|
|
| (3 intermediate revisions by the same user not shown) |
| Line 1: |
Line 1: |
| #REDIRECT [[IR 05000244/1997012]] | | {{Adams |
| | | number = ML17265A248 |
| | | issue date = 04/24/1998 |
| | | title = Provides Clarification for Several Statements Made in NRC Insp Rept 50-244/97-12 Dtd 980209 |
| | | author name = Mecredy R |
| | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | | addressee name = Vissing G |
| | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | | docket = 05000244 |
| | | license number = |
| | | contact person = |
| | | document report number = 50-244-97-12, NUDOCS 9805060235 |
| | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
| | | page count = 4 |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:CATEGORY j. |
| | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:98 05060235 DOC.DATE: 98/04/24 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Rob ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 AUTH. NICE . |
| | ~ AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. |
| | RECIP.NAME |
| | ~ RECIPIENT AFFILIATION VISSING,G.S. |
| | |
| | ==SUBJECT:== |
| | Provides clarification for several statements made in NRC insp rept 50-244/97-12'td 980209. |
| | DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR \ ENCL TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response Z SIZE: |
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ZD CODE/NAME LTTR ENCL PD1-1 PD VISSZNG,G. 0 INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB NRR/DRPM/PECB NRR/DRPM/PERB NUDOCS-ABSTRACT OE DIR OGC/HDS3 RGN1 FILE 01 EXTERNAL: LITCO BRYCE,J H NOAC NRC PDR NUDOCS FULLTEXT D |
| | 0 N |
| | NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL |
| | |
| | April 24, 1998 U. S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
| | |
| | ==Subject:== |
| | Clarification of Statements Made in NRC Inspection Report 50-244/97-12, dated February 9, 1998 Ref . (1) NRC Integrated Inspection Report 50-244/97-12 and Notice of Violation, dated February 9, 1998 (2) Letter from R.E. Smith, RGEE, to NRC, |
| | |
| | ==Subject:== |
| | |
| | ===Response=== |
| | to NRC Request for Information Pursuant to 10CFR50.54(f) |
| | Regarding Adeqacy and Availability of Design Information R.E. Ginna Nuclear Power Plant, dated February 7, 1997 (3) Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,. |
| | |
| | ==Subject:== |
| | Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Adequacy and Availability of Design Basis Information R.E. Ginna Nuclear Power Plant, dated September 30, 1997 (4) Letter from'.C. Mecredy, RG6E, to NRC, |
| | |
| | ==Subject:== |
| | |
| | Submittal of Security Plan revision M, dated July 24, 1997 |
| | |
| | ==Dear Mr. Vissing:== |
| | |
| | This letter is to provide clarification for several statements made in NRC Inspection Report 50-244/97-12. |
| | : 1) Statement: Section E1.3 D v page 14 states "The UFSAR verfication project was scheduled to proceed in parallel with the validation of all other design basis source documents so that an electronic link of these yource documents to a living UFSAR could be accomplished by October 1998 for use during the DBD project." |
| | Clarification: The UFSAR verification project and design basis documentation project are not proceeding in parallel. This was explained in our letter dated September 30, 1997 (Reference 3). The UFSAR verfication and design basis documentation projects use some of the same resources; therefore, it was decided to concentrate on the UFSAR verification project until 9805060235 05000244 980424'DR ADQCK 8 PDR |
| | |
| | April 24, 1998 page 2 October 18, 1998 and then shift additional resources to the design basis documentation project. The links from the UFSAR to the source documents will not be completed until December 2001 as explained in Reference 3. |
| | '2) Statement: Section E1.3 L' n D i n Ba 14 states "With the completion of the service water |
| | 'v'age safety system functional inspection (SSFI) and the NRC design team inspection of Ginna, RG&E noted in the updated response letter of September 30, 1997, that they had completed the commitment to perform two SSFIs in 1997. RG&E indicated that they would perform a SSFI of the AFW system in 1998." |
| | Clarification: RG&E has determined we, should concentrate the majority of our resources on the Design Basis Documentation (DBD) and UFSAR verification projects described above, as closeout of Motor-Operated Valve (GL89-10) and Service well's Water (GL89,-13) issues. Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998. |
| | : 3) Statement: Section ES F 1 V' n -2 Ev T m HQV-4~1 , page 17 states "The inspector noted that the licensee work in compiling a document of all variables used in the UFSAR Accident Analysis chapter was partially complete and was scheduled for completion by March 1, 1998, according in the licensee's Commitment and Action Tracking System to'OS598 (CATS)..." |
| | Clarification: The scope of the compilation of the major variables used in the UFSAR Accident Analysis chapter has been expanded to include additional items, such as accident and analysis assumptions, valve stroke times and setpoints. This |
| | 'r effort is currently scheduled to be completed by June 30, 1998. |
| | Statement: Section E8.2 v I 04 ~ |
| | S rv' m R imiz W page 18 states "In addition to issues related to heat exchanger performance testing and revision of the SWSROP, comments were made regards.ng the need to update the SW system hydraulic flow model since it under predicted flows in some cases. The licensee indicated that this work was being done in-house and was scheduled for completion by the end of January 1998." |
| | Clarification: Additional testing has been performed to better predict flows to the CRFC motor coolers. With the inclusion of this data, the SW system Hydraulic model is expected to be refined by June 16, 1998. |
| | |
| | April Page 5) 3 24, 1998 Statement: |
| | selected barrier Section S3 u 'fe ua d P ur s page 23 states "The inspectors verified that changes to the Plan associated with the vehicle system (VBS), as implemented, did not decrease the effectiveness of the Plan. Discussions with the licensee indicated that the plan was currently being reviewed and a plan revision would be submitted in accordance with the provisions of 10CFR 50.54(p) in the near future." |
| | Clarification: RGRE submitted a Security Plan revision M on July 24, 1997 (Refe'rence 4) which provided enhancement to the VBS. Also, RGGE submitted Security Plan revision N on January 15, 1998 although this revision was not related to the VBS. |
| | Very truly yours, Robert C. Mecredy GJWE498 xc: Mr. Guy S. Vissing (Mail Stop 14B2) |
| | Senior Project Manager Project Directorate I-1 Washington, D.C. 20555 Mr. Hubert J. Miller U. S. Nuclear Regulatory Commission Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}} |
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
CATEGORY j.
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:98 05060235 DOC.DATE: 98/04/24 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Rob ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 AUTH. NICE .
~ AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME
~ RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Provides clarification for several statements made in NRC insp rept 50-244/97-12'td 980209.
DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR \ ENCL TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response Z SIZE:
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ZD CODE/NAME LTTR ENCL PD1-1 PD VISSZNG,G. 0 INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB NRR/DRPM/PECB NRR/DRPM/PERB NUDOCS-ABSTRACT OE DIR OGC/HDS3 RGN1 FILE 01 EXTERNAL: LITCO BRYCE,J H NOAC NRC PDR NUDOCS FULLTEXT D
0 N
NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL
April 24, 1998 U. S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Clarification of Statements Made in NRC Inspection Report 50-244/97-12, dated February 9, 1998 Ref . (1) NRC Integrated Inspection Report 50-244/97-12 and Notice of Violation, dated February 9, 1998 (2) Letter from R.E. Smith, RGEE, to NRC,
Subject:
Response
to NRC Request for Information Pursuant to 10CFR50.54(f)
Regarding Adeqacy and Availability of Design Information R.E. Ginna Nuclear Power Plant, dated February 7, 1997 (3) Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,.
Subject:
Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Adequacy and Availability of Design Basis Information R.E. Ginna Nuclear Power Plant, dated September 30, 1997 (4) Letter from'.C. Mecredy, RG6E, to NRC,
Subject:
Submittal of Security Plan revision M, dated July 24, 1997
Dear Mr. Vissing:
This letter is to provide clarification for several statements made in NRC Inspection Report 50-244/97-12.
- 1) Statement: Section E1.3 D v page 14 states "The UFSAR verfication project was scheduled to proceed in parallel with the validation of all other design basis source documents so that an electronic link of these yource documents to a living UFSAR could be accomplished by October 1998 for use during the DBD project."
Clarification: The UFSAR verification project and design basis documentation project are not proceeding in parallel. This was explained in our letter dated September 30, 1997 (Reference 3). The UFSAR verfication and design basis documentation projects use some of the same resources; therefore, it was decided to concentrate on the UFSAR verification project until 9805060235 05000244 980424'DR ADQCK 8 PDR
April 24, 1998 page 2 October 18, 1998 and then shift additional resources to the design basis documentation project. The links from the UFSAR to the source documents will not be completed until December 2001 as explained in Reference 3.
'2) Statement: Section E1.3 L' n D i n Ba 14 states "With the completion of the service water
'v'age safety system functional inspection (SSFI) and the NRC design team inspection of Ginna, RG&E noted in the updated response letter of September 30, 1997, that they had completed the commitment to perform two SSFIs in 1997. RG&E indicated that they would perform a SSFI of the AFW system in 1998."
Clarification: RG&E has determined we, should concentrate the majority of our resources on the Design Basis Documentation (DBD) and UFSAR verification projects described above, as closeout of Motor-Operated Valve (GL89-10) and Service well's Water (GL89,-13) issues. Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998.
- 3) Statement: Section ES F 1 V' n -2 Ev T m HQV-4~1 , page 17 states "The inspector noted that the licensee work in compiling a document of all variables used in the UFSAR Accident Analysis chapter was partially complete and was scheduled for completion by March 1, 1998, according in the licensee's Commitment and Action Tracking System to'OS598 (CATS)..."
Clarification: The scope of the compilation of the major variables used in the UFSAR Accident Analysis chapter has been expanded to include additional items, such as accident and analysis assumptions, valve stroke times and setpoints. This
'r effort is currently scheduled to be completed by June 30, 1998.
Statement: Section E8.2 v I 04 ~
S rv' m R imiz W page 18 states "In addition to issues related to heat exchanger performance testing and revision of the SWSROP, comments were made regards.ng the need to update the SW system hydraulic flow model since it under predicted flows in some cases. The licensee indicated that this work was being done in-house and was scheduled for completion by the end of January 1998."
Clarification: Additional testing has been performed to better predict flows to the CRFC motor coolers. With the inclusion of this data, the SW system Hydraulic model is expected to be refined by June 16, 1998.
April Page 5) 3 24, 1998 Statement:
selected barrier Section S3 u 'fe ua d P ur s page 23 states "The inspectors verified that changes to the Plan associated with the vehicle system (VBS), as implemented, did not decrease the effectiveness of the Plan. Discussions with the licensee indicated that the plan was currently being reviewed and a plan revision would be submitted in accordance with the provisions of 10CFR 50.54(p) in the near future."
Clarification: RGRE submitted a Security Plan revision M on July 24, 1997 (Refe'rence 4) which provided enhancement to the VBS. Also, RGGE submitted Security Plan revision N on January 15, 1998 although this revision was not related to the VBS.
Very truly yours, Robert C. Mecredy GJWE498 xc: Mr. Guy S. Vissing (Mail Stop 14B2)
Senior Project Manager Project Directorate I-1 Washington, D.C. 20555 Mr. Hubert J. Miller U. S. Nuclear Regulatory Commission Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
