Letter Sequence RAI |
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TAC:M95814, (Approved, Closed) TAC:M95815, (Approved, Closed) TAC:M95816, (Approved, Closed) TAC:M95829, (Approved, Closed) TAC:M95830, (Approved, Closed) TAC:M95832, (Approved, Closed) TAC:M95874, (Approved, Closed) TAC:M95875, (Approved, Closed) TAC:M95876, (Approved, Closed) TAC:M96099, (Approved, Closed) TAC:M96100, (Open) TAC:M96101, (Open) TAC:M96102, (Open) TAC:M96103, (Open) TAC:M96104, (Open) |
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MONTHYEARML20136G0511997-03-13013 March 1997 Forwards Request for Addl Info Re Use of ASME Code Cases N-508-1,N-509-,N-524 & 5-46 Project stage: RAI ML20199F4921997-11-19019 November 1997 Forwards Safety Evaluation Accepting Licensee 960620,970114, 0512 & 0729 Requests for Relief from Requirements of Section XI of ASME Boiler & Pressure Vessel Code for Current or New 10-yr Inservice Insp Interval Project stage: Approval 1997-11-19
[Table View] |
Forwards Request for Addl Info Re Use of ASME Code Cases N-508-1,N-509-,N-524 & 5-46ML20136G051 |
Person / Time |
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Site: |
Grand Gulf, Arkansas Nuclear, River Bend, Waterford |
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Issue date: |
03/13/1997 |
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From: |
Donohew J NRC (Affiliation Not Assigned) |
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To: |
Hagan J ENTERGY OPERATIONS, INC. |
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References |
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TAC-M95814, TAC-M95815, TAC-M95816, TAC-M95829, TAC-M95830, TAC-M95832, TAC-M95874, TAC-M95875, TAC-M95876, TAC-M96099, TAC-M96100, TAC-M96101, TAC-M96102, TAC-M96103, TAC-M96104, NUDOCS 9703170178 |
Download: ML20136G051 (8) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy 1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 ML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations 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 ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV 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 ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 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 ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities 1999-09-09
[Table view] |
Text
. . ~ . . . . . - - - . - - . .. _ . - -
s i !
i Mr. Joseph J. Hagan March 130 1997
, ,_ Vice President, Operations GGNS
+ Entergy Operations, Inc.
I P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
REQUEST FOR ADDITIONALEINFORMATION RELATED TO USE OF ASME CODE CASES N-508-1, N-509, N-524, AND 5-46, ARKANSAS NUCLEAR ONE, UNITS 1 AND 2, GRAND GULF NUCLEAR STATION, RIVER BEND STATION, AND WATERFORD 3 STEAM ELECTRIC STATION (TAC NOS. M96102, M96101, M95816, i M95830, M95876, M96104, M96103, M95815, M95832, M95875, M96100, M96099, M95814, M95829, AND M95874)
Dear Mr. Hagan:
i The staff is continuing its review of your submittals dated June 20, 1996, and January 14, 1997, for approval of American Society of Mechanical ,
1 Engineers Boiler and Pressure Vessel Code (ASME Code) Cases N-508-1, N-509, N-524, and N-546 for the following Entergy plants: Arkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, River Bend Station, and Waterford 3 Steam Electric Station. To permit us to continue our review on our current schedule we require that the information requested in the enclosure be provided within 60 days of your receipt of this letter.
NRC FRE GBHEh GUPY 1 -
6 ack . Donohew, Senior Project Manager
' Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-313, 50-368, 50-416, 1 50-458, and 50-382 l cc: See next page DISTRIBUTION:
Docket File PUBLIC PD4-1 r/f C. Patel J. Roe E. Adensam (EGA1) J. Donohew G. Bagchi J. Dyer, RIV ACRS OGC (15B18) G. Kalman C. Hawes W. Beckner T. McLellan D. Wigginton Document Name: ASMECODE.RAI 0FC PM/PS-k LA/PD4-1 NAME JDon N vw CHawes 0(n H 9 9D ,i DATE '3 /l$97 3 /)D/97 COPY M NO YES/NO OFFIEIAL RECORD COPY D Dbck050$0S13 P PDR
l s
s creo g 4 UNITED STATES s* j 2
NUCLEAR REGULATORY COMMISSION WASHINoTON, D.C. 20066 4 001 4
9 * * * * * ,o March 13, 1997 Mr. Joseph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO USE OF ASME CODE CASES N-508-1, N-509, N-524, AND 5-46, ARKANSAS NUCLEAR ONE, UNITS 1-AND 2, GRAND GULF NUCLEAR STATION, RIVER BEND STATION, AND WATERFORD 3 STEAM ELECTRIC STATION (TAC NOS. M96102, M96101, M95816, l M95830, M95876, M96104, M96103, M95815, M95832, M95875, M96100, 1 M96099, M95814, M95829, AND M95874)
Dear Mr. Hagan:
The staff is continuing its review of your submittals dated June 20, 1996, and January 14, 1997, for approval of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Cas6s N-508-1, N-509, N-524, and N-546 for the following Entergy plants: Arkansas Nuclear One, l Units 1 and 2, Grand Gulf Nuclear Station, River Bend Station, and Waterford 3 Steam Electric Station. To permit us to continue our review on our current schedule we require that the information requested in the enclosure be provided within 60 days of your receipt of this letter.
Sincerely, 4
M. V Jac N. Donohew, Senior Project Manager j Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-313, 50-368, 50-416, 50-458, and 50-382 cc: See next page
Mr. Joseph J. Hagan Entergy Operations, Inc. Grand Gulf Nuclear Station ec:
Executive Vice President General Manager, GCNS
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Sox 756 P. O. Box 31995 Port Gibson, MS 39150 Jackson, MS 39286-1995 Attorney General Wise, Carter, Child & Caraway Department of Justice P. O. Box 651 State of Louisiana Jackson, MS 39205 P. O. Box 94005 Baton Rouge, LA 70804-9005 Winston & Strawn 1400 L Street, N.W. - 12th Floor State Health Officer Washington, DC 20005-3502 State Board of Health P. O. Box 1700 Director Jackson, MS 39205 Division of Solid Waste Management Mississippi Department of Natural Office of the Governor Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 Jackson, MS 39209 Attorney General President, Asst. Attorney General Claiborne County Board of Supervisors State of Mississippi Port Gibson, MS 39150 P. O. Box 22947 Jackson, MS 39225 Regional Administrator, Region IV i U.S. Nuclear Regulatory Commission Vice President, Operations Support l 611 Ryan Plaza Drive, Suite 1000 Entergy Operations, Inc. l Arlington, TX 76011 P.O. Box 31995 l Jackson, MS 39286-1995 l Senior Resident Inspector l U. S. Nuclear Regulatory Commission Director, Nuclear Safety l Route 2, Box 399 and Regulatory Affairs l Port Gibson, MS 39150 Entergy Operations, Inc. 1 P.O. Box 756 l Manager of Operations Port Gibson, MS 39150 '
Bechtel Power Corporation P.O. Box 2166 l Houston, TX 77252-2166 '
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l 1 . Entergy Operations, Inc. Arkansas Nuclear One, Units 1 & 2 )
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Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 1
Director, Division of Radiation Wise, Carter, Child & Caraway
- Control and Emergency Management P. O. Box 651 1 Arkansas Department of Health Jackson, MS 39205 1 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Mr. C. Randy Hutchinson
- Vice President Operations, AN0 ,
Entergy Operations, Inc. I Winston & Strawn 1448 S. R. 333
. 1400 L Street, N.W. Russellville, AR 72801 ;
- Washington, DC 20005-3502 ;
, l Manager, Rockville Nuclear Licensing l Framatone Technologies 1700 Rockville Pike, Suite 525 l Rockville, MD 20852 Senior Resident Inspector - '
U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional. Administrator, Region IV i
U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County
- Pope County Courthouse
- Russellville, AR 72801 9
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l Entergy Operations, Inc. River Bend Station cc:
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Winston & Strawn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer
- Washington, DC 20005-3502 Entergy Operations, Inc.
P. O. Box 31995 Manager - Licensing Jackson, MS 39286 Entergy Operations, Inc.
River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.
St. Francisville, LA 70775 River Bend Station P. O. Box 220 ,
Director St. Francisville, LA 70775 l Joint Operations Cajun 1 10719 Airline Highway Director - Nuclear Safety l P. O. Box 15540 Entergy Operations, Inc.
Baton Rouge, LA 70895 River Bend Station P. O. Box 220 Senior Resident Inspector St. Francisville, LA 70775 P. O. Box 1050 St. Francisville, LA 70775 Vice President - Operations Support Entergy Operations, Inc.
President of West Feliciana P. O. Box 31995 Police Jury Jackson, MS 39286-1995 P. O. Box 1921 St. Francisville, LA 70775 Attorney General State of Louisiana Regional Administrator, Region IV P. O. Box 94095 ,
U.S. Nuclear Regulatory Comission Baton Rouge, LA 70804-9095 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Wise, Carter, Child & Caraway P. O. Box 651 Ms. H. Anne Plettinger Jackson, MS 39205 3456 Villa Rose Drive Baton Rouge, LA 70806 Vice President & Controller Cajun Electric Power Cooperative i Administrator 10719 Airline Highway Louisiana Radiation Protection Division P.O. Box 15540 P. O. Box 82135 Baton Rouge, LA 70895 Baton Rouge, LA 70884-2135 Mr. John R. McGaha '
Vice President - Operations Entergy Operations, Inc.
River Bend Station P.O. Box 220 St. Francisville, LA 70775
. Entergy Operations, Inc. Waterford 3 i
cc:
Administrator Regional Administrator, Region IV Louisiana Radiation Protection Division U.S. Nuclear Regulatory Commission Post Office Box 82135 611 Ryan Plaza Drive, Suite 1000
) Baton Rouge, LA 70884-2135 Arlington, TX 76011 i Vice President, Operations Resident Inspector /Waterford NPS 2
Support Post Office Box 822 Entergy Operations, Inc. Killona, LA 70066 P. O. Box 31995 Jackson, MS 39286 Parish President Council i
St. Charles Parish Director P. O. Box 302
. Nuclear Safety & Regulatory Affairs Hahnville, LA 70057 Entergy Operations, Inc.
P. O. Box B Executive Vice-President i Killona, LA 70066 and Chief Operating Officer Entergy Operations, Inc.
Wise, Carter, Child & Caraway P. O. Box 31995
- P. O. Box 651 Jackson, MS 39286-1995
! Jackson, MS 39205 i Chairman General Manager Plant Operations Louisiana Public Service Commission Entergy Operations, Inc. One American Place, Suite 1630 P. O. Box B Baton Rouge, LA 70825-1697 Killona, LA 70066 l
Licensing Manager Vice President Operations Entergy Operations, Inc. Entergy Operations, Inc.
P. O. Box B P. O. Box B Killona, LA 70066 Killona, LA 70066 Winston & Strawn 1400 L Street, N.W.
e Washington, DC 20005 1702 1
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REQUEST FOR ADDITIONAL INFORMATION
- REQUEST FOR AUTHORIZATION TO USE CODE CASES N-509. N-524 AND N-546 1
ENTERGY OPERATIONS. INC.
ARKANSAS NUCLEAR ONE. UNITS 1 AND 2. DOCKET NO.S 50-313 AND 50-368 I
- GRAND GULF NUCLEAR STATION UNIT 1. DOCKET NO. 50-416 l RIVER BEND STATION. DOCKET NO. 50-458 l
! WATERFORD 3 STEAM ELECTRIC STATION. DOCKET NO. 50-382 i
- 1. INTRODUCTION i In accordance with 10 CFR 50.55a(c)(3), 10 CFR 50.55a(d)(2), and i 10 CFR 50.55a(e)(2), ASME Code cases may be used as alternatives to Code j 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 deemed necessary by the NRC. Code cases i nel referenced in Regulatory Guide 1.147 may be adopted only if i authorized by the NRC on a case-by-case basis. In some cases, use of
- unapproved Code cases may be acceptable for use when certain conditions
. are included. To ensure consistent implementation, licensees proposing 4 the use of currently unapproved Code case (s), must commit to such
! conditions, if applicable.
i In three letters dated June 20, 1996, the licensee proposed the use of Code Cases N-509, N-524 and N-546 in lieu of the Code requirements. In a
- letter dated January 14, 1997, the licensee submitted supplemental
! information regarding the submittals. The information provided by the l licensee in these submittals has been reviewed by the NRC staff.
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- 2. Additional Information Reauired i
l Based on the above review, the staff has concluded that the following
! information and/or clarification is required to complete the licensee's
! submittals.
, A. Pursuant to 10 CFR 50.55a(a)(3)(i), the licensee proposed to use i Code Case N-509, " Alternative Rules 'for the Selection and
- i. Examination of Class-1, 2, and 3 Integrally Welded Attachments,"
4 Section XI, Division 1 in lieu of the Code selection requirements
- for integrally welded attachments. To find Code Case N-509 acceptable for use, the staff has determined that a minimum
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4 examination sample of 10% of the total number of integral i attachments in all non-exempt Class 1, 2, and 3 piping, pumps and i valves is necessary. Confirm that this condition will be met.
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i ENCLOSURE
e B. Pursuant to 10 CFR 50.55a(a)(3)(1), the licensee proposed the use of l Code Case N-546, " Requirements for Qualification of VT-2 Examination Personnel, Section XI, Division 1." To find this Code case acceptable for use, the staff has determined that the following l conditions must be met: Licensee's must 1) develop procedural guidelines for obtaining consistent, quality VT-2 visual :
examinations, 2) document and maintain records to verify the l qualification of persons selected to perform VT-2 visual examinations, and 3) implement independent review and evaluation of '
detected leakage by persons other than those that performed the VT-2 visual examinations. Confirm that these conditions will be met.
i The schedule for timely completion of this review requires that the licensee provide, by the requested date, the above requested
. information and/or clarifications regarding the proposed alternatives for the subject Entergy plants.
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