|
|
Line 49: |
Line 49: |
| . Enclosure 1 Unit i Third 'l en Year interval Rr_qusst for Relief No. RR-27 | | . Enclosure 1 Unit i Third 'l en Year interval Rr_qusst for Relief No. RR-27 |
| : 1. System / Component (s) for Which Reliefis RtQufited Bolted connections located in the Class I reactor coolant system pressure boundary. | | : 1. System / Component (s) for Which Reliefis RtQufited Bolted connections located in the Class I reactor coolant system pressure boundary. |
| II. CodcAtguirrnical: ASME Section XI,1989 Edition, Paragraph IWA 5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retalning bolted connections prior to performing the visual examination. Table IWB 2500-1, Examination Category B P requires a system leakage test (IWB-5221) and corresponding VT-2 visual examination on Class I components each refueling outage prior to plant startup. Table IWB-25001, Examination Category B-P also requires a hydrostatic test (IWB-5222) and corresponding VT-2 visuel examination be performed on Class I components on a ten year frequency. (Note: FNP intends to use Code Case N-498-1, as requested in Relief Request RR-21 by SNC letter dated May 28,1997, es an alternative to the hydrostatic test). | | II. CodcAtguirrnical: ASME Section XI,1989 Edition, Paragraph IWA 5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retalning bolted connections prior to performing the visual examination. Table IWB 2500-1, Examination Category B P requires a system leakage test (IWB-5221) and corresponding VT-2 visual examination on Class I components each refueling outage prior to plant startup. Table IWB-25001, Examination Category B-P also requires a hydrostatic test (IWB-5222) and corresponding VT-2 visuel examination be performed on Class I components on a ten year frequency. (Note: FNP intends to use Code Case N-498-1, as requested in Relief Request RR-21 by SNC {{letter dated|date=May 28, 1997|text=letter dated May 28,1997}}, es an alternative to the hydrostatic test). |
| III. Code RcQuirement for Whicideligfis Regunted: Insulation will not be removed from pressure-retaining bolted connec: ions prior to performing VT-2 visual examinations during the conduct of pressure tests. | | III. Code RcQuirement for Whicideligfis Regunted: Insulation will not be removed from pressure-retaining bolted connec: ions prior to performing VT-2 visual examinations during the conduct of pressure tests. |
| IV. llasit.fgr Relief: These system pressure tests are performed during startup when the Reactor Coolant System is at nominal operating pressure and at near operating temperature. The re-installation ofinsulation after the performance of system pressure testing is considered to pose potential nuclear safety and personnel safety issues, as follows. | | IV. llasit.fgr Relief: These system pressure tests are performed during startup when the Reactor Coolant System is at nominal operating pressure and at near operating temperature. The re-installation ofinsulation after the performance of system pressure testing is considered to pose potential nuclear safety and personnel safety issues, as follows. |
Line 71: |
Line 71: |
| : 1. System / Component (s) for Which Reliefis Requested: Bolted connections located in the Class I reactor coolant system pressure boundary. ! | | : 1. System / Component (s) for Which Reliefis Requested: Bolted connections located in the Class I reactor coolant system pressure boundary. ! |
| i i 11. Cnde.kquitement: ASME Section XI,1989 Edition, Paragraph IWA-5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation . | | i i 11. Cnde.kquitement: ASME Section XI,1989 Edition, Paragraph IWA-5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation . |
| shall be removed from pressure retaining bolted connections prior to performing the visual examination. Table IWB 2500-1, Examination Category B-P requires a system leakage test (IWB 5221) and corresponding VT-2 visual examination on Class 1 1 components each refueling outage prior to plant startup. Table IWB-2500-1, Examination Category B P also requires a hydrostatic test (IWB 5222) and corresponding VT-2 visual examination be performed on Class I components on a ten year frequency. (Note: FNP intends to use Code Case N-498-1, as requested in Relief Request RR 21 by SNC letter dated May 28,1997, as an alternative to the hydrostatic test). , | | shall be removed from pressure retaining bolted connections prior to performing the visual examination. Table IWB 2500-1, Examination Category B-P requires a system leakage test (IWB 5221) and corresponding VT-2 visual examination on Class 1 1 components each refueling outage prior to plant startup. Table IWB-2500-1, Examination Category B P also requires a hydrostatic test (IWB 5222) and corresponding VT-2 visual examination be performed on Class I components on a ten year frequency. (Note: FNP intends to use Code Case N-498-1, as requested in Relief Request RR 21 by SNC {{letter dated|date=May 28, 1997|text=letter dated May 28,1997}}, as an alternative to the hydrostatic test). , |
| III. Codc.kguitsment for Which Reliefis kgucited: Insulation will not be removed from ' | | III. Codc.kguitsment for Which Reliefis kgucited: Insulation will not be removed from ' |
| pressure-setaining bolted connections prior to performing VT-2 visual examinations during the conduct of pressure tests. | | pressure-setaining bolted connections prior to performing VT-2 visual examinations during the conduct of pressure tests. |
|
---|
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:INCOMING CORRESPONDENCE
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 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 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 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 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 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 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 ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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 L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC 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 ML20196J8631999-06-30030 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 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 L-99-224, 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 ML20195F1731999-06-0707 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-99-217, 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-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999 Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999 Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999 Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21 ML20206B4391999-04-21021 April 1999 Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205R0431999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error 1999-09-23
[Table view] |
Text
< . I Dave Morey Southern Nuclear Scs Presdent Operating Company f atley Project PO Boa 1295 Bemingham. Alabama 35201
. Tel 2ffs 932.5131 s
SOUTHERN November 18, 1997 COMPANY !
Energy to Serve hur Wid' l Docket Nos.: 50-348 10 CFR 50.55 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk j Washington, DC 20555 l
1 1
Joseph M. Farley Nuclear Plant Mief Request No. 27 Ladies and Gentlemen:
In accordance with the provisions of 10CFR50.55a(a)(3)(i), Southern Nuclear Operating Company (SNC) is requesting NRC approval of enclosed Re:icf Requests RR-27 (one for Unit I and one for Unit 2) concerning the Class I pressure test requirements oflWA-5242(a) of the 1989 Edition of ASME Section XI. Paragraph IWA-5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retaining bolted connections prior to performing visual examinations. Thc visual examination are performed each outage during startup with the Class 1 piping and components at normal operating pressure and at near normal operating temperature.
This is a new Code requirement for Farley that becomes efTective on December 1,1997, with the implementation of the 1989 Code. Afler evaluation of this new requirement, SNC believes this requirement to pose both nuclear and personnel safety concerns at Farley. These concerns are:
//
- 1. Loose insulation would be in the containment during a mode in which a LOCA must be /'/
considered. If a LOCA occurred during re-installation of the insulation, the insulation could Systems.
Cooling migrate to the containment sumps and restrict the suction / of f the Eme
- 2. There are incret. sed hazards for personnel due to the high contact temperature of the bolting and due to the high containment ambient temperature.
SNC believes that use of the alternate examinations delineated in the relief requests will provide an acceptable level of quality and safety for Class I bolted connections, while climinating nuclear and personnel safety concerns. A similar version of this relief request has been approved for use on Class I bolted connections at SNC's Vogtle Electric Generating Plant per the NRC's Safety Evaluation dated October 24,1997. Approvalis requested by 9712010118 971118 Its im if t 11:Hifilli PDR ADOCK 05000348 ll'!HE N 'lailltlidI!Dl'l!!Ill lu.
P PDR
l U S. Nuclear Regulatory Commission ' Page 2 February 28,1998, to support pressure testing during the Unit 2 refueling outage, currently scheduled to commence in March 1998. l Ifyou have any questions, please advise.
Respectfully submitted.
SOUTHERN NUCLEAR OPERATING COMPANY b ?llWf Dave Morey M1A/ cit:bolicov. doc
Enclosures:
- 1. Unit 1 - Third Ten Year Intervs Request for Relief No. RR-27
- 2. Unit 2 - Updated Program Request for Relief No. RR-27 cc: Mr. L. A. Reyes, Region 11 Administrator -
Mr. J.1. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident inspector 4
6
l ENCLOSUREI Farley Nuclear Plant - Unit 1 Third TELYratlokm1Brancst for Relief No. RR 27
[
. Enclosure 1 Unit i Third 'l en Year interval Rr_qusst for Relief No. RR-27
- 1. System / Component (s) for Which Reliefis RtQufited Bolted connections located in the Class I reactor coolant system pressure boundary.
II. CodcAtguirrnical: ASME Section XI,1989 Edition, Paragraph IWA 5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retalning bolted connections prior to performing the visual examination. Table IWB 2500-1, Examination Category B P requires a system leakage test (IWB-5221) and corresponding VT-2 visual examination on Class I components each refueling outage prior to plant startup. Table IWB-25001, Examination Category B-P also requires a hydrostatic test (IWB-5222) and corresponding VT-2 visuel examination be performed on Class I components on a ten year frequency. (Note: FNP intends to use Code Case N-498-1, as requested in Relief Request RR-21 by SNC letter dated May 28,1997, es an alternative to the hydrostatic test).
III. Code RcQuirement for Whicideligfis Regunted: Insulation will not be removed from pressure-retaining bolted connec: ions prior to performing VT-2 visual examinations during the conduct of pressure tests.
IV. llasit.fgr Relief: These system pressure tests are performed during startup when the Reactor Coolant System is at nominal operating pressure and at near operating temperature. The re-installation ofinsulation after the performance of system pressure testing is considered to pose potential nuclear safety and personnel safety issues, as follows.
- 1. Loose insulation would be in the containment during a mode in chich a LOCA must be considered if a LOCA occunM during re installation of the insulation, the insulation could migrate to the comamment sumps and restrict the suction of the Emergency Core Cooling Systems.
- 2. There are increased hazards for personnel due to the high contact temperature of the bolting and due to the high containment ambNnt temperature.
V. Alternate Examination: Insulated Class I pressure-retaining bolted connections will be uninsulated and VT-2 examined once each refueling outage while the connections are at atmospheric or static pressures. The bolted connections will subsequently be examined (aller the insulation is re-installed) during the regularly scheduled system pressure test conducted at nominal operating pressure and at near operating temperature. This re-examination will be conducted no earlier than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after ruching nominal system operating pressure.
El-1
linclosure 1 RRt27 - Unit i VI. histiEcation for GrAatiaghliff: The pressure test with the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time will allow adequate time for any leakage to penetrate the insulation, thereby, providing a means of detecting any significant leakage with the insulation in place. Secondly, by removing
)
the insulation each refueling outage, any boric acid residue can be detected. This two-phase approach provides an acceptable level of quality and safety for Class 1 bolted j connections; therefore, the proposed alternative should be authorized pursuant to 10CFR50.S$a(a)(3)(i).
Vll. Impkmentation Scheduk: This request for reliefis applicable to the Third Ten-Year Interval beginning December 1,1997.
Vill. ReliefRequesLSlaitu: This is a new third interval relief request, awaiting NRC approval.
El-2
ENCLOSURE 2 Farley Nuclear Plant - Unit 2 lladattdhegram ikqunLfor ReliefNo RR-27
{
i
- Enclosure 2 Unit 2 Updatedhogram - keouest for Relief No. RR 27 l t
- 1. System / Component (s) for Which Reliefis Requested: Bolted connections located in the Class I reactor coolant system pressure boundary. !
i i 11. Cnde.kquitement: ASME Section XI,1989 Edition, Paragraph IWA-5242(a) requires that for systems borated for the purposes of controlling reactivity, insulation .
shall be removed from pressure retaining bolted connections prior to performing the visual examination. Table IWB 2500-1, Examination Category B-P requires a system leakage test (IWB 5221) and corresponding VT-2 visual examination on Class 1 1 components each refueling outage prior to plant startup. Table IWB-2500-1, Examination Category B P also requires a hydrostatic test (IWB 5222) and corresponding VT-2 visual examination be performed on Class I components on a ten year frequency. (Note: FNP intends to use Code Case N-498-1, as requested in Relief Request RR 21 by SNC letter dated May 28,1997, as an alternative to the hydrostatic test). ,
III. Codc.kguitsment for Which Reliefis kgucited: Insulation will not be removed from '
pressure-setaining bolted connections prior to performing VT-2 visual examinations during the conduct of pressure tests.
IV. Dasis for Rdief: These system pressure tests are performed during startup whc, the Reactor Coolant System is at nominal operating pressure and at near operating j temperaturc. The re-installation ofinsulation after the performance of system pressure testing is considered to pose potential nuclear safety and personnel safety issues, as follows:
- 1. Loose insulation would be in the containment during a mode in which a LOCA must be considered. If a LOCA occurred during re-installation of the insulation, the insulation could migrate to the containment sumps and restrict the suction of the Emergency Core Cooling Systems.
- 2. There are increased hazards for personnel due to the high contact temperature of the bolting and due to the high containment ambient temperature.
V. AlternatcluminatinD: Insulated Class I pressure-retaining bolted connections will be uninsulated and VT-2 examined once each refueling outage while the connections are l at atmospheric or static pressures. The bolted connections will subsequently be examined (afler the insulation is re-installed) during the regularly scheduled system pressure test conducted at nominal operating pressure and at near operating temperature. This re-examination will be conducted no earlier than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reaching nominal system operating pressure.
E2-1
.-s - , - _ .
_..-.m_s.w _
,-,-.,.,,--.r,<- .m 7m_..w-y._,__-__ , . - .,._,y ,m ,r, m. .. . .. --.- -- -
O *
, . Enclosure 2 RR 27 - Unit 2 VI. Justification for Granting Relief: The pressure test with the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time will allow adequate time for any leakage to penetrate the insulation, thereby, prosiding a means of detecting any significant leakage with the insulation in place. Secondly, by removing the insulation each refueling outage, any boric acid residue can be detected. This two-phase approach provides an acceptable level of quality and safety for Class I bolted connections, therefore, the proposed alternative should be authorized pursuant to 10CFR50.50, )(3)(i).
VII. Implementation Schtdyle: This request for reliefis applicable to the updated program beginning Deceraber 1,1997.
Vlli. ReliefjltQuest. Status: This is a new relief request, awaiting NRC approval.
1 i
E2-2