|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 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 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 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) 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 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 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 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 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 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 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents 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 RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation 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 ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARRBG-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 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 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 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 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 05000458/LER-1999-010, Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-05-28028 May 1999 Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in1999-05-26026 May 1999 Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in 05000458/LER-1999-009, Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form1999-05-24024 May 1999 Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl1999-05-14014 May 1999 Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 05000458/LER-1999-007, Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 11999-05-10010 May 1999 Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 1 05000458/LER-1999-006, Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 11999-05-0606 May 1999 Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 1 05000458/LER-1999-005, Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 11999-05-0303 May 1999 Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 1 RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl1999-04-30030 April 1999 Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 9802241999-04-30030 April 1999 Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224 ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested 05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 11999-04-23023 April 1999 Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1 RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC1999-04-15015 April 1999 Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl1999-04-0808 April 1999 Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage1999-04-0808 April 1999 Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr1999-03-31031 March 1999 Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed1999-03-25025 March 1999 Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed ML20204G8701999-03-15015 March 1999 Responds to NOV Described in NRC Correspondance to Util ,expressing Disappointment in NRC Determination That AD Wells Deliberately Provided Incomplete & Inaccurate Info to NRC During Meeting on 971015 RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations1999-03-15015 March 1999 Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check1999-03-0505 March 1999 Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air1999-03-0303 March 1999 Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 9912161999-02-25025 February 1999 Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216 RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition1999-02-11011 February 1999 Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition ML20203C4201999-01-25025 January 1999 Submits Denial of NRC Request for Advance Info Re Concerns Raised by Ucs in 10CFR2.206 Petitions on River Bend & Perry Plants.Petitioners Were Not Required to Provide NRC with Info in Advance of Informal Public Hearings 1999-09-09
[Table view] |
Text
f.
Entergy oper"tions,Inc.
~^~ Rrver Bond ctation 54u5 U, S Hghway 61 PO. Box 220 -
Fax J04 G35 5068 Rick J. King t Safety & Degulatory Affaas January 6,1998 U.S. Nuclear Regulatory Commission Document Control Desk, OPI-17 Washington, DC 20555
Subject:
River Bend Station - Unit I Docket No. 50-458 License No. NPF-47 Request for Relief from ASME Code Section XI Inservice Testing Requirements File Nos.: G9.5, G12.5.2 RBF1-98-0002 RBG4i339 Ladies and Gentlemen: ;
Pursuant 10CFR50.55a(f)(5)(iii), River Bend Station (RBS) requests relief from certain ASME Code,Section XI, Inservice Testing (IST) requirements for the second :0-year interval which began December 1,1997. The requests for reli;f are attacled for cases where full compliance with the ASME Code,Section XI, requirements is not practical in accordance with 10CFR50.55a(f)(6)(i). Because testing in accordance with the code is not pratical, alternative testing is conducted to provide adequate assurance of the operational readiness of the affected components.
The three cases concern the following requirements:
PRR-001 ASME/ ANSI OMa-1988, Part 6, Palagraph 4.6.4(b): Pump vibration measurement 1
.VRR-001 ASME/ ANSI OMa-1988, Part 10, Paragraph 4.2.1.4: Valve stroke time measurement VRR-002 - ASME/ ANSI OMa-1988, Part 10, Paragraph 4.3.2.4(b): Valve obturator movement 99011300e9 900106 '
yDR ADOCK 03000458 PDit ,
w<
Request for Relief ffom ASME Section XI Inservice Testing Requirements
- January 6,1998 ' ,
. RBF1-98M2 '
RBO-44339 - ,
Page 2 of 3 ;
. ! These requests for relief have been prepared utilizing guidance established in NUREG-1482, ,
- Guidelines for Inservice Testing at Nuclear Power Plants," Section 2.5, RBS has included L l the proposed alternative testing in the current IST program plan which became effective !
December 1,1997 and which was submitted to the NRC in a letter dated December 2,1997.
. Approval of these relief requests is req'acsted by September 1,1998. [
Please note that two of the attached relief req" 's were previously approved by the NRC_ for.
the first 10-year interval. Attached relief request PRR-001 was approved as indicated in the
.NRC letter to EOI dated April 28,1997 (reference TAC No, M97705). --VRR-001 was
- approved as indicated in the NRC letter to EOI dated November 24,1995 (reference TAC No.
M90975).
Should you have any questions or need any additional information, please contact Rick.
McAdams at (504) 336-6224.
Sincerely,
'l .
RJK\RM p attachments i
_.-m U'- +- -. ,w b , , y
=l
- Request for' Relief from ASME Section XI Inservice Testing Requirements.
' January 6,' 1998 .
- RBF1-98-0002,
- RBO-44339 :
' Page 3 of 3 cc: -Mr. Davia L. Wigginton U.' S. Nuclear Regulatory Commission .
- M/S OWFN 1311-3 Washington, DC 20555 NRC Resident Inspector P. O. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Department of Environmental Quality.
- Radiation Protection Division P. 0.' Box 82135 Baton Rouge, LA 70884-2135 Attn: Administrator L
i
< - River Bend Stetion insewice Testing Plan for Pumps and Velves Interval 2, Revision 0 j f y i .
REQUEST FOR RELIEF VRR 001 Code ComponentID Class Category Descripton SYSTEM:109 MSS MAIN 8 TEAM GE CODE: 8 21 B21 RVF041 A 1 BC MAIN STEAM LINE A PRESSURE RELIEF VALVE B21 RVF0418 1 BC MAIN STUAM LINE B AUTO DEPRESSURIZATION SYSTEM PRESSURE RELIEF VALVE B21 RVF041C 1 BC MAIN STEAM LINE C AUTO DEPRESSURIZATION SYSTEM PRESSURE RELIEF VALVE B21 RVF041D 1 BC MAIN STEAM LINE D AUTO DEPRESSURIZATION SYSTEM ' ~
PRESSURE RELIEF VALVE B21 RVF041F 1 BC MAIN STEAM LINE B PRESSURE RELIEF VALVE B21 RVF0410 1 BC MAIN STEAM LINE C PRESSURE RELIEF VALVE B21 RVF041L 1 BC MAIN STEAM LINE C PRESSURE RELIEF VALVE B21 RVF047A 1 BC MAIN Gif.AM LINE A AUTO DEPRESSURIZATION SYSTEM PRE *.SURE RELIEF VALVE B21 RVF047B 1 BC MAIN STEAM LINE B PRESSURE RELIEF VALVE B21 RVF047C 1 BC MAIN STEAM LINE C AUTO DEPRESSURIZATION SYSTEM PRESSURF RELIEF VALVE B21 RVF047D 1 BC MAIN STEAM LINE D PRESSURE RELIEF VALVE B21 RVF047F 1 BC MAIN STEAM LINE B PRESSURE RELIEF VALVE B21 RVF051B 1 BC MAIN STEAM LINE B PRESSURE RELIEF VALVE B21 RVF051C 1 BC MAIN STEAM LINE C PRESSURE RELIEF VALVE B21 RVF051D i BC MAIN STEAM LINE D PRESSURE RELIEF VALVE B21 RVF0510 1 BC MAIN STEAM LINE C AUTO DEPRESSURIZATION SYSTEM PRESSURE RELIEF VALVE IEST REQUIREMENT: Stroke time measurement in accordance wth ASME//NSI OMa-1988, Part 10.
Paragraph 4.2.1.4.
ALTERNATE TFS11NG: No stroke time measurements will be performed. The valves will be full stroke exercise tested in accordance with ASME/ ANSI OMa 1988, Part 10. SRV tailpipe steam flow, reector vessel pressure drop, or indication on the SRV tallpipe acoustic monitor will De used to provido positive indication of valve stroke.
BASIS: The Safety Relief Valves are not equipped with direct position indicat;ng devices.
Additionally, the actual valve stroke times e" on the order of 100 mS. Use of other Indicators of valve position (i.e. acour< attors, telipipt, temperature, vessel pressurs) do not provide the aco ;uired to use the stroke times, which wouki f
1 OF ~
h
.g Qfgy mms.nssuun on..rwe r.een o m ra rum es sna v.r a In%N.I2, M M 0
's '
REQUEST FOR RELIEF
^
VRR.001 be obtained, for any meaningful use (i.e. degradation trencing). The proper valve stem movement during actuation is verif6ed during perbdie shop testing.
Modi 6 cation of the valves to provide direct position indication would be costly and would not provide a compensating increase in the level of safety gained by the availabMy of stroke tirne measurements.
REFERENCESj RBC 40430 APPROVALt Pending NRC approval.
Relief prev 60usly granted (as VRR 72) on 11/24/95 in NRC Safety Evaluation Report ( ' ,
TAC No. M90975 ). Principal Contributor: M. Khannis 2 OF 2 l
MIver nond stodon Insuvico reanne Men for pumpe and vooves o
.m Intwvel2, novision 0 e;
m94 '
REQUEST FOR RELIEF l - - VRR 002 Code 1 Component ID Class Category Description l
SYSTEM: 203 CsH . HIGH PRESSURE CORE SPRAY (HPCs) GE CODE: Ett :
E22 AOVF005 1 AC HIGH PRESSURE CORE SPRAY PUMP DISCHARGE HEADER CHECK VALVE INSIDE DRYWELL Code ComponentID Class Category Descripton
^
SYSTEM: 204 . 'tHS . RESIDUAL HEAT REMOVAL LPCI(RHR) GE CODE: E12 E12 AOVF041A 1 AC RESIDUAL HEAT REMOVAL PUMP A INJECTION LINE TESTABLE CHECK VALVE E12 AOVF041B 1 AC RF.SIDUAL HEAT REMOVAL PUMP B INJECTION LINE TESTABLE CHECK VALVE E12 nvVF041C 1 AC RESIDUAL HEAT REMOVAL PUMP C INJECTION LINE TESTABLE CHECK VALVE Code ComponentID Class Category Descripton GE CODE: E21 SYSTEfA: 204 - CSL LOW PRES 8URE CORE SPRAY (LPCS)
E21 AOVF006 1 AC LOW PRESSURE CORE SPRAY PUMP INJECTION INSIDE DRYWELL CHECK VALVE Code ComponentID Class Category Description REACTOR CORE ISOLATION COOUNG (RCIC) GE CODE: E51 SYSTEM: 209 . ICS E51 AOVF065 1 AC REACTOR CORE ISOL COOLING PUMP DISCHARGE LINE OUTBOARD TESTABLE CHECK VALVE E51 AOVF066 1 AC REACTOR CORE ISOL COOLING PUMP DISCHARGE LINE INBOARD TESTABLE AOV CHECK VALVE TEST REQUIREMENT: Valve otturator movement in accordance with ASME/ ANSI OMa-1988, Part 10, Paragraph 4.3.2.4(b).
1 OF 2
. ,A Mwer Sand Semelen Anservfoe Tesehe Man fler Ptdague anetskea snearvei2, neweseen e
.H. '"'ypfergy REQUEST POR REUEF
- W M 02 4 ALTERNATE TESTING: Otiturator movement for the listed valves wiu be demonstrated in accordance wth the 1980 Edition of the A8ME Boller and Pressure Vessel Code,Section XI, Paragraph IWV.3522(b), as follows:
l A mechanical exerciser shot be used to move the disk. The force at torque detNered i 4
F to the disk by the exerciser wlN be limited to less than 10% of the equNeierd force or 4 torque represented by the minimum emergency condibon pressure differential acting l on the disk, or to 200% of the octual observed force or torque required to perform the !
erorcise on the veno when the veno is new and in good operating condtion, . !
)
whi.ever is iess.
l l The force or torque required to full stroke eneroise me listed veNes to the open potition wiu be measured. s :
i Mggi Demonstration of volve otiturator movement in accordance with Part 10, Paragraph l 4.3.2.4(b) may not provide adequate assurance of salve operational readiness for check vanes other than vacuum breakers. Measurement of the force or torque y l required to initiate movement (breakaway) may Nt be suf#clent to vertfy that the listed valves are capable of stroking to their open safety posinen. Valve binding in exooss of acceptable limits may occur at obturolor posioons beyond the point of initial ,
movement. This mode of valvo degradation would not be identitled by the procedurs !'
spoolAed in Part 10, Paragraph 4.3.2.4(b).
i The heted valves no kmger have air actuators connected to the valves. Therefore, the .
l '
valve actuators cannot be used to perform the Code required exercise testing.
Exercising the listed volves wth tow would require using the Emergency Core Cooling System (ECCS) pumps to inject water into the reactor due to the relatively high accident 50w rates rcoulrod for fuu stroke exercising of the veNes. Additionally, the -
injecuon une nozzles at.sociated wth the Residual Hsal Removal System are not 1
og Jipped with intomal spargers. General Electric Servios information Letter 401 identines problems wth injecong water through this flow path and the potenusi i
l damage to nuoloar instrumentation or fuel assonibiles which could occur if this flow -
path were used for other than emergency conditions. For those reasons performing the Code required check volve exercise testing with tow creates a hardship without providing a compensating increase in the level of qualty or safety. .
Pari 10 sino atows check valve disassornbly at refuenng outages as an aNemative to ,
the veno obturetor movement describt d in Paragraphs 4.3.2.4(a) or (b). However, ched volve disassembly is not a proftcod altomalNo.
The inroposed allemate testing is in .coordance wth a previously approved edition of the A8ME Woller and Pressure Voi / el Code and wel provide an acceptable level of E
quaty and safety. .
REBRENCES; NUREG 1482, Appendix A, Question Group 3 ,
. APPflM
+
Pending NRC approval. ,
t 2 OF 2
nIver send stetron Iru srvice TeneMy Men for Pumps and Velves Intervel2, Revision 0
, g
,. REQUEST FOR RELIEF ,
PRR 001 Code Component 10 Cians Description OE CODE:
SYSTEM: 266 SWP SERVICEWATER. STANDBY (SSW)
SWP P2A 3 STANDBY SERVICE WATER PUMP A !
SWP P2B 3 STANDBY SERVICE WATER PUMP B SWP P2C 3 STANCBY SERVICE WATER PUMP C SWP P2D 3 STANDBY SERVICE WATER PUMP D Code ComponentID Class Description DIESEL GENERATOR FUEL OR. OE CODE:
SYSTEM: 309 . EOF EGF P1A 3 STANDBY DIESEL GENERATOR FUEL OIL TRANSFER PUMP A EGF P1B 3 STANDBY DIESEL GENERATOR FUEL OIL TRANSFER PUMP B EGF Pic 3 STANDBY DIESEL GENERATOR FUEL OIL TRANSFER PUMP C TEST REQUIREMENT: ASME/ ANSI OMa 1988, Part 6, Paragraph 4.6.4 (b), *0n verticalline shaft pumps, measurements shall be taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction."
ALTERNATE TESTING: Vibration measurements will be taken in three orthogonal directions in a location that provides valid indica.cn of motor vibratory motion in close proximity of the upper motor bearing housing.
On the standby serue water pumps the upper measurements will be taken on a lifting lug that is integral to the motor stator housing. The lifting lug is structurally rigid and provides transmissibility of the motor vibratory motion. The vibration measurements will be taken in three orthogonal directions on the lifting lug.
On the diesel fuel oil transfer pumps the upper measurements will be taken on the motor stator housing which is rigidly connected to the motor bea ing housing. The vibration measurements will be taken in three directions on the motor stator in close proximity to the motor bearing housing, BASIS: The standby service water pump motors are totally enclosed, weather proof induction motors that are equipped with housing covers which completely enshroud the upper motor bearing housing. The housing cover precludes vibration measurements imm being taken directly on the upper bearing housing.
The diesel fuel oil transfer pt mps are also equipped with housing covers that preclude vibration measurements from being taken directly on the upper motor bearing housing.
1 OF 2 i
,
- y' MNor Bend Station innerdce Testing Men for Pumps and Vekes j
$,%W g.. Intervel2, Movision 0
< ,e .fW
~
REQU5ST FOR REL!EF PRR 001 Removing the upper motor bearing housing eovers for routine vibration readings would
[
compromise the design configuration and the operation of the pump motors. Cooling.
thermocouples and other motor sensors would be disabled. Also, the test
~
- configuration would ddfor grestry from normel configuration which would invalidate the test data obtained to prove operationalreadiness of the pump. This option is not practical.
Moddying the upper bearing housing cover to include an access port or installing vibration sensors is not preferred since these methods would change component configuration wthout a compensating increase in safety. The transmission path P,r the anomate vibration points will not attenuate the vibration response or amplMude, therefore providing equhralent data without disturbing the equipment operation or - -
design.
Therefore, the allemative testing proposed would provide adequate indication of component condition te vertfy operational readiness.
REFERENCES:
RBF196 0459 ,
RBF197 0191 RSC-47600 APPROVAL: Pending NRC approval.
Relief previously granted (as PRR 006) on 4/28/97 in NRC Safety Evaluation Report (TAC No. M97705). Principal contributor: Joseph Coleccino.
2 OF 2
January 15,1998 NOTE TO: Duplicating & Copying Section Staff FROM: Gene R. Wood, Section Chief Duplicating & Copying
SUBJECT:
NEW PAY SCALE Attached you wi:1 find a copy of the pay scale reflecting the cost of living increase that went into effect on October 12,1997. I talked with Kathy Schmitt in Human Resources yesterday and she faxed me the cepy attached She also told me that the increase should be reflected on the check you receive on January 27th, She also advised me that payroll was in the process of calculating the retroactive pay from October 12th, She said they may have this ready for the check on January 27th, but most likely we will not see this until the check of February 10,1998, if you have any questions regarding the pay scale or the retroactive pay, please let me know.
h t. o ood Gene R. Wood, Section Chief Duplicating & Copying Section
f AF Wage Schedules httpdAnnv.cpms.csd. mil / wage /scheds/afsu:vey-sch!O27/1119027P.html '
u~
-AC-0027P DoD Civilian Personnel Management Service (AW) p
^
Arlington, Virginia 22209-5144 Issue Date: 19 Wyeober 1997 .
sa t.
SUBJEC1: Federal Wage System Special Printing' Schedules for Printing and Lithographic Occupations ,
for' the Washingtors, District >f Columbia wage Area g To: Cow.anding Officers of Military Deparu=ents mal ovu emeeut Austallations in the Area o t'
r.
The schedules shown belcw have been established under authority of DoD Directive 5120.39, dated ba 19ril 24, 1980, subject to the limitations contained in OPM Notice No. 97-52, dated 17 November 1997, y and are to be applied in accordance with the provisions of 5 CFR Part 532 to all etcployees whose 'S official. duty station is located within the geographic boundary of the wage area definition shown to on the reverse side.
4
.IP XD-XN XL-XS XP-Rates XL-Rates XS-XD-XN Rates Pay Grade 1 2 3 1 2 3 1 2 3 Level 1 8.36 8.71 9.06 9.21 9.55 9.97 13.94 14.52 15.10 2 9.49 9.89 1C.29 10.44 10.88 31.32 14.80 15.42 16.05 3 10.43 10.85 11.32 11.48 11.98 12.45 15.54 16.20 16.86 1 4 11.36 11.84 12.33 12.54 13.07 13.61 16.50 17.18 17.88 2 5 12.30 12.81 13.35 13.52 14.09 14.68 17.57 18.30 19.02 3 ,
d 6 13.33 13 .88 14.45 14.66 15.26 15.89 18.67 19.45 20.23 4 7 14.45 15.05 15.65 15.89 16.55 17.21 20.03 20.86 21.69 51 8 15.86 16.52 17.18 17.44 18.17 18.90 21.51 22.41 23.31 62 9 17.35 18.07 18.79 19.08 19.88 20.68- 23.00 23.96 24.92 73 10 18.44- 19.62 20.40 20.72 21.58 22.44 24.49 25.51 26.53 84 11 20.32 21.17 22.02 22.36 23.29 24.22 24.74 25.77 26.80 95 12 21.81 22.72 23'.63 23.99 24.99 25.99 25.08 26.12 27.16 10 6 13 23.31 24.28 25.25 25.64 26.71 27.78 25.49 26.55 27.61 11 7 14 24.80 25.83 26.86 27.27 28.41 29.55 25.97 27.05 28.13 8 15 26.28 27.38 28.48 28.92 30.12 31.32 26.82 27.94 29.06 9 XS-16 28.20 29.38 30.56 XS-17 29.31 30.53 31.75 XS-18 30.52 31.79 33.06 XS-19 31.84 33.17 34.50 BARBARA L. KELLY Order Date: 5 August 1997 ,
Chief Effective Date: 12 Octcber 1997 Wage Setting civision Supersedes Schedule Issued 3 December 1996
~ . . . . - . . , .-_. - - , _ _ _ . ._. . . - _ - - , . . . . . - _ _ . _ - . _ _