|
|
(One intermediate revision by the same user not shown) |
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE,'ROCHESTER N.Y.14649.0001 ROBERT C MECREOY Vice President clnna Nuclear production September 30, 1992 TELEPHONE nstEa, cooE T is 546-2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson PWR Project Directorate I-3 Washington, D.C.20555 | | {{#Wiki_filter:ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, 'ROCHESTER N. Y. 14649.0001 ROBERT C MECREOY TELEPHONE Vice President cooE T is 546-2700 clnna Nuclear production September 30, 1992 nstEa, U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson PWR Project Directorate I-3 Washington, D.C. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Status of Actions in Response to SWSOPX Violations, Deficiencies, and Unresolved Items Xnspection Report 50-244/91-201 R.E.Ginna Nuclear Power Plant Docket No.50-244 | | Status of Actions in Response to SWSOPX Violations, Deficiencies, and Unresolved Items Xnspection Report 50-244/91-201 R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
|
| |
|
| ==Dear Mr.Johnson,== | | ==Dear Mr. Johnson,== |
| In Reference (a)RG&E committed, by the end of the third quarter 1992, to provide an updated status of RG&E actions taken or planned irn response to the items identified in Appendix A of Reference (b).Appendix A of Reference (b)identified a total of 15 items;4 were identified as Deficiencies, 5 were identified as Unresolved items, and 6 were identified as Observations. | | |
| Three, of.these resulted in Violations as documented in Reference (c).Since.the issuance of Reference (b)and the subsequent Notice of Violations, Reference (c), RG&E has expended a significant effort toward resolution of the open issues identified during the SWSOPI Team Xnspection. | | In Reference (a) RG&E committed, by the end of the third quarter 1992, to provide an updated status of RG&E actions taken or planned irn response to the items identified in Appendix A of Reference (b) . |
| As acknowledged by the NRC in Reference (c), all identified items, weaknesses, and observations related to the SWSOPI're being tracked in our Commitment and Action Tracking System to.assure formal resolution of these matters.Since the completion of the team inspection, RG&E has been tracking the progress of 62 COmrtlitmentS Oi aCticn itesssS reSulting direCt j frOm tahe SWSOPX Or related to it.Currently, 35 of these have been closed by RG&E and 27 remain open in, various stages of completion. | | Appendix A of Reference (b) identified a total of 15 items; 4 were identified as Deficiencies, 5 were identified as Unresolved items, and 6 were identified as Observations. Three, of. these resulted in Violations as documented in Reference (c). Since .the issuance of Reference (b) and the subsequent Notice of Violations, Reference (c), RG&E has expended a significant effort toward resolution of the open issues identified during the SWSOPI Team Xnspection. |
| In addition, during the week of August 17, 1992, NRC staff performed a follow-up inspection during which RG&E provided information and status of RG&E actions for the three violations (91-201Ž01, 91-201-11, and 91-201-14) and two of the unresolved items (91-201-04 and 91-201-15).Since NRC documentation of the results of.thatinspection (designated 50-244/92-012) has not as yet, been received, this letter provides the status of all the 15 deficiencies, unresolved items, and observations identified in Appendix A of Reference (a).('Tt210210045 921016 PDR ADOCK 05000244 8 ,'PDR ATTACHMENT A In response RG&E committed to 1)evaluate/test, the diesel generator cooler performance and determine the optimum flow[R01958];2)enhance the analytical modeling and capability of the existing hydraulic model so that an analytical basis and test specification for the re-balance of the SWS is available prior to the 1993 refueling outage[R01959];and 3)conduct testing as required during the 1993 outage to confirm the analytical results of the enhanced model and to set optimal flows"for each SW cooler so that.the SWS flow balance will be optimized when the plant returns to power following" the 1993 outage.[R01960]In a lett~~, Reference,(d), RG&E indicated that the existing service water s'st: em flow balance to the emergency diesel generator coolers was satisfactory and that no change was warranted at this time, however, the overall SWS flow balance continues;.to be planned for the 1993 outage.In addition, by Reference (e)RG&E committed to perform pilot thermal performance testing of the diesel generator coolers during the summer of 1992 based upon the existing system instrumentation | | As acknowledged by the NRC in Reference (c), all identified items, weaknesses, and observations related to the SWSOPI're being tracked in our Commitment and Action Tracking System to .assure formal resolution of these matters. Since the completion of the team inspection, RG&E has been tracking the progress of 62 COmrtlitmentS Oi aCticn itesssS reSulting direCt j frOm tahe SWSOPX Or related to it. Currently, 35 of these have been closed by RG&E and 27 remain open in,various stages of completion. In addition, during the week of August 17, 1992, NRC staff performed a follow-up inspection during which RG&E provided information and status of RG&E actions for the three violations (91-201'01, 91-201-11, and 91-201-14) and two of the unresolved items (91-201-04 and 91-201-15). Since NRC documentation of the results of. thatinspection (designated 50-244/92-012) has not as yet, been received, this letter provides the status of all the 15 deficiencies, unresolved items, and observations identified in Appendix A of Reference (a). |
| [R02438], evaluate these results[R02440], and commence periodic thermal performance testing during the summer of 1993 to coincide with the highest lake water temperatures | | 'Tt210210045 921016 PDR ADOCK 05000244 |
| [R02439].The'pilot testing has been completed and the results are being reviewed by engineering and plant staff.Page-7}} | | ( 8 , |
| | PDR |
| | |
| | ATTACHMENT A In response RG&E committed to 1) evaluate/test, the diesel generator cooler performance and determine the optimum flow [R01958]; 2) enhance the analytical modeling and capability of the existing hydraulic model so that an analytical basis and test specification for the re-balance of the SWS is available prior to the 1993 refueling outage |
| | [R01959]; and 3) conduct testing as required during the 1993 outage to confirm the analytical results of the enhanced model and to set optimal flows"for each SW cooler so that. the SWS flow balance will be optimized when the plant returns to power following the 1993 outage. [R01960] |
| | In a lett~~, Reference,(d), RG&E indicated that the existing service water s'st: em flow balance to the emergency diesel generator coolers was satisfactory and that no change was warranted at this time, however, the overall SWS flow balance continues;.to be planned for the 1993 outage. |
| | In addition, by Reference (e) RG&E committed to perform pilot thermal performance testing of the diesel generator coolers during the summer of 1992 based upon the existing system instrumentation |
| | [R02438], evaluate these results [R02440], and commence periodic thermal performance testing during the summer of 1993 to coincide with the highest lake water temperatures [R02439]. The |
| | 'pilot testing has been completed and the results are being reviewed by engineering and plant staff. |
| | Page 7}} |
Similar Documents at Ginna |
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] |
Text
ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, 'ROCHESTER N. Y. 14649.0001 ROBERT C MECREOY TELEPHONE Vice President cooE T is 546-2700 clnna Nuclear production September 30, 1992 nstEa, U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson PWR Project Directorate I-3 Washington, D.C. 20555
Subject:
Status of Actions in Response to SWSOPX Violations, Deficiencies, and Unresolved Items Xnspection Report 50-244/91-201 R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
In Reference (a) RG&E committed, by the end of the third quarter 1992, to provide an updated status of RG&E actions taken or planned irn response to the items identified in Appendix A of Reference (b) .
Appendix A of Reference (b) identified a total of 15 items; 4 were identified as Deficiencies, 5 were identified as Unresolved items, and 6 were identified as Observations. Three, of. these resulted in Violations as documented in Reference (c). Since .the issuance of Reference (b) and the subsequent Notice of Violations, Reference (c), RG&E has expended a significant effort toward resolution of the open issues identified during the SWSOPI Team Xnspection.
As acknowledged by the NRC in Reference (c), all identified items, weaknesses, and observations related to the SWSOPI're being tracked in our Commitment and Action Tracking System to .assure formal resolution of these matters. Since the completion of the team inspection, RG&E has been tracking the progress of 62 COmrtlitmentS Oi aCticn itesssS reSulting direCt j frOm tahe SWSOPX Or related to it. Currently, 35 of these have been closed by RG&E and 27 remain open in,various stages of completion. In addition, during the week of August 17, 1992, NRC staff performed a follow-up inspection during which RG&E provided information and status of RG&E actions for the three violations (91-201'01, 91-201-11, and 91-201-14) and two of the unresolved items (91-201-04 and 91-201-15). Since NRC documentation of the results of. thatinspection (designated 50-244/92-012) has not as yet, been received, this letter provides the status of all the 15 deficiencies, unresolved items, and observations identified in Appendix A of Reference (a).
'Tt210210045 921016 PDR ADOCK 05000244
( 8 ,
PDR
ATTACHMENT A In response RG&E committed to 1) evaluate/test, the diesel generator cooler performance and determine the optimum flow [R01958]; 2) enhance the analytical modeling and capability of the existing hydraulic model so that an analytical basis and test specification for the re-balance of the SWS is available prior to the 1993 refueling outage
[R01959]; and 3) conduct testing as required during the 1993 outage to confirm the analytical results of the enhanced model and to set optimal flows"for each SW cooler so that. the SWS flow balance will be optimized when the plant returns to power following the 1993 outage. [R01960]
In a lett~~, Reference,(d), RG&E indicated that the existing service water s'st: em flow balance to the emergency diesel generator coolers was satisfactory and that no change was warranted at this time, however, the overall SWS flow balance continues;.to be planned for the 1993 outage.
In addition, by Reference (e) RG&E committed to perform pilot thermal performance testing of the diesel generator coolers during the summer of 1992 based upon the existing system instrumentation
[R02438], evaluate these results [R02440], and commence periodic thermal performance testing during the summer of 1993 to coincide with the highest lake water temperatures [R02439]. The
'pilot testing has been completed and the results are being reviewed by engineering and plant staff.
Page 7