng Smea r # 79 )
<2
< 20
<4
< 200 5:3 1$19 ( Solidi fication Building Smear #80)
<2
< 20
<4
< 200 SN 1520 ( So l i d i f ica t i on Bu i l d i ng Smea r #81 )
<2
< 20
< 8e
< 200 SN 1521 ( So l i d i f i ca t i on Bu i l d i ng Smea r #82 )
<?
< 20
<4
< 200 SN 1522 ( So l i d i f i ca t i on Bu i l d i ng Smea r #83 )
<2
< 20
< 8e
< 200 SN 1523 (Solidification Buildireg Smear #8fs)
<2
< 20
<4
< 200 SN 1524 (Solidification Building Smear #85)
<2
< 20 10 i is
< 200 SN 1525 (Solidification Building Smear #86)
<2
< 20
<4
< 200 SN 1526 ( So l i d i f i ca t i on Bu i l d i ng Smea r E8 T )
<2
< 20
<4
< 200 SN 1527 ( So l i d i f i ca t ion Bu i l d i seg Smea r #88 )
<2
< 20
<4
< 200 S:31528 (Solidification Building Smear #89)
<2
< 20
<as
< 200 SN 1529 ( So l i d i f i ca t i on Bu i l d i ng Smea r #90 )
<2
< 20
<4
< 200 SN 1530 (Solidification Building Smear #91)
<2
< 20
<4
< 200 S:t 1531 (Waste Sorting Area Smear #1)
<2
< 20 523
< ?OO SN 1S32 (Waste sorting Area Smear #2)
<2
< 20 6619
< 200 SN 1533 l Waste Sorting Area Smear #3)
<2
< 20 62 3
< 200 SN 1$3fs (Wsiste Sorting Area Smear #4)
<2
< 20
<2
< 200 SN 1535 P4Jste sorting Area Smear #5)
<2
< 20 10 i as
< 200 SN 1536 (Waste sorting Area Smear #6)
<2
< 20 3316
< 200 SN 1$37 (Waste Sorting Area Smear #7)
<2
< 20 91 19
< 200 SN 1538 (Waste Sorting Area Smear #8)
<2
< 20 1 044 1 10
< 200 SN 1539 (Waste sorting Area Smear #9)
<2
< 20 60 1 8
< 200 SQ 1540 (Waste Sorting Area Smear #10)
<2
< 20 68 i 8
< 200 I
t I
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e
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Enclosure ( Con t' d )
Cross Alpha dps/ smea r Cross _Beja pample ID NJQ Mqensee NteG License _e
,
SN 1541 (Waste Sorting Area Smear #11)
(1) < 2
< 20 1360 t 35 2609
< 2
< 20 68 2 8
< 200 SN 1542 (Waste Sorting Area Smear #12)
8317
< 200
< 2
< 20
)
SN 1543 (Waste Sorting Area Smear #13)
l SN 1544 (Waste Sorting Area smear #14)
<2
< 20 4617
< 200 SU 15845 (Waste Sorting Area Smear #15)
31 3
< 20 8ts t 9
< 2fMI l
SN 1546 (Spent f uel Fool Smea r # 3 )
< 2
< 20 81 3
< 200 SN 1547 (Spent inel Pool Smea r #2)
< 2
< 20
<4
< 200
< 2
< 20 81 3
< 200 SN 1548 (Spont fuel Pool Smea r #3 )
SN 1549 (5 pent Fuc t Pool Smea r #1s )
< 2
< 20
<4
< 2fM)
SN 1*>50 ( Spent fuel Pool Smear #*>)
< 2
< 20
$i3
< 200 SN 1551 (Spent fuel Pool Smea r #6 )
< 2
< 20 17 1 as
< 2fMI SN 1552 (Spent f uel Pool Smear #1)
(1) < 2
< 20 28s 1 5
< 200 l
SN 1553 ( Sper.t fuel Pool Smea r #8 )
< 2
< 20 31 3
< 200 St. 1*>$4 (Spent fuel Pool Smea r #9 )
(1) 12 1 4
< 20 1410 2 36 2090 SN 1555 (Spent fuel Pool Smea r #10)
< 2
< 20 62 3
< 200 SN 1556 (Spent fuel Poo l Smea r #11 )
< 2
< 20 25 t 5
< 200 SN 1%7 (Spent f uel Pool Seea r #12 )
< 2
< 20 3216
< 2f>0 SN 1558 ( Spent fuel Pool Smea r #13 )
2f2
< 20 11 t4
< 200 SN 1%9 (Spent fuel Pool Smea r Elia )
< 2
< 20
< 8,
< 20f)
SN 1560 (Spent fuel Pool Smea r #15 )
is 1 3
< 20 54 t 7
< 2fMI SN 1561 (Spent fuel Pool Smear 1/16)
3*2
< ?O 25 t 5
< 200
SN 1%? (Spent Tuct Pool Smea r 417 )
< 2
< 20 42 f 6
< 2fM)
SN 1%3 ( Spent fuel Pool Smea r #18)
212
< 20 52 t 7
< 2fMI
< 2
< 20 81 3
< 200 SN 15634 (Spent Iuel rool Smea r #19 )
SN 1565 ( Spent fuel Pool Smear #20)
< 2
< 20 56 f 7
< 200 8016
< 2f10 SN 1566 (Spent fuel Fool Smea t-g21 )
< 2
< 20
SN 1%T (Spent fuel Pool Smes.r #22)
< 2
< 20 3929
< 200 SN 1%8 (Spent fuel Pool Smea r #23 )
< 2
< 20 30 1 6
< 200 SN 1569 (Spent fuel Pool Smea r #24 )
(1) < 2
< 20 936 2 29 1373
< 2
< 20 16 1 8
< 200 SN 1510 ( Spent Tuel Pool Smea r #25 )
84 2 3
< 20 100 1 10
< 200 SN 1571 (Spent fuel Pool Smea r #26 )
SN 1572 (Spent f uel Pool Smea r #2 7 )
(1) 12 1 4
< 20 7830 1 84 12679 SN 15T3 (Spent fuel Pool Smea r #28 )
(1) 110 1 8 ND ( 2, 3) 40000 2 4000 9fMM)O SN 15184 (S ent TpeI Poo1 Seca r #29 )
(1) 32 2 6
( 2, 3) 152000 t 8000 250000 SN 151*> ( Spen t I ne l Pool Smea r #30)
(1) 32 2 6 ND ( 2, 3) 34900 1 180 60000 SN 1576 (Spent Tuel Pool Smear #28-1)
(1)2425
< 20 11000 t 100 18332 SN 15F T (Spent f uel Pool Smea r #29-1 )
(1)212
< 20 11900 1 104 18566 SN 1578 (Spent fuel Pool Smea r #30-1 )
(1) 8 1 3
< 20 5000 t 68 8099
< 2
< 20 is 1 3
< 2(Mt SN 1579 (Primary Sample Room Smear #1)
< 2
< 20 1314
< 200 SN 1580 (Primary Sample Room smear #2)
< 2
< 20
$i3
< 200 SN 1581 ( Prima ry Sample Poom Smea r #3 )
SN 1582 ( Pr; mary sample f.oom Smea r #4)
(1) < 2
< 20 2910 t $1 5991 SN 1583 ( Primary Sample Room S. ear #5)
(1)222
< 20 1250 t 38s 2670 53 1584 ( Primary Sample Room Smea r #6)
(1)412
< 20 3170 1 Saa 7110 SN 1585 ( Pr ima ry Samp l e Room Smea r # 7 )
(1)412
< 20 4340 t 63 9787 S:1 1586 ( Primary sample Room Smear #8)
(1)312
< 20 as360 1 63 9363 S*3 158T ( Prima ry Sample Room smear #9)
(1) < 2
< 20 1970 2 42 4183 SN 1588 ( Primary Sample Room Smear #10)
(1) 57 i 8 ND (2, 3) 72000 M 4000 200000 SN 1589 (Primary Sample Room Smear #11)
(1) < 2
< 20 220 1 14 467 SN 1590 ( Primary Sample Room Smear #12)
(1) 1518s ND (2, 3) 32000 t 8s000 90000
$3 1591 ( Primary Sample Room Smea r #13)
(1) < 2
< 20 579 1 23 1382
< 2
< 20 8s t i6
< 200 S3 1592 (Primary Sample Room smea r #184)
< 2
< 20 93 1 7 297 SN 1*>93 ( Primary Sample Room Smea r #15)
---
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-
-
-.
.-
,
s
,
o e
Cross Alpha. dpmAmeE Cross Beta, dpef_smea r
,
Hample 3D NHQ Licensee
!8RC Liyen}gg
SN 1594 ( Prima ry Sample Room Smea r #10-1)
(1)412
<20 7000 1 80 15218
,
SN 1$95 ( Primary sample Room Smea r #12-1)
(1) <2
<20
$160 1 68 11137 (1) Alpha activity was determined using an alpha scintillation counter, [berl ine SAC-4.
(2) Bets / gamma activity was determined using an [berline RM-14.
(3) Values reported by the licensee reflect activity prior to a smear being taken of the original smeae.
NRC values for SN 1573, 1574, 1575, 1588, and 1590 are not comparable to the licensee's values since a smear of these Smears was performed prior to analysis by the NRC laboratory.
(4) NRC uncertainties are 2 Standard deviations.
i
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