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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
R.1C3 CCELERATED R.IWY' RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9410180207 DOC.DATE: 94/09/30 NOTARIZED: NO DOCKET N FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION WIDAY,J.A. Rochester Gas & Electric Corp.
RECIPIENT AFFILIATION RECIP.NAME JOHNSON,A. Project Directorate I-3 p//
SUBJECT:
Forwards Rev 7 to EOP AP-PRZR.1, "Abnormal Pressurizer Pressure."
DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-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 PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 2 2 INTERNAL: SHE CENTER 01 1 1 NRR/DRCH/HHFB 1 '1 RES/DSIR/EIB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE IVASTE! CONTACl TI.IE DOCUMENT CONTROL f
DESK, ROOM Pl-37 (EXT. 504-2083 ) TO LIMINATEYOUR . LAME PRO~I DISTRIBUTION LISTS I'OR DOCI.:ME. ITS YOU DON"I'EED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9
////I$7/ (PI/8 Egi1~gE l(581I//
zzul/IE ////////
ROCHESTER GAS ANDELECTRIC CORPORATION o 89 EASTA VENUE, ROCHESTER, N. Y. 14649<001 JOSEPH A. WIDAY TELEPHONE Plant Manager AREA COOE 7te 546-2700 Glnna Nuchor Plant September 30, 1994 Mr. Allen Johnson Project Directorate I-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna'Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very Truly Yours, oseph A. Widay JAW/jdw xc: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station RGS.E Nuclear Safety 5 Licensing 5 St'<" '-
g
~410180207 Wo 230 005 PDR ADOCK 05000244
( . PER
Page 2
Enclosures:
AP-PRZR.1 Abnormal Pressurizer Pressure Rev. 7
EOP: TjjLE:
REV: 6 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION NTROLLED COPY NUMBER CHNICAL REVIEW PORC REVIEW DA E c2,1 9 P NT UPERINT DENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED
EOP: T I JLE:
REV 6 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 2 of 11 A. PURPOSE This procedure provides the actions necessary to mitigate the consequences of abnormal PRZR pressure.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS This procedure is entered from:
- a. AP-CVCS.1, CVCS LEAK, or b ~ I AP FW 1 I PART AL OR COMPLETE LOSS OF MA N
~ I FEEDWATER, or
- c. AP-IA.1, LOSS OF INSTRUMENT AIR, or d I AP RCC 1 I CONT NUOUS CONTROL ROD WITHDRAWAL OR
~
INSERTION, or
- e. AP-RCS.l, REACTOR COOLANT LEAK, or f AP TURB 1 i TURBINE TRIP WITHOUT RX TRIP REQUIRED i or
- g. AP-TURB.2, AUTOMATIC TURBXNE RUNBACK, when PRZR pressure can NOT be controlled.
- 2. SYMPTOMS The symptoms of ABNORMAL PRZR PRESSURE'are;
- a. Annunciator F-19, or PRZR PORV OUTLET HI TEMP 145'F, lit,
- b. Annunciator F-18, PRZR SAFETY VLV OUTLET HI 145'F, lit, or TEMP
- c. Annunciator AA-13, PRESSURIZER SAFETY VALVE lit, or POSXTXON,
- d. Annunciator F-l, PRT LIQUID HI TEMP 220'F, lit, or
- e. Annunciator F-9, PRT HX PRESS 5 PSI, lit, or
- f. Annunciator F-17, PRT LEVEL 60.8 % 84.5, lit, or
- g. Annunciator F-2, PRESSURIZER HI PRESS 2310 PSI, lit, or
- h. Annunciator F-10, PRESSURIZER LO PRESS 2185 PSI, lit, or
- i. Annunciator F-6, PRESSURIZER HEATER BREAKER TRIP, lit.
- j. Annunciator F-26, 2377 PSI.
PRESSURIZER HI PRESS CHANNEL ALERT
EOP: TITLE:
REV 6 P-PRZR.1 ABNORMAL PRESSURIZER 'PRESSURE PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x***x* A x% x% x**x% **x*x%'x CAUTION x x x***xx*x IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
- x***xxax xz***xkx*xx**x*x*******%'**ax*
NOTE: Actual PRZR pressure should be verified by more than 1 indicator.
1 Check PRZR Pressure: IF one pressure channel deviates significantly from the other 3, o All 4 narrow range channels THEN perform the following:
EQUAL 'PPROXIMATELY
- a. IF the controlling PRZR pressure o All 4 narrow range channels channel has failed, THEN place TRENDING TOGETHER controller, 431K, in MANUAL and adjust output to restore PRZR pressure.
- b. Refer to ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.
2 Check Reactor. Power STABLE IF the abnormal PRZR pressure is a result of a power transient, THEN evaluate conditions and go to the appropriate plant procedure.
3 Check PRZR Pressure:
- a. Pressure - LESS THAN 2235 PSIG a. Go to Step 12.
- b. Pressure - GREATER THAN 2000 PSIG b. IF pressure decreasing uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP: LITLE:
REV' P-PRZR. 1 ABNORMAL PRESSURIZER PRESSURE PAGE 4 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x*** x x**x**x x ~***x*****x x*x*xx**xx**x*
CAUTION OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR, 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.
- x**x*xx*xxxxxx*xxxx**x%*xxkx*xxxxxxxxxx 4 Check PRZR Heater Status:
- a. PRZR heater control group a. Place PRZR heater control group BREAKER CLOSED switch to TRIP to reset, then place switch to CLOSE and let return to AUTO.
- b. PRZR heater backup group - ON b. IF PRZR pressure less than 2220 psig, THEN energize PRZR backup heaters.
IF PRZR backup heater breaker has tripped, THEN perform the following:
- 1) Place the breaker switch to OFF to reset breaker.
- 2) Place the breaker switch to ON to energize heaters.
- 3) Verify load increase on Bus 16.
'C J
EOP: ZIZLG:
REV 6 P-PRZR. 1 ABNORMAL PRESSURIZER PRESSURE PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Normal PRZR Spray Place controllers in MANUAL at 0%
Valve Controllers DEMAND AT demand. IF valves can NOT be OS closed, THEN perform the following:
- a. Trip the reactor.
- b. Trip the associated RCP.
- c. Go to E-O, REACTOR TRIP OR SAFETY INJECTION.
NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not be operable in the automatic mode.
6 Check PRZR Pressure Place 431K in MANUAL and decrease Controller, 431K, Demand output to energize PRZR heaters.
LESS THAN 50~o
'i
)
EOP:
REV: 6 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR PORVs:
- a. PORVs - CLOSED a. Manually close PORVs.
IF any v'alve can NOT be closed, THEN manually close the associated block valve.
~ MOV-516 for PCV-430
~ MOV-515 for PCV-431C
- b. Annunciator F-19, PRZR PORV b. IF PORV leakage is indicated, OUTLET HI TEMP 145'F THEN perform the following:
EXTINGUISHED
- 1) Close PORV block valves one at a time AND check if pressure stabilizes.
~ MOV-515
~ MOV-516
- 2) IF a leaking PRZR PORV is identified, THEN restore any nonleaking PORV to operable AND go to Step 8.
- c. Go to Step 9
I U'W
EOP:
REV 6 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 7 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Attempt To Reseat Any Leaking PORV:
- a. Verify affected PORV block valve a. Close the affected PORV block CLOSED valve.
- b. Cycle the leaking PORV open then closed
- c. Open affected PORV block valve
- d. Verify leakage has stopped d. IF leakage continues, THEN perform the following:
- 1) Reclose leaking PORV block valve.
- 2) Refer to Tech Spec section 3.1.1.4 for required actions.
- e. Go to Step 11
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REV 6 P-PRZR.1 ABNORNAL PRESSURIZER PRESSURE PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x x x x ~ x P x x x*x**xx x x*x x***xx x x x x**
CAUTION o IF PRZR PRESSURE IS TO BE REDUCED WHILE AT POWER, IT SHOULD BE DONE SLOWLY SINCE THE PRZR LOW PRESSURE TRIP IS RATE SENSITIVE.
o WHEN REDUCING PRZR PRESSURE, OTaT SETPOINT WILL DECREASE.
xx**xxxxxxxxx*xxxxxex x*xxx*x*xx**xxxx*x*x 9 Check PRZR Safety Valves: IF safety valve leakage indicated, THEN perform the following to o Position indicator - LESS THAN attempt to reseat the leaking valve:
0.1 INCH
- a. SLOWLY reduce PRZR pressure o Annunciator F-18, PRZR SAFETY (remain above 2000 psig).
VLV OUTLET HI TEMP 145'F EXTINGUISHED b. IF symptoms indicate leakage has stopped, THEN restore pressure o Annunci.ator AA-13, PRESSURIZER to normal.
SAFETY VALVE POSITION EXTINGUISHED c. IF leakage recurs or can NOT be stopped, THEN perform the following:
- 1) Verify leakage within limits of Tech Spec section 3.1.5.
- 2) Go to Step 17.
10 Check AUX Spray Valve, Manually close valve. IF valve can AOV-296 CLOSED NOT be closed, THEN consider isolating letdown and closing charging flow control valve, HCV-142.
/'
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REV' P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll Check PRZR Pressure Restored:
Control
- a. Pressure - TRENDING TO 2235 PSIG a. IF pressure continues to decrease, THEN return to Step 1.
- b. Go to Step 17 12 Check PRZR Backup Heaters- Verify PRZR backup heater switch in OFF AUTO, AND ensure proper operation.
NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not be operable in the automatic mode 13 Check PRZR Pressure Place 431K in MANUAL at 50% demand.
Controller, 431K, Demand INCREASING NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
o The aT between the REGEN Hx charging outlet and the PRZR shall NOT exceed 320'F.
14 Check RCPs ANY RUNNING IF letdown in service, THEN perform the following:
- a. Open AUX spray valve, AOV-296, as necessary to control PRZR pressure.
- b. Go to Step 16.
4 o 1 P
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REV' P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 10 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If either RCP is off, then the associated PRZR spray valve controller should be placed in MANUAL with demand at 0%.
15 Check PRZR Spray Valve Place PRZR spray valve controllers Controllers Demand GREATER in MANUAL and open as required to THAN 04 control pressure.
~ PCV-431A
~ PCV-431B 16 Check PRZR Pressure IF PRZR pressure continues to TRENDING TO 2235 PSIG increase uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.
17 Check PRT Indications:
- a. Level - BETWEEN 55% a.'Drain PRT to RCDT using PRT drain valve, AOV-526.
- b. Pressure - APPROXIMATELY b. Open PRT vent, AOV-527. IF PRT 1.5 PSIG AND STABLE pressure will NOT decrease, THEN open PRT drain valve, AOV-526, to reduce pressure.
- c. Temperature - AT CNMT AMBIENT c. To feed and bleed the PRT, TEMPERATURE AND STABLE perform the following:
- 1) Start a RMW pump.
')
Verify RMW to CNMT isolation valve, AOV-508, open.
- 3) Feed and bleed the PRT using PRT fillvalve AOV-548, and PRT from RMW, drain valve, AOV-526.
REV: 6 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE ll of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
18 Notify Higher Supervision
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