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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 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 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 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 ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed 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 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 L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS 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 L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 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 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 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 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 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 L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 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 IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements 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 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 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 ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 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 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 ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:NRC TO U.S. CONGRESS
MONTHYEARML20235Z1691989-02-16016 February 1989 Forwards Ofc of Investigations Rept for Case 2-86-005 Concluding That Allegations of Concerned Employee Not Substantiated ML20196C3481988-11-28028 November 1988 Informs That Ofc of Investigations Reviewed All Info Developed During Investigation of Allegations & Concluded That No Addl Field Work Required.Rept of Investigations Outlining Findings Expected in Jan 1989 ML20205T4451988-11-0202 November 1988 Advises That Ofc of Investigations Concluded Interviews W/ Util Mgt Employees on 880928.Ofc Currently Evaluating Testimonial & Documentary Info Developed During Course of Investigation to Determine If Addl Field Work Appropriate ML20205E5911988-09-21021 September 1988 Informs That Results of Interview of 11 Util Employees by OI Will Be Incorporated Into OI Rept of Investigation Re Plant ML20207G6191988-08-15015 August 1988 Informs That Hearing Held on 880801 to Resolve Three Issues, Including Petition Filed by Attys Representing Alabama Power Co Employees to Quash/Modify Subpoenas Issued by Nrc.Motion Denied.Protective Order Encl ML20207C7611988-07-18018 July 1988 Informs of 880707 Motion Filed by Assistant Us Atty for Middle District of Alabama Requesting Util Show Cause Why Util Should Not Be Held in Contempt of Court for Not Honoring Subpoenas Issued by Ofc of Investigations ML20150C6171988-06-10010 June 1988 Advises That Request to Enforce Subpoenas Issued to 11 Util Employees Submitted to Us Justice Dept on 880520.Enforcement Request Not Yet Filed W/Court ML20154L5411988-05-16016 May 1988 Forwards Responses to Questions Contained in Re Plant.Documents Provided in Response to Question 1 Not Released to Public.Therefore Restricted Access Should Be Preserved ML20151Z6401988-02-17017 February 1988 Forwards Answers to Recipient Re Operation of Plant During 1982-83.NRC Satisfied W/Operation ML20137Z6621985-09-27027 September 1985 Responds to 850905 Constituent Ltr Re B&W Plants.Latest Eia Prepared for Plants Available in Lpdr in Apollo,Pa.Response to 850729 FOIA Request Encl 1989-02-16
[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 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 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 IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements 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 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 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 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 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 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 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 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 ML20199D8541999-01-12012 January 1999 Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199C9361999-01-0808 January 1999 Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted 1999-09-09
[Table view] |
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[ o UNITED STATES l
!' , g NUCLEAR REGULATOhY COMMISSION W ASHING TON, D. C. 20555 gQ
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/ February 17, 1988 so-s4e '
CHAIRMAN The Honorable Philip R. Sharp, Chairman i Subcommittee on Energy and Power Committee on Energy and Commerce United States House of Representatives Washington, D.C. 20515
Dear Mr. Chairman:
In your November 19, 1987 letter to me, you asked several questions regarding NRC actions relating to the operation of the Alabama Power Company's Joseph M. Farley Nuclear Plant in 1982-83. The Commission's responses to those specific questions are enclosed. The Commission believes that these responses establish that the NRC has acted appropriately and responsibly regarding the allegations described in your
'etter.
At present, the NRC is satisfied, based on our technical inspections and evaluations, that operation of the Farley plant presents no immediate public health and safety issues.
However, any final regulatory decisions on these questions must await completion of ongoing investigations by the NRC's Office of Investigations (01) and Office of Inspector and Auditor (OIA) that relate to these allegations. As the response to question 2 indicates, the 01 investigation has been delayed significantly owing to an unresolved dispute over the terms and conditions for interview of licensee personnel by NRC investigators. The Commission is following these matters closely, and we will advise you of any significant new developments.
Sincerely,
% W. ,
Lando W. Z ,J .
Enclosure:
J Responses to Questions Concerning Allegations at Farley cc: Rep. Carlos J. Moorhead i
8808300076 880217 COMMS NRCC PDR CORRESPONDENCE PNV hk"f )
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I OVESTION 1. (a) Has Farley been operated with damaged fuel?
ANSWER.
Yes. In 1982, Farley Nuclear Plant Unit 1 began experiencing higher than expected reactor coolant system radioactivity levels, which is an indication of fuel cladding failure. The plant continued to operate until a scheduled -
refueling outage in January 1983. During the refueling outage, the licensee found eleven assemblies with failed fuel ruds. In addition, during this refueling the licensee also found fuel pellets and fuel rod debris in and around the reactor vessel. The damaged fuel assemblie's, along with four other fuel assemblies which were found to be leaking, were removed from the reactor vessel and discharged to the spent fuel pool, i
a
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QUESTION 1. (b) If so, was such operation a violation of license conditions or NRC regulations?
ANSWER.
So far as we have determined to date, the amount of damaged fuel which Farley operated with Uas not so great as to violate license conditions or technical specifications. It is not uncommon for nuclear power plants to experience some fuel cladding failure. Consequently, the NRC has established limits on the specific radioactivity permitted in the primary coolant systems to ensure that plants do not operate with significant levels of fail'e d fuel. These limits are set forth in the plant's Technical Specifications appended to the facility license. Licensee records maintained during the operating cycle prior to the Unit i refueling outage in January 1983 indicate the plant did not exceed the specific radioactivity limits for steady state operations. However, allegations l were received that the plant exceeded this limit, and that the results of 1
analyses showing they exceeded the limit were not recorded by plant personnel. l These allegations are the subject of an 01 investigation presently underway.
l
CUESTION 1. (c) What is the safety significance of operating a plant with damaged fuel? Does it affect plant operation? Does it result in contamination of plant equipment? Can it lead to increases in exposures to plant workers? Was there any contamination or increase of exposure to plant workers in the Farley case?
ANSWER.
The safety significance of operating a nuclear power plant with damaged fuel is that of potential increases in radiological effluents released from the plant and increases in radiation exposure to plant workers from contaminated plant equipment. 1/ Plant shutdown is therefore required if the Technical Specification limits are exceeded for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or more. The Farley plant experienced increases in primary coolant radioactivity levels, resulting in increased radioactive effluents. However, the plant records indicate that radioactive effluents remained below the release limits specified in the plant's Technical Specifications. Farley workers experienced an increase in cumulative radiation exposure for 1983 of approximately 100 percent over the 1982 exposure.
Increased radiation levels in the plant, removal of the damaged fuel, and plant modifications to address the cause of the cladding damage contributed significantly to the increased exposure. Although Farley experienced significant increases in cumulative radiation exposure for 1983, the cumulative exposure was still less than the national average for pressurized water reactors. As noted above, the accuracy of the Farley plant records is the sub,iect of an allegation new under investigation by OI.
-1/
NRC Publication NUREG/CR 4485 "The Impact of Fuel Cladding Failure Events on Occupational Radiation Exposures at Nuclear Power Plant," documents the results of a study performed to determine the magnitude of the impact of fuel cladding failures during routine and outage activities at a pressurized water reactor. This study indicates that fuel cladding failures would result in an increase in radiation levels in many areas of the plant.
QUESTION 1. (d) Has the NRC or the utility taken any action to rectify the problem? Please explain.
ANSWER.
As noted above, the utility removed the damaged fuel during an outage which began in January 1983. In addition, plant modifications were made to correct the problem that caused the fuel cladding failures. The NRC inspection program included at that time, as it does now, not only a verification of regulatory compliance, but also an assessment of the plant's radiation protection staff capabilitics and management's involvement in programs to maintain radiation exposures as low as reasonably achievable. Based on inspections performed subsequent to the fuel cladding failures (which have not identified any '
significant lasting effects resulting from the operation of the plant with damaged fuel), the NRC staff is satisfied that there are no imediate public health and safety issues at Farley as a result of the fuel damage, i 1
QUESTION 1. (e) Has the NRC taken, or does the NRC intend to take, enforcement action as a result of this incident?
ANSWER.
To date, the NRC has not taken enforcement actions as a result of this incident, as inspections performed by NRC regional and resident inspectors have not identified any violations of regulatory requirements resulting from operation of the plant with damaged fuel. Enforcement action will be taken if investigations now in progress establish a factual basis for such action.
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QUESTION 2. Is there an ongoing or completed investigation by your Office of Investigations (01) concerning activities at the Farley plant? Please describe the findings or status of any such investigation.
ANSWER.
Yes, there is an ongoing investigation by the Office of Investigations (01) concerning activities at the Farley clant. It was initiated after the Regional Administrator of NRC Region II requested 01's assistance, on August 23. 1985, to interview an individual who alleged potential falsification of health physics test and measuremeri data by officials at Farley. After the interview, the Regional Administra or requested that the investigative effort be expanded to determine whether the falsification of records occurred as alleged. The investigation has been delayed since mid-1986 because of an unresolved dispute between 01 and the law firm which is representing both the licensee and potential interviewees (past and present employees of the licensee). The nature of the dispute is documented in the attached correspondence between OI and the law firm in question. Efforts to resolve this impasse, though unsuccessful to i date, are continuing.
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QUESTION 3. Is there an ongoing or completed investigation by your .
OfficeofInspectorandAuditor(OIA)concerningtheNRC staff's handling of issues at Farley? Please describe the findings or status of any such investigation.
ANSWER.
The Office of Inspector and Auditor (OIA) is conducting three investigations into concerns related to the NRC staff's handling of issues at Farley.
In the first investigation, an alleger claimed that the Region II Allegation and Investigations Coordinator mischaracterized his concern about contamination of a creek by discharges from Farley. The second investigation pertains to an allegation that an NRC employee was attempting to impede an 01 investigation of the Alabama Power Company and that the NRC had removed NRC Inspection Reports :
from the local Public Document Room in Dothan, AL, to preclude public access to '
these records. The third OIA investigation involves several general alleged ,
improprieties pertaining to NRC's regulatien of Farley.
j OIA's three investigations pertaining to Farley are all ongoing; therefore, it ,
would be premature to discuss our findings at this time. We anticipate all the l investigations will be completed within 90 days.
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QUESTION 4 (a) Did the NRC receive, or is the NRC aware of, allegations that Farley employees were harassed or fired when they tried to raise health and safety concerns? Please provide whatever infomation you have on this.
ANSWER _.
A member of the Region II Regional Administrator's staff provided OI:RII with information by memoranda dated March 10 and April 1,1986, that "several indi-viduals" were r.ubjected to harassment because they raised safety concerns.
Additionally, in April 1987, Region 11 received a telephone call from an individual alleging that he was being blacklisted by Alabama Power Company because of issues he raised in 1982 associated with the fuel failure problem at Farley. The Region II allegation coordinator advised the individual of the directemployeeremediesfordiscrimination(e.g., blacklisting)available through the Department of Labor (DOL), and the individual subsequently filed a formal complaint with DOL and forwarded a copy to the NRC. The DOL investigated the allegation, held a hearing, and found the complaint to be without merit.
Presently, the individual is appealing the DOL decision. Further, "the several individuals" referred to in the aforementioned Region II memoranda were identified and interviewed by 01. During the interviews, it was determined that three of the four former Farley employees are the plaintiffs in a wrongful dismissal suit against Alabama Power Company filed in the Jefferson County, Alabama (Bimingham) Circuit Court. l
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l QUESTION 4 (b) What is the NRC's policy for dealing with allegations of P
harassment and intimidation of licensee employees for raising safety concerns?
ANSWER.
Harassnent and intimidation may constitute violations of the Commission's anti-discrimination regulations (e.g.,10 CFR 50.7) th.at mirror the employee protection provisions of section 210 of the Energy Reorganization Act or of the independence criterion for quality assurance progr.ws undar 10 CFR Part 50, Appendix B. Because the Department of Labor (DOL) and NRC have complementary responsibilities in the area of employee protecticn, DC'. and NRC have entered into a Memorandum of Understanding, 47 Fed. Reg. 54585 (Dec. 3, 1982) to facilitate cooperation and coordination. Guidance to NRC employees on handling allegations in this area has been issued in NRC Manual Chapter Appendix 0517 Part I.C.4 The NRC usually awaits the completien of DOL investigations and related proceedings under section 210 before initiating its own investigation or enforcement action for a complaint of discrimination. However, if an allegation is made to the NRC that involves significant public health and safety implications (e.g., the allegations of intimidation or discrimination are so widespread as to require imediate action or involve high levels of nanagement),
the NRC may take action imediately without waiting for DOL. The action to be taken would be detertnined on a case-by-case basis and would include consideration of imediate NRC investigation and enforcement action for specific acts of discriminatien, action to identify patterns of discrimination and levels of management involvement to bring to the attention of the licensee, and
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QUESTION 4(o). Cont.inued) l enforcement conferences and management meetings to discuss possible licensee actions with reotrd to the potential chilling effect of discrimination.
Technical issues can'be examined through the NRC inspection process and would be acted on without regard to pending 00L proceedings.
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