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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] |
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DISR261 ESTER GAS 8c ELECTRIC C TION DOCUMENT CONTROL Document Transmittal Transmittal: 9812038N 058 To: DOCUMENT CONTROL DESK Date: 12/18/1998 US NRC Holder: 1217 WASHINGTON LISTED BELOW ARE
'C ATT: ALLEN JOHNSON PROJECT DOCTORATE 1-1 20555 NEW OR REVISED CONTROLLED DOCUMENTS. REVIEW THE ATTACHED INSTRUCTION LETTER (IF APPLICABLE), AND UPDATE YOUR CONTROLLED DOCUMENT IN ACCORDANCE WITH RM-RDM-1.
Doc Id Doc Title Rev Rev Date Qty TRM TECHNICAL REQUIREMENTS MANUAL FOR 006 12/18/1998 1 GINNA STATION 98i2290i34 98i2i8 PDR ADGCK 05000244 g' PDR Receipt Acknowledgement and Action Taken:
Signature Date Return to: Rochester Gas 6 Electric Corporation Ginna Station Records Management 1503 Lake Road Ontario, New York 14519
Rochester Gas and Electric Cor'poration Inter-Office Correspondence December 18, 1998
Subject:
Technical Requirements Manual (TRM) Revision 6 To: Distribution Attached are the associated revised pages for the Ginna Station Technical Requirements Manual (TRM). The changes included within Revision 6 are summarized as follows:
1 ~ The title of the Senior Vice President has changed from 'Customer Operations'o 'Generation'hich requires updating of TR 2.1 Required Action A.l and A.4.
- 2. A clarification is provided for TSR 3.3.4.1 to state that the surveillance is only applicable to the Charcoal Filter 1G fire detection system.
3.,The actual value (> 50%) of the minimum diesel driven fire pump fuel oil tank level has been added to TSR 3.7.1.3
- 4. Table TR 3.7.2-2 was revised to correct a typographical error and to correct the location of fire suppression system S50.
- 5. Table TR 3.7.4-1 was revised to correct the locations of the fire hose stations inside containment.
- 6. Table TR 3.7.5-1 was revised to correct the nomenclature for various fire dooi's.
- 7. The heading for page TRM 3.8-3 was revised to list the proper title of the section.
- 8. Table TR 5.1-1 was revised to add a new temporary LCO requirement for R-11 as the result of a commitment made to the NRC as part of their review of an RG&E request for the use of leak-before-break methodology for RHR lines inside containment.
Revision 6 of the TRM is considered effective December 18, 1998. Instructions for the necessary changes to your controlled copy of the ITS are as follows:
Volume Section Remove Insert III TRM Cover Page Cover Page III TRM LEP-i LEP-i III TRM Chapter 2.0 TRM 2.0-1 TRM 2.0-1 III TRM Chapter 3.3 TRM 3.3-9 TRM 3.3-9 III TRM Chapter 3.7 TRM 3.7-3 TRM 3.7-3 m TRM Chapter 3.7 TRM 3.7-10 TRM 3.7-10 III TRM Chapter 3.7 TRM 3.7-17 TRM 3.7-17 III TRM Chapter 3.7 TRM 3.7-20 TRM 3.7-20 III TRM Chapter 3.7 TRM 3.7-21 TRM 3.7-21 III TRM Chapter 3.7 TRM 3.7-22 TRM 3.7-22 III TRM Chapter 3.8 TRM 3.8-3 TRM 3.8-3 III TRM Chapter 5.0 TRM 5.0-2 TRM 5.0-2 Please contact Tom Harding (extension 3384) if you have any questions.
@~i Thomas L. Hardi g
GINNA STATION T evision 4 TECHNICA REQ REMENTS MANUAL TRM) espo sib e Hanage
/0//s /f7 Effective te Controlled Copy Ho.
List of Effective Pages (TRH)
Page Rev. Page Rev. Page Rev. Page Rev.
TOC Section 3.3 Section 3.7 (con'd) (con'd)
TRN 3.3-13 TRH 3.7-10 TRM 3.3-14 TRN 3.7-11 Section 1.0 TRM 3.3-15 TRN 3.7-12 TRH 3.3-16 TRN 3.7-13 TRN 1.0-1 TRH 3.?-14 Section 3.4 TRH 3.7-15 Section. 2.0 TRH 3.7-16 TRH 3.4-1 TRH 3.7-17 TRH 2.0-1 TRH 3.4-2 TRH 3.7-18 TRH 3.4-3 TRH 3.7-19 Section 3.0 TRH 3.4-4 TRH 3.7-20 TRM 3.4-5 TRM 3.7-21 TRM 3.0-1 TRH 3.4-6 TRH 3.7-22 TRH 3.4-7 TRH 3.7-23 Section 3.1 TRH 3.4-8 TRH 3.7-24 TRH 3.4-9 TRN 3.1-1 TRN 3.4-10 Section 3.8 TRH 3.1-2 TRN 3.4-11 TRN 3.1-3 TRM 3.4-12 TRM 3.8-1 TRH 3.1-4 TRN 3.4-13 TRN 3.8-2 TRH 3.1-5 TRM 3.4-14 TRM 3.8-3 TRH 3.1-6 TRH 3.1-7 Section 3.5 Section 3.9 Section 3.2 TRN 3.5-1 TRH 3.9-1 TRM 3.9-2 TRN 3.2-1 0 Section 3.6 TRM 3.9-3 TRM 3.9-4 Section 3.3 TRN 3.6-1 Section 4.0 TRH 3.3-1 1 Section 3.7 TRH 3.3-2 0 TRH 4.0-1 TRH 3.3-3 1 TRN 3.7-1 TRH 3.3-4 0 TRH 3.7-2 Section 5.0 TRH 3.3-5 0 TRH 3.7-3 TRH 3.3-6 0 TRM 3.7-4 TRH 5.0-1 TRH 3.3-7 1 TRH 3.7-5 TRH 5.0-2 TRH 3.3-8 1 TRM 3.7-6 TRH 3.3-9 TRH 3.7-7 TRH 3.3-10 4 TRH 3.7-8 TRH 3.3-11 4 TRH 3.7-9 TRH 3.3-12 4 Ginna Station TRN LEP-i Revision 4
SLs Violation TR 2.1 2.0 SAFETY LIHITS (SLs) 2.1 SLs Violation TR 2.1 See SL 2.1.1 and SL-2.1.2.
APPLICABILITY: In accordance with SL 2.1.
ACTIONS CONDITION REQU I REO ACT IONS COHPLETION TIHE A. SL 2.1.1 or 2.1.2 A. I Notify Senior Vice Immediately violated. President, Customer Operations.
A.2 Notify NSARB Immediatel, Chairman.
4 ANO A.3 Notify NRC. Immediately A.4 Prepare Safety Limit 14 days Violation Report and submit to the NRC, NSARB, and Senior Vice President, Customer Operations.
The report shall describe the applicable circumstances preceding the violation, the effect of the violation upon facility components, systems, or structures, and the corrective actions take to prevent recurrence.
Ginna Station TRH TRH 2.0-1 Revision 0
Fire ction Instrumentation TR 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FRE(UENCY TSR 3.3.4. 1 Perform a continuity check of nonsupervised 92 days circuits between local alarm panels and the control room.
TSR 3.3.4.2 Perform a continuity check of supervised 24 months circuits associated with detector alarms.
TSR 3.3.4.3 NOTE 24 months Verification of RTD detectors inside containment shall include detector continuity and temperature indication in the control room.
Perform a TADOT of fire detection instrumentation.
Ginna Station TRN 3.3-9 Revision 4
Fire pression Water Sources TR 3.7.1 SURVEIl,LANCE REQUIREHENTS SURVEILLANCE FREQUENCY TSR 3.7. 1. 1 Operate each fire pump on recirculation 31 days flow for a 15 minutes.
TSR 3.7. 1.2 Verify each fire suppression valve in the 31 days pump train or header flow path that is not locked, supervised, or otherwise secured in position is in the correct position.
TSR 3.7. 1.3 Verify level of diesel driven fire pump 31 days fuel oil tank is within limit.
TSR 3.7.1.4 starting batteries.'1 Inspect and test diesel driven fire pump days TSR 3.7.1.5 Verify diesel driven fire pump fuel oil 92 days stored in the day tank is within ASTH D975 recommended limits for Number 2 diesel fuel oil for viscosity, water, and sediment.
TSR 3.7. 1.6 Cycle air operated valve 9227 through one 10 months complete cycle.
(continued)
Ginna Station TRH 3.7-3 Revision 4
Fire Suppression Spray and Sprinkler Systems TR 3.7.2 Table TR 3.7.2-2 (page 1 of I)
Fire Suppress>on Spray and Sprinkler Systems - Hourly Watch SYSTEM FIRE SYSTEM LOCATION TYPE NUMBER ACTUATION Main Oil Storage Room Spray S16 Automati c Service Building - Main Floor, Basement. Hot Shop Sprinkler SI9 Automatic Transformer 01 Spray S20 Automatic Transformer fil Spray S21 Automatic Transformer t 12A Spray S22 Automatic Transformer 812B Spray S23 Automatic Turbine Condener Pit Spray S24 Hanual Generator Hydrogen Seal Spray S25 Automatic Turbine Island Sprinkler S26 Automatic
- 10. Main Turbine Oil Reservo>r Spray S27 Automatic Auxiliary Building - East Sta>rs Sprinkler S35 Automatic Auxiliary Building - West Stairs and Crane Hatch Sprinkler S36 Automatic Contamination Storage Room Sprinkler SSO Automatic Ginna Station TRM 3.7-10 Revision 3
Fire Hose Stations TR 3.7.4 Table TR 3.7.4-1 (page 2, of 2)
Fire Hose Stations HOSE REEL BUILDING FLOOR PROTECTED LOCATION NUMBER LOCATED ELEVATION 28 Auxil i ar y Basement West 29 Auxil i ary Basement Center 30 Auxil i ary Basement East 31 Screen House Main Fire Pumps 33 Containment Operating West Containment Operating East 35 Containment Mezzanine West 36 Containment Mezzanine East 37 Containment Basement West 38 Containment Basement East Ginna Station TRM 3.7-17 Revision 1
e
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Fire Barrier Penetration Seals TR 3.7.5 Table TR 3.7.5-1 (page 1 of 3)
Fire Barrier Penetration Seals BUILDING/ROOM SEPARATION LOCATION IN FIRE BARRIER FROM BLDG/ROON COMPONENTS
- 1. Control Building
- a. Air Handling Turbine Bldg North Wall Fire Seals Room Fire Door F-24 Fire Damper AH-44-P Fire Damper AH-39-P Fire Damper AH-53-P
- b. Battery Room A Turbine Bldg North Wall Fire Seals Fire Door F-25 Fire Damper BA-28-P
- c. Battery Room A Air Handling West Wall Fire Seals Room Fire Damper BA-33-P Fire Damper BA-38-P
- d. Battery Room B Turbine Bldg North Wall Fire Seals Fire Door F-26 Fire Damper BB-37-P
- e. Battery Room B Battery Room A West Wall Fire Seals Fire Door S-49 Fire, Damper BB-46-P Fire Damper BB-47-P
- f. Control Room Relay Room Floor Fire Seals
- g. Computer (MUX) Transformer West Wall Fire Seals Room Yard
- h. Relay Room Turbine Bldg North Wall Fire Seals Fire Door F-504
- i. Relay Room TSC Back East Wall Fire Seals Closet
- j. Relay Room Transformers South Wall Fire Seals
- k. Relay Room Back Stairwell West Wall Fire Seals Fire Door F-502 e
Ginna Station TRM 3.7-20 Revision 1
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Fire Barri er Penetrat i on Seal s TR 3.7.5 Table TR 3.7.5-1 (page 2 of 3)
Fire Barrier Penetration Seals BUILDING/ROOM SEPARATION FROM LOCATION IN FIRE BARRIER BLDG/ROOM COMPONENTS
- 2. Diesel Generator (DG) Room A
- a. DG Room A Oil Storage West Wall Fire Seals Room
- b. DG Room A Turbine Bldg South Wall Fire Seals Fire Door F-30
- c. DG A Vault DG B Vault East Wall Fire Seals
- 3. DG Room B
- a. DG Room B DG Room A West Wall Fire Seals
- b. DG Room B Turbine Bldg South Wall Fire Seals Fire Door F-29
- c. DG B Vault Remaining Vault Special Fire Seals
- 4. Intermediate
- a. Clean Side Turbine Bldg North Wall Fire Seals Fire Door S-37 Fire Door S-36
- b. Clean Side Cable Tunnel East Wall Fire Seals (Tunnel entrance is a smoke barrier only)
- c. Clean Side Service Bldg West Wall Fire Seals Stairwell and Elevator Shaft
- d. Clean Side Turbine Bldg - North Wall Fire Seals Intermediate Fire Door S-44 Ginna Station TRM 3.7-21 Revision 1
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1 Fire Barrier Penetration Seals TR 3.7.5 Table TR 3.7.5-1 (page 3 of 3) .
Fire Barrier Penetration Seals BUILDING/ROON SEPARATION LOCATION IN FIRE BARRIER FROM BLDG/ROOM COMPONENTS
- e. Clean Side Turbine Bldg - North Wall Fire Seals Operating
- f. Controlled Side Service Bldg West Wall Fire Seals Fire Damper F-509 Fire Damper I-27-P
- g. Controlled Side Service Bldg - West Wall Fire Seals Intermediate Fire Door S-46 Fire Door S-65 Fire Door F-510 Fire Damper I-340-1-P Fire Damper I-340-2-P Fire Damper I-350-P Fire Damper I-402-P
- h. Controlled Side Aux Bldg - South Wall Fire Seals Spent Fuel Fire Door F-503 Pool Fire Damper I-411-1-P Through I-411-21-P Fire Damper I-317-P
- i. Controlled Side Aux Bldg- East Wall Fire Seals Spent Fuel Fire Damper I-318-P Pool
- 5. Oil Storage Room DG Room A East Wall Fire Seals
- 6. Auxiliary Building Service West Wall Fire Seals Building Ginna Station TRM 3.7-22 Revision 1
Instrument Bus D TR 3.8.2
'table TR 3.8.2-1 (page I of 1)
Instrunent Bus O Supported Functions Fails to Tripped MOOE OF SUPPORT SYSTEH Condition? APPLICABILITY
- 1. LCO Table 3.3.2-1, Function 6.b, I'rain 8 No 1,2,3 2~ LCO Table 3.3.6.1, Functions 3.a, 3.b and 3.c Yes 1,2,3/4/5 6/ and
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(GREATS Intake Radiation Honitors) Novement of irradiated fuel
- 3. LCO Table 3.3. 1.1, Function 2 (N-44) Yes 1,2
- 4. LCO Table 3.3. 1-1, Function 5 (OTOT Channel 4) Yes 1,2
- 5. LCO Table 3.3.3-2, Functions Sb and 6c (SG A LT-463) Yes 1,2,3
- 6. LCO Table 3.3.3-2, Functions Sb and 6c (SG B LT-471) Yes 1,2,3
- 7. LCO Table 3.3.3-2, Functions 4d and 4e (SG 8 FT-475) Yes 1,2,3
- 8. LCO Table 3.3.3.1, Function 1 (Pzr Pressure PT-449) Yes 1,2,3
- 9. LCO Table 3.3.3- I, Function 23 (SG A LT-463) Yes 1,2,3
- 10. LCO Table 3.3.3"1, Fmtion 24 (SG B LT-471) Yes 1,2,3
- 11. TR Table 3.3.1-1, Functions 1 and 2 Yes 1,2,3,4,5,6 (CREATS Toxic Gas Intrunentation)
Ginna Station TRH TRH 3.8-3 Revision 3
Table TR 5.1-1 (page 1 of 1)
Terporary LCO Requirements Action Required Actions Item Report ¹ Teaporary LCO Requirement If Not Net Effective Dates 5.1.1 97.0783 a. Verify key suitches for NOVs 852A and 8528 are in "off a. Declare associated ECCS train 6/19/97 until LCO position" every 31 days. inoperable per LCO 3.5.2. 3.5.2 is changed 5.1.2 97-0894 a. Verify NaOH System tank NaOH solution concentration is a. Declare NaOH system inoperable per 6/19/97 until LCO s 35X by Height every 184 days. LCO 3.6.6. 3.6.6 is changed.
5.1.3 97-0960 a. Verify borated uater volune in each accumulator is a. Declare associated accumulator 6/19/97 until LCO k 67X and s 82X every 12 hours. inoperable per LCO 3.5.1. 3.5. 1 is changed.
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