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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] |
Text
A.CCEI ERAT 0 DOCUVIENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9306040043 DOC.DATE: 93/05/24 NOTARIZED: NO DOCKET N FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION /u 5'P JOHNSON,A. Project Directorate Z-3 ++4~+~
SUBJECT:
Forwards Ginna Nuclear Power Plant EOP,including Rev 7 to AP-TURB.l, "Turbine Trip W/o RX Trip Required" a Rev 8 to FR-C.2, "Response to Degraded Core Cooling." D DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR TITLE: OR/Licensing Submittal: Suppl 1 A ENCL SIZE:
to NUREC-0737(Generic Ltr 82-33)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 2 2 INTERNAL: NRR DRCH/HHFB11 1 1 OC/LFMB 1 0 REG E Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAI NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9
IIIII/i7llll IIIIIIIIII!II
////// /// Ill/IIIII l IIIIII/ /IIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE trice Prerldent ArtEA cooE Tie 546-2700 Cinna Nudear Production May 24, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Robert C. Mecredy Enclosures c: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station oaoe06 pO~
I I 930b040043 'Tt30524 PDR ADDCK 05000244 P PDR
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AP-TURB.1 Turbine Trip Without RX Trip Required FR-C.2 Response To Degraded Core Cooling
TITLE:
REV:
AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAG 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORAT ON GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT UPERINTENDENT EFF I E DATE CATEGORY 1.0 REVIEWED BY
T1TLE:
REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 2 of 10 A. PURPOSE This procedure provides the necessary instructions to control the plant following a turbine trip without a reactor trip required.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS This procedure is entered from:
- a. AP-CW.l, LOSS OF A CIRC WATER PUMP, or,
- b. AP-ELEC.1, LOSS OF 12A AND/OR 12B TRANSFORMER, or,
- c. AP-FW.l, PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER, or
- d. AP-TURB.2, AUTOMATIC TURBINE RUNBACK, or,
- e. AP-TURB.3, TURBINE VIBRATIONS, or,
- f. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip.
- 2. SYMPTOMS The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are:
- a. Annunciator K-1, THRUST BEARING FAILURE, lit, or
- b. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or
- c. Annunciator K-10, TURBINE MANUAL TRIP, lit, or
- d. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" Hg, lit, or
- e. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
- f. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or
- g. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or
- h. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or
- i. Annunciator K-3, AMSAC ACTUATED, lit.
TITLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *" * * *
- CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
1 Verify Turbine Stop Valves- Manually trip turbine.
CLOSED IF turbine stop valves can NOT be closed, THEN close both MSIVs.
IF reactor power greater than 8%
with both MSIVs closed, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
CAUTION PRZR PRESSURE LOW PRESSURE TRIP IS RATE SENSITIVE, THEREFORE, MONITOR PRESSURE WHEN REDUCING RCS TEMPERATURE.
NOTE: Automatic rod control is desired, if available.
2 Check Reactor Power:
F-
- a. NIS intermediate ranges a. Go to Step 8.
GREATER THAN 2.5x10 ~ AMPS
- b. Verify control rods driving in b. Ensure rod control bank selector to reduce reactor power in AUTO switch in manual and drive rods in as necessary to reduce reactor power.
- c. Borate as necessary to maintain control rods above rod insertion limits
E TlTLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish Shutdown S/G Level Control
- a. Place MFW regulating valve controllers in MANUAL
- b. Control MFW flow as necessary to restore S/G level
- c. S/G level - TRENDING TO PROGRAM c. Operate MFW bypass valves in MANUAL to restore. S/G level.
IF S/G level can NOT be restored, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
4 Verify Proper Operation Of Steam Dump:
,a. Verify annunciator G-15, STEAN a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.
- b. Condenser steam dump~operating b. IF steam dump NOT available, in AUTO THEN perform the following:
- 1) Adjust S/G ARV setpoints to 1005 psig and verify proper operation.
- 2) IF power is greater than 8%,
THEN ensure reactor trip and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
- c. Tavg - TRENDING TO 547'F c. IF Tavg,can NOT be controlled, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP: TITLE:
REV 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check PRZR Pressure IF PRZR pressure can NOT be TRENDING TO 2235 PSIG controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
6 Check PRZR Level:
- a. Level - GREATER THAN 13% a. Perform the following:
- 1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to CLOSE.
- 2) Place letdown orifice valve switches to CLOSE (AOV-200A, AOV-200B, and AOV-202).
- 3) Verify excess letdown isolation valve (AOV-310) closed.
- 4) Ensure PRZR heaters off.
- 5) Control charging to restore PRZR level greater than 13%.
- 6) WHEN PRZR level greater than 13%, THEN restore letdown.
- b. Level - TRENDING TO PROGRAM b. Increase charging flow as necessary to restore PRZR level to program.
EOP: TITLE:
REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX'TRIP REQUIRED PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Placing MFW regulating valve controllers in MANUAL will restore automatic control of MFW bypass valves if desired.
7 Check MFW System:
- a. Verify MFW regulating valve a. Place MFW regulating valve bypass valves - OPERATING IN AUTO bypass valve controllers in AUTO and transfer to bypass control if desired.
- b. MFW pumps - BOTH RUNNING b. Perform the following:
- 1) Verify one MFW pump running.
IF NOT, THEN verify both MDAFW pumps running.
- 2) Go to Step 8.
- c. Close one MFW pump discharge valve
- d. Stop selected MFW pump 8 Establish Stable Plant Conditions:
- a. Place rod control bank selector in MANUAL
- b. Check Rx power - LESS THAN b. Return to Step 2.
2.5x10 6 AMPS
- c. PRZR pressure - BETWEEN c. Control PRZR heaters and spray 2220 PSIG AND 2260 PSIG as necessary.
- d. PRZR level - between 20% and 30% d. Control charging as necessary.
- e. S/G levels - TRENDING TO PROGRAM e. Control S/G feed flow as necessary.
- f. RCS Tavg - GREATER THAN 540'F f. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.
I' TITLE:
REV: 5 AP- TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Maintain Reactor power less than 2%. This is within the capacity of MDAFW pumps.
9 Check S/G Feed Flow Status:
- a. Manually start both MDAFW pumps
- b. Verify total AFW flow - GREATER b. Perform the following; THAN 200 GPM
- 1) Establish MFW flow using MFW regulating valve bypass valves.
IF MFW NOT available, THEN manually start TDAFW pump and establish flow as necessary.
- 2) Go to Step 10.
- c. Verify MFW flow control valves c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.
~ MFW regulating valves
~ MFW bypass valves
- d. Close MFW pump discharge valves
~ MOV-3977, A MFW pump
~ MOV-3976, B MFW pump
- e. Stop any running MFW pump
- f. Check S/G level - TRENDING TO 39% f. Adjust MDAFW pump flow as necessary to restore S/G level.
TITLE REV: 5 AP-TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
CAUTION WHEN FEEDING BOTH S/GS USING ONE MDAFW PUMP, THEN THE SUM OF THE FLOWS TO BOTH S/GS MUST BE LESS THAN 230 GPM.
10 Establish Normal AFW Pump Shutdown Alignment:
- a. Place AFW bypass switches to DEF
- b. Verify AFW bypass valves b. Go to Step 11.
OPERABLE
~ AOV-4480
~ AOV-4481
- c. Verify the following: c. Continue with Step 11. WHEN conditions met, THEN do Steps o Both S/G levels - STABLE OR 10d through g.
INCREASING o Total AFW flow - LESS THAN 200 GPM
- d. Close MDAFW pump discharge valves
~ MOV-4007
~ MOV-4008
- e. Stop all but one MDAFW pump
- f. Open AFW discharge crossover valves
~ MOV-4000A
~ MOV-4000B
- g. Open AFW bypass valves as necessary to control S/G levels
~ AOV-4480
~ AOV-4481
EOP:
I REV: 5 AP-TURB. 1 E TRIP WITHOUT Rx TR1P REQUIRED PAGE 9 of 1O STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Normal Shutdown Alignment:
- a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
- b. Perform the following as necessary:
o Open generator disconnects
~ 1G13A71
~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump it
- c. Verify Bus 11A and Bus 11B c. IF either bus NOT energized, energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2, THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/
BUS 12B.
- d. Dispatch AO to perform Attachment SD-1 NOTE: Refer to 0-9.3, NRC STATE AND COUNTIES IMMEDIATE NOTIFICATION, for reporting requirements.
12 Notify Higher Supervision
Ebs:
REV' AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Establish Desired Plant Conditions: .
- a. Reactor shutdown - DESIRED a. IF turbine is to be restored to service, THEN maintain reactor critical and refer to 0-1.2, PLANT FROM HOT SHUTDOWN TO STEADY LOAD.
- b. Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN
-END-
F.OP:
REV: 5 TURBINE TRIP WITHOUT Rg TRIP REQUIRED PAGE 1 of 1 APPENDIX LIST
- 1) Attachment SD-1
- 2) Attachment SD-2
r