Letter Sequence RAI |
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MONTHYEARML20203E0371998-02-12012 February 1998 Forwards RAI Re Inservice Insp Program Plan & Associated Requests for Relief for Plant,Units 1 & 2 Project stage: RAI ML20249A3391998-06-12012 June 1998 Forwards RAI Re ISI Program Plan & Associated Requests for Relief.Info Requested to Be Provided by 980724 Project stage: RAI ML20199D8541999-01-12012 January 1999 Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 Project stage: Approval 1998-06-12
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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: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] |
Text
__ . _ _ . _ _ _ __. .. - _ _ _ -_ _ _ _ _ _ _ ___ _ _
, , february 12, 1998 Mr. D. N. Mor:y Vice President Farley Project Southern Nuclear Operating Company, Inc.
s Post Office Box 1295 Birmingham, Alabama 35201 1295
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF JOSEPH M. FARLEY NUCLEAR Pl. ANT, UNITS 1 AND 2 (TAC NOS. M98858 AND M98859)
Dear Mr. Morey:
By letter dated May 28,1997, and supplemented by letter dated November 3,1997, you submitted the Joseph M. Farley Nuclear Plant, Units 1 and 2 Inservice Insptction (ISI)
Programs in accordance with the requirements of 10 CFR 50.55a(g)(4)(ii).
The staff, with assistance from its contractor, Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed your submittals and determined that additional information is required. The enclosure identifies the requested additionalinformation (RAI) needed.
in order to maintain a timely review, it is requested that the information be provided within 60 days of receipt of this letter. In addition, to expedite the review process, please send a copy of your RAI response to the NRC contractor identified in the enclosure. If you require any clarification regarding this reqti st, please call me at (301) 415 2426.
Sincerely, ORIGINAL SIGNED BY:
Jacob 1. Zimmerman, Project Manager Project Directorate 112 Division of Reactor Projects -l/ll
. Office of Nuclear Reactor Regulation !
l\
Docket Nos. 50-348 and 50-36*
Enclosure:
As stated cc w/ encl: See next page hI Qigiribution:
PDil 2 Rdg. JZimmerman JZwolinski ACRS doeN9t Me HBerkow PSkinner, Ril OGC PUBLIC LBerry JJohnson, Ril TMcLellan DOCUMENT NAME: G:\FARLEY\M98858 RAI To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" =
Copy with attachment /englosure "N" = No copy . A OFFICE PM POMh4 lE PM PDil-2 hM t LA',PDilp!#'\ l l NAME JZWfMSMAN'en LBERRY IQ1 HC'ERK(W/ /
DATE 2// 8 798 2/ lM98 7 t/ N 9B .ii6 c * *
- OFFiclAL RECORD COPY 9802260238 980212 -_I ~"' 7f PDR ADOCK 05000348- *" d " '-~ .- A h G PDR
s a ct:
,y e t UMTED STATES s g NUCLEAR HEGULATORY COMMi3SION "o g WASHINGTON, D.C. 30t#4'J01
%* . . , , , 'd' Tebruary 12, 1998 Mr. D. N Morey Vice President- Fa iey Project Southem Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201 1295
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF
- JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M98858 AND M98859)
Dear Mr. Morey:
By letter datud May 28,1997, and supplemented by letter dated November 3,1997, you submitted the Joseph M. Farley Nuclear Plant, Units 1 and 2 Inservice Inspection (ISI)
Program iin accordance with the requirements of 10 CFR 50.55a(g)(4)(li).
The staff, with assistance from its contractor, Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed your submittals and determined that additional information is required. The enclosure identifies the requested additionalinformation (RAI) needed.
In order to maintain a timely review, it is iequested that the infon?.ation be provided within 60 days of receipt of this letter. In addition, to expedite the review process, please send a copy of your RAI response to the NRC contractor identified in the enclosure. If you require any clarification regarding this request, please call me at (301) 415-2426.
Sincerely, h
Jacob 1. immerman, Project Manager Project Directorate ll 2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50 364
Enclosure:
As stated cc w/ encl: See next page
l l
Joseph M. Farley Nuclear Plant ;
cc:
Mr. R. D. Hill, Jr. I General Manager - ,
i Southem Nuclear Operating Company Post Omco Box 470 Ashford, Alabama 36312 !
Mr. Mark Ajiuni, Licensing Manager I Southem Nuclear Operating Company .
Post Office Box 1295 Birmingham, Alabama 35201 1205
- Mr. M. Stanford Blanton
! Balch and Bingham Law Firm Post Office Box 306
- 1710 Sixth Avenue North Birmingham, Alabama 35201 -
Mr. J. D. Woodard Executive Vice President Southem Nuclear Operating Company
- Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer .
Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 30130-1701 9
Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region ll U.3. Nuclear Regulatory Commissim Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 '
Atlanta, Georgia 30303 ,
~
Resident inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway g5 Columbia, Alabama 3631g
r ,
l, .-
- I r
4 M ie!L M I' j ADanadion Program Plan
!- )
- 1. Scopa/ Status f Review i
! Throughout the service life of a water-cooled nuclear power facility, Title 10 of the Code of l Fadatal Regulations (10 CFR) 50.55a(g)(4) requires that components (including supports) that ;
j are classified as American Society of Mechanical Engineers (ASME) Boller and Pressure l
, Vessel Code (ASME Code) Class 1 Class 2, and Class 3 meet the requirements, except i j design and access provisions and preservice examir.ation requirements, set forth in Section XI i of the ASME Code, " Rules for inservice inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the .
components. This section of the regulations also requires that inservice examinations of :
! components and system pressure tests conducted during the successive 120-month inspection
- intervals comply with the requirements in the latest edition and addenda of the Code ;
incorporated by reference in 10 CFR 50.65a(b) on the date 12 months prior to the start of an j interval, subject to the limitations nnd modifications listed therein. The components (including ,
. _ supports) may meet requirements set forth in subsequent editions and addenda of the Code
- that are incorporate i by reference in 10 CFR 50.55a(b) subject to the limitations and
- modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval. .
- The !icensee, Southem Nuclear Operating Company, has prepared the Joseph M. Farfey
! Nuclear Plant, Units 1 & 2, Third 10-Year IntervalInservice Inspection Program Plan, .
j Revision 0, to meet the requirements of the 198g Edition of Section XI of the ASME Code.
I L The staff has reviewed the available information in the Joseph M. Farfey Nuclear Plant, Un/t 1, <
Third 10-Year IntervalInservice Inspection (ISI) Program Plan, the Joseph M. Farfey Nuclear l Plant, Unit 2, Updated Inservice Inspection (ISI) Program Plan, Revision 0, submitted May 28,
- j. 1997, and the licensee's requests for relief from ASME Code Section XI requirements.
- 2. AdditionalInformation Required >
l Based on the proceding review, the staff has concluded that additional information and/or clarification is required to complete its review, of the ISl Program Plan, j A. By a Safety Evaluation Report (SER) dated March 20,1997, the NRC allowed Southem Nuclesr Operating Company (SNC) to update the Unit 2 ISI Program approximately ;
i 44 months early, to coincide with the required update of the Unit 1 program. As stated by SNC, 'this update will become effective on December 1,1997, and will continue in
.' place through November 30,2007. Unit 2 is presently in tlw second interval with the l third interval scheduled to start on July 30,2001; therefore, this update will cover part of
- the second and third intervals?
~ The method of implementation for the Unit 2 program is unclear because the plan covers portions of two intervals. Explain SNC's plan for completing interval requirements, For example, when the Code allows deferral of examinations to the end ,
- of the interval, what date will be used for the end of the interval? Also, describe how the 4 - trancition from the second 10 year interval to the third 10 year interval will take place. .
How will SNC close out the second 10-year interval prior to beginning the third 10 year i interval? Will all of the secona 10 ycar interval requirements and commitments be met? -
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, 2-IWB 2420 requires that the sequence of component exsminations established during the first inspection interval be repeated during each su;cessive inspection interval. By using the same examination sequence each interval, essentially no more than 10 years willlapse between examinations. Since SNC is combining portions of two intervals into one program plan, will the sequen;e of examinations be altered significantly from the first 10 Year interval? Will more than 10 years elapse between examinations for any component?
B. The Program submittal does nat include an implementation schedule for performance of examinations as required by IWA 2420(b). This is necessary to determine compliance with Tables IWB 24121, IWC 24121, and IWD 24121. Provide an implementation schedule including the total number of components in each item Number, the total number of componentt, selected for exatnination in cach item Number, and the period (include interval for Unit 2) in which the examinations will occur.
C. In accordance with 10 CFR 50.55a(c)(3),10 CFR 50.55a(d)(2), and 10 CFR 50.55a(o)(2), ASME Code Cases may be used as alternatives to Code requirements. Code Cases that the NRC has approved for use are listed in Regulatory Guide 1.147, inservice Inspection Code Case Acceptability, with any additional conditions that the NRC may have imposed, When used, these Code Cases must be implemented in their entirety. The licensee may adopt an approved Code Case by notifying the NRC in writing. Published Code Cases awaiting approval and subsequent listing in Regulatory Guide 1.147 may be adopted only if the licensee
.aquests, and the NRC authorizes, thelc use on a case by-case basis. Provide a list of all Code Cases, both approved and unapproved, that SNC intends to implement during the third 10 year interval.
D. Augmented examinations have been established by the NRC when added assurance of structural reliabihty is deemed necessary. Examples of documents that address augmented examinations are:
(1) Branch Technical Position MEB 31, High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containmsnt, and (2) Regulatorj Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations.
Address the degree of compliance with these documents and any other augmented examinations, which may have been incorporated in the third 10 year interval inservice inspection program plan.
E. Provide the staff with the status of the augmented reactor pressure vessel examinations required by 10 CFR 50.55a(g)(6)(ii)(A), effective September 8,1992, and provido a technical discussion of how the regulation was/will be implemented at Joseph M. Farley Nuclear Plant, Units 1 and 2. Include in the disec a e description of the approach and any specialized techniques or equipment that was# be used to complete the required augmented examination. Also, provide the percent of the volume examined for each
l 3-wold. Section 50.55a(g)(6)(ii)(A)(2) requires essentially 100% of the volume of each weld to be examined. Confirm that ' essentially 100T of each Examination Category 81.10 weld (RPV shell welds) has been examined, or that an alternative has been submitted for staff review.
F. Provide a list of all ultrasonic calibration blocks to be used during the third 10-year !
interval, including identifications, material specifications, and sizes. Also, provide a list of all ultrasonic examination proceduren that will be used in the ISI Program; include titles and general descriptions of the components to which each procedure is applicable.
G. SNC must state %s specific paragraph of the Regulations under which each proposed request for rahef or attemative is submitted. In some cases, it appears that SNC has cited the wrong paragraph. For example, SNC has requested that RR 16 be granted pursuant to 10 CFR 50.55a(s)(3)(l). Howner, SNC states that ' Denial of this relief request would cause an excessive burden upon Southern Nuclear Operating Company because it hac been demonstrated that it is impractical to muet the Code requirements with presently developed techniques." Because SNC states that the required examination is a burden and imoractical, and no alternative examination is presented, it la unclear whether this relief request falls within the category of 50.55a(a)(3)(ii) or l 50.55a(g)(5)(lii).
l A licensee may pi ' pose an altemative to CFR or Code requirements in accordance with l 10 CFR 50.55s(a)(3)(1) or 10 CFR 50.55a(a)(3)(ii). When submitting a proposed alternative, the licensee must specify the appropriate regulatory basis. Under 10 CFR 50.55a(s)(3)(i), the proposed alternative must be shown to provide an acceptatste level of quality and safety, i.e., essentially be equivalent to the original requiremont in terms of quality and safety. Under 10 CFR 50.55a(s)(3)(ii), the licensee must show that compliance with the original requirement results in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Examp!as of hardship and/or unusual difficulty include, but are not limited to excessive radiation exposure, disassembly of components solely to provide access for examinations, and development of sophisticated tooling that would result in only minimalincreases in examination coverage.
In accordance with 10 CFR 50.55a(g)(5)(iii), a licensee may submit a request for relief from ASME Code requirements. If a licensee determines that conformance with certain ASME Code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in Section 50.4, information to support that determination. Wher, a licensee determines that an inservice inspection requirement is impractical, e.g., the system would have to be redesigned or a component would have to be replaced to enable inspection, the licensee should cite this part of CFR to support the criteria for evaluation The NRC may, giving due consideration to the burden placed on the Heensee, impose an alternative examination requirement.
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4 SNC should review the submitted requests for relief and provide the required references to ensure that each request for relief is evaluated in accordance with the appropriate criteda.
H. Request for Rollef RR 6,7,9,17. Several requests for relief were submitted based on estimated examination coverages. For example, in RR 6, SNC noted that the examination coverage listed in the request for relief is based upon several factors, including NDE data sheet evaluations, design drawing configurations, field observations, and measurements of the components. In addition, SNC stated that *Due to these factors, examination coverage is given as a range for these examinations. Actual examination results should fall within the ranges listed; however, variations outside this range are possible and this relief request would be modified only if the values are significantly out of range.'
The Code requires that all examinations be performed to the extent practical. The licensee provioes a ' range' of coverage, making it difficult to determine if the licensee has met or exceeded previous examination coverages. Relief cannot be granted hased upon a range of examination coverage. For the requests currently being evaluateu,if the actual coverages do not meet or exceed the actual coverages previously obtained, ths licensee will be required to resubmit for relief. Therefore, the licensee should provic'e the actual coverages expected or consider submitting the subject relief requests following the examinations when actual coverages cen be calculated. Provide information as to the course of action SNC proposes to take regarding examination coverages.
- l. Request for Relief RR 9. It is unclear which welds are affected by this relief request.
Are the four branch connections listed in RR 9 the only compononts for which relief is requested? Identify all branch connections that will be affected by this request for relief.
J. Request for Rollef RR 14. IWC 1222, of the 1989 Addenda of ASME Section XI, exempts vessels, pumps, and valves and their connections in piping NPS 4 and smaller within systems (or portions of systems) other than residual heat removal (RHR),
emergency core cooling (ECC), and containment heat removal (CHR) systems, with the followiq note: 'In piping" is defined as having a cumulative inlet and a cumulative outlet pipe cross sectional area neither of which exceeds the nominal outside diameter (OD) cross sectional area of the designated size.
Provide information concerning the components listed in Request for Relief RR 14, including the si: es of inlet and outlet lines. Confirm that the cumulative inlet or the cumulative outlet pipe cross sectional areas do not exceed the nominal OD cross +ectional area of the designated size, it appears from drawing D175039, sheet 2 of 7, that the Volume Control Tank may have at least three 3-inch inlet lines. This would make the cumulative inlet cross sectional area greater than the nominal OD cross-sectional area of the designated size. Consequently,it would not be exempt from examination.
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Also confirm that the subject components are within systems (or portions of systems) other than the RHR, ECC, and CHR systems. Provide the necessary information to verify that the subject components comply with the 1989 Addenda of ASME Section XI, IWC.1222 K. Request for Rollef RR 17, It appears from Attachment 171 that, for reflectors transverse to the shell-to-flange weld, a greater volume can be examined than the approximate 30% coverage (scanning from shell side of weld) stated in RR 17 for reflectors transverse to the shell-to flange weld. RR 17 identifies the limitations for this examination as the sharp taper on the flange side and the configuration of the examination sled. What specific techniques or equipment modifications have been employed to maximize the percentage of volume examined?
L. Request for Rollef RR 18. RR 18 proposes an attemative schedule for reactor pressure vessel nozzle examinations. Code Case N 521, Altomat/ve Rules for Deferral ofInspection*: of Nozzle to Vessel Weld' Inside Radius Sections, and Nozzle-to-Safe End Wolds of e Pressudzed Water Re Vessel, has been found acceptable for use with the following conditions: (a) no inst ,ce repairs or replacements by welding have ever been performed on any of the subject areas;(b) none of the subject areas cor,tain identified flaws o elevant conditions that currently require successive inspections in accordance with IWB 2420(b); and (c) the unit is not in the first interval. An additional requirement imposed by the NRC is that all subject areas be scheduled for examination such that the new sequence of examinations will not exceed 10 years beiwoen examinations. Confirm that all of tne above conditions will be met.
M. Request for Rollef RR 23. Pursuant to 10 CFR 50.55a(a)(3)(l), SNC proposed to use Code Case N 566, Corrective Action for Leakage at Bolted Connections,Section XI, Olvision 1, in lieu of the corrective measures specified by the Code for leakage at bolted connections. This Code Case is currently being reviewed by the NRC staff and, as of yet, not been found acceptable as written. The NRC has approved the use of alternatives to the requirements of IWA 5250(a)(2) proposed by other licensees that have included a detailed and well defined evaluation of the botting and the bolted connection. Considering that Code Case N 566, as currently written, will probably not be authorized at this time, discuss the intended action regarding use of this Code Case at Farley, N. Verify that there are no requests for relief in addition to those submitted, if additional requests for relief are required, SNC should submit them for staff review.
The schedule for timely completion of this review requires that SNC provide, by the specified date, the above requested information and/or clarifications regarding the Joseph M. Farley Nuclear Plant, Unit 1, Third 10-Year IntervalInservice inspection (ISl} Program Plan and the Joseph M. Farley Nuclear Plant, Unit 2, Updated Inservice Inspection (ISI) Program Plan, Revision 0.
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