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| | issue date = 04/14/1999 | | | issue date = 04/14/1999 |
| | title = Forwards Revised Ginna Station EOPs & Procedures Index | | | title = Forwards Revised Ginna Station EOPs & Procedures Index |
| | author name = WIDAY J A | | | author name = Widay J |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
| Line 17: |
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| =Text= | | =Text= |
| {{#Wiki_filter:REGULATORY XNFORMATXON DISTRXBUTION SYSTEM (RIDS)V..g CESSION NBR:99042003S5 DOC.DATE: 99/04/14 4/14 NOTARXZED: | | {{#Wiki_filter:V REGULATORY XNFORMATXON DISTRXBUTION SYSTEM (RIDS) |
| NO DOCKET 4 hester G 05000244 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 0 AUTH'.NAME | | ..g CESSION NBR:99042003S5 DOC.DATE: 99/04/14 4/14 NOTARXZED: NO DOCKET 4 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester hester G 05000244 0 |
| .AUTHOR AFFILIATION WIDAY, J.A.Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. | | AUTH'.NAME . AUTHOR AFFILIATION WIDAY,J.A. Rochester Gas & Electric Corp. |
| | RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards revised Ginna Station EOPs.DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:Inadequate Core Cooling (Item I..)em II.F.2)GL 82-2S NOTES:License Exp date in accordance with 10CFR ,.{/2 2.109{9/19/72).05000244 XNTERNAL: RECXPXENT ID CODE/NAME LPD1-1 PD RES DE RES/DSIR/RPSB | | Forwards revised Ginna Station EOPs. |
| 'I COPIES LTTR ENCL 1 1 1 1 1 1 1 RECXPXENT XD CODE/NAME VXSSING,G.
| | DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ENCL SIZE: |
| NRR/DSSA/SRXB RES/DET/EXB COPIES LTTR ENCL 1 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR'E YOUR NAME OR ORGANXZATXON REMOVED FROM DXSTRXBUTXON XXSTS Y U OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPXES REQUIRED: LTTR 9 ENCL | | TITLE: OR Submittal:Inadequate Core Cooling (Item em I II.F.2) |
| \t'I'IjjIIIIIIIIII fy'f>PiIlIidlll ROCHESTER GASANDELECTRIC CORPORATION | | . . ) GL 82-2S NOTES:License Exp date in accordance with 10CFR 2 , 2.109 . { / |
| ~JOSEPH A.WIDAY Aont Monoger Ginno Nuclear Plont h~~0 l>~Pj', lOAK f L 89EASTAVENUE, ROCHESTER, N.Y.14649%001 TELEPHONE AREA CODE 716 546-2700 April 14, 1999 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555
| | {9/19/72) . 05000244 |
| | 'I RECXPXENT COPIES RECXPXENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VXSSING,G. 1 1 XNTERNAL: 1 NRR/DSSA/SRXB 1 RES DE 1 1 RES/DET/EXB 1 1 RES/DSIR/RPSB 1 1 EXTERNAL: NOAC 1 1 NRC PDR'E YOUR NAME OR ORGANXZATXON REMOVED FROM DXSTRXBUTXON XXSTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU Y U OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPXES REQUIRED: LTTR 9 ENCL |
| | |
| | \ t h~ ~ 0 l>~ |
| | 'I'IjjIIIIIIIIII fy'f>PiIlIidlll Pj ', lOAK f |
| | L ROCHESTER GASANDELECTRIC CORPORATION ~ 89EASTAVENUE, ROCHESTER, N.Y. 14649%001 JOSEPH A. WIDAY TELEPHONE Aont Monoger AREA CODE 716 546-2700 Ginno Nuclear Plont April 14, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| Emergency Operating Procedures R.E.Ginna Nuclear Power Plant Docket No.50-244 | | Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Vissing:== |
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| |
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| ==Dear Mr.Vissing:==
| |
| As requested, enclosed are Ginna Station Emergency Operating Procedures. | | As requested, enclosed are Ginna Station Emergency Operating Procedures. |
| Very truly yours, ad%os hA.Wi JAW/jdw xc: U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s): | | Very truly yours, ad% |
| AP Index AP-PRZR.1, Rev.10 AP-RCS;1, Rev.14 9904200385 990414 PDR ADGCK 05000244.'' | | os hA. Wi JAW/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s): |
| P PDR REPORT NO.01 REPORT: NPSP0200 DOC TYPE: PRAP GINNA NUCLEAR POllER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 04/14/99 PAGB: 1 PARAMETERS: | | AP Index AP-PRZR.1, Rev. 10 AP-RCS;1, Rev. 14 9904200385 990414 PDR ADGCK 05000244.'' |
| DOC TYPES-PRAP PRPT STATUS: EF QU 5 YEARS ONLY: PROCEDURE NUMBER AP CCW.1 AP CCW.2 AP-CCH.3 AP-CR.1 AP-CVCS.1 AP-CVCS.3 AP CW.I AP-ELEC.1 AP-ELEC.2 AP-ELEC.3 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.1 AP IA.1 AP PRZR.1 AP-RCC.1 AP-RCC.2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 PROCEDURE TITLE LEAKAGE IHTO THE COMPONENT COOLING LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW-PLANT SHUTDOWN CONIROL ROOM INACCESSIBILITY CVCS LEAK LOSS OP ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 128 BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 128 TRANSFORMER (BELOW 350 F)LOSS OF SAFEGUARDS BUS 14/16 LOSS OF SAFEGUARDS BUS 17/18 PARTIAL OR COMPLBTE LOSS OF MAIN FEEDWATBR LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OP REACIOR COOLANT FLOM HIGH REACIOR COOLANT ACTIVITY SHUIDOWN LOCA LOSS OF RHR EFFECT REV DATE LAST RBVIEW 005 05/01/98 05/01/98 05/01/03 BF 000 06/09/97 06/09/97 06/09/02 EF 001 02/27/98 06/09/97 06/09/02 EF 011 02/27/98 02/27/98 02/27/03 BF 015 05/01/98 05/01/98 05/01/03 EP 010 04/14/99 09/29/94 09/29/99 EF 006 02/24/96 05/14/98 05/14/03 EF 008 ll/16/98 02/06/97 02/06/02 EF 004 11/16/98 02/27/98 02/27/03 EF 012 05/01/98 05/01/98 014 04/14/99 05/01/98 05/01/03 EP r 05/01/03 EF 010 12/14/98 05/01/98 05/01/03 EF 007 08/05/97 08/05/97 08/05/02 BF 009 05/01/98 05/01/98 05/01/03 EF 013 01/25/99 05/01/98 05/01/03 EF 013 10/30/98 05/01/98 05/01/03 BP 012 02I24I96 08/30/94 08/30/99 EP 010 03/29/96 08/30/94 08/30/99 EP 015 01/26/98 11/17/94 11/17/99 EP 012 OSI01/98 05/01/98 05I01/03 BP 000 02/26/99 02/26/99 02/26/04 EF 010 07/16/98 05/01/98 05/01/03 BP 017 03/22/99 05/01/98 05/01/03 EF 009 03/22/99 03/22/99 03/22/04 EF REPORT NO.01 REPORT: NPSP0200 DOC TYPE: PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 04/14/99 PAGE: 2 PARAMETERS: | | P PDR |
| DOC TYPES PRAP STATUS: EF QU 5 YEARS ONLY: PROCEDURE NUMBER AP-RHR.2 AP SW.1 AP TURB.l AP TURB.2 PROCEDURE TITLE LOSS OF RHR 46IILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS SERVICE WATER LEAK TURBINE TRIP WITNOUI RX TRIP REQUIRED TURBINE LOAD REJECTION EFFECT DATE LAST REVIEW NEXT REVIEW ST 007 05/15/97 03/21/95 03/21/00 EF 014 01/14/99 06/03/98 06/03/03 EF 010 02/12/99 10/10/97 10/10/02 EF 016 02/27/98 05/13/98 05/13/03 EP AP TURB.3 AP TURB.4 AP TURB.5'IURBINE VIBRATION LOSS OF CONDENSER VACUUM RAPID LOAD REDUCTION 008 12/04/96 02/10/98 02/10/03 EF 014 05/01/98 05/01/98 05/01/03 EP 003 02/27/98 07/10/95 07/10/00 EF TOTAL FOR PRAP 31}} | | |
| | REPORT NO. 01 GINNA NUCLEAR POllER PLANT 04/14/99 PAGB: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP PRPT STATUS: EF QU 5 YEARS ONLY: |
| | PROCEDURE EFFECT LAST NUMBER PROCEDURE TITLE REV DATE RBVIEW AP CCW.1 LEAKAGE IHTO THE COMPONENT COOLING LOOP 013 10/30/98 05/01/98 05/01/03 BP AP CCW.2 LOSS OF CCW DURING POWER OPERATION 012 02I24I96 08/30/94 08/30/99 EP AP-CCH. 3 LOSS OF CCW - PLANT SHUTDOWN 010 03/29/96 08/30/94 08/30/99 EP AP-CR. 1 CONIROL ROOM INACCESSIBILITY 015 01/26/98 11/17/94 11/17/99 EP AP-CVCS. 1 CVCS LEAK 012 OSI01/98 05/01/98 05I01/03 BP AP-CVCS. 3 LOSS OP ALL CHARGING FLOW 000 02/26/99 02/26/99 02/26/04 EF AP CW.I LOSS OF A CIRC WATER PUMP 010 07/16/98 05/01/98 05/01/03 BP AP-ELEC. 1 LOSS OF 12A AND/OR 128 BUSSES 017 03/22/99 05/01/98 05/01/03 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 009 03/22/99 03/22/99 03/22/04 EF AP-ELEC.3 LOSS OF 12A AND/OR 128 TRANSFORMER (BELOW 350 F) 005 05/01/98 05/01/98 05/01/03 BF AP-ELEC. 14/16 LOSS OF SAFEGUARDS BUS 14/16 000 06/09/97 06/09/97 06/09/02 EF AP-ELEC. 17/18 LOSS OF SAFEGUARDS BUS 17/18 001 02/27/98 06/09/97 06/09/02 EF AP-FW. 1 PARTIAL OR COMPLBTE LOSS OF MAIN FEEDWATBR 011 02/27/98 02/27/98 02/27/03 BF AP IA.1 LOSS OF INSTRUMENT AIR 015 05/01/98 05/01/98 05/01/03 EP AP PRZR.1 ABNORMAL PRESSURIZER PRESSURE 010 04/14/99 09/29/94 09/29/99 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 006 02/24/96 05/14/98 05/14/03 EF AP-RCC.2 RCC/RPI MALFUNCTION 008 ll/16/98 02/06/97 02/06/02 EF AP-RCC.3 DROPPED ROD RECOVERY 004 11/16/98 02/27/98 02/27/03 EF AP-RCP. 1 RCP SEAL MALFUNCTION 012 05/01/98 05/01/98 05/01/03 EP r |
| | AP-RCS. 1 REACTOR COOLANT LEAK 014 04/14/99 05/01/98 05/01/03 EF AP-RCS. 2 LOSS OP REACIOR COOLANT FLOM 010 12/14/98 05/01/98 05/01/03 EF AP-RCS. 3 HIGH REACIOR COOLANT ACTIVITY 007 08/05/97 08/05/97 08/05/02 BF AP-RCS. 4 SHUIDOWN LOCA 009 05/01/98 05/01/98 05/01/03 EF AP-RHR. 1 LOSS OF RHR 013 01/25/99 05/01/98 05/01/03 EF |
| | |
| | REPORT NO. 01 GINNA NUCLEAR POWER PLANT 04/14/99 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES PRAP STATUS: EF QU 5 YEARS ONLY: |
| | PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE DATE REVIEW REVIEW ST AP-RHR. 2 LOSS OF RHR 46IILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 007 05/15/97 03/21/95 03/21/00 EF AP SW.1 SERVICE WATER LEAK 014 01/14/99 06/03/98 06/03/03 EF AP TURB.l TURBINE TRIP WITNOUI RX TRIP REQUIRED 010 02/12/99 10/10/97 10/10/02 EF AP TURB.2 TURBINE LOAD REJECTION 016 02/27/98 05/13/98 05/13/03 EP AP TURB.3 'IURBINE VIBRATION 008 12/04/96 02/10/98 02/10/03 EF AP TURB.4 LOSS OF CONDENSER VACUUM 014 05/01/98 05/01/98 05/01/03 EP AP TURB.5 RAPID LOAD REDUCTION 003 02/27/98 07/10/95 07/10/00 EF TOTAL FOR PRAP 31}} |
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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
V REGULATORY XNFORMATXON DISTRXBUTION SYSTEM (RIDS)
..g CESSION NBR:99042003S5 DOC.DATE: 99/04/14 4/14 NOTARXZED: NO DOCKET 4 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester hester G 05000244 0
AUTH'.NAME . AUTHOR AFFILIATION WIDAY,J.A. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Forwards revised Ginna Station EOPs.
DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:Inadequate Core Cooling (Item em I II.F.2)
. . ) GL 82-2S NOTES:License Exp date in accordance with 10CFR 2 , 2.109 . { /
{9/19/72) . 05000244
'I RECXPXENT COPIES RECXPXENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VXSSING,G. 1 1 XNTERNAL: 1 NRR/DSSA/SRXB 1 RES DE 1 1 RES/DET/EXB 1 1 RES/DSIR/RPSB 1 1 EXTERNAL: NOAC 1 1 NRC PDR'E YOUR NAME OR ORGANXZATXON REMOVED FROM DXSTRXBUTXON XXSTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU Y U OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPXES REQUIRED: LTTR 9 ENCL
\ t h~ ~ 0 l>~
'I'IjjIIIIIIIIII fy'f>PiIlIidlll Pj ', lOAK f
L ROCHESTER GASANDELECTRIC CORPORATION ~ 89EASTAVENUE, ROCHESTER, N.Y. 14649%001 JOSEPH A. WIDAY TELEPHONE Aont Monoger AREA CODE 716 546-2700 Ginno Nuclear Plont April 14, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, ad%
os hA. Wi JAW/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):
AP Index AP-PRZR.1, Rev. 10 AP-RCS;1, Rev. 14 9904200385 990414 PDR ADGCK 05000244.
P PDR
REPORT NO. 01 GINNA NUCLEAR POllER PLANT 04/14/99 PAGB: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP PRPT STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NUMBER PROCEDURE TITLE REV DATE RBVIEW AP CCW.1 LEAKAGE IHTO THE COMPONENT COOLING LOOP 013 10/30/98 05/01/98 05/01/03 BP AP CCW.2 LOSS OF CCW DURING POWER OPERATION 012 02I24I96 08/30/94 08/30/99 EP AP-CCH. 3 LOSS OF CCW - PLANT SHUTDOWN 010 03/29/96 08/30/94 08/30/99 EP AP-CR. 1 CONIROL ROOM INACCESSIBILITY 015 01/26/98 11/17/94 11/17/99 EP AP-CVCS. 1 CVCS LEAK 012 OSI01/98 05/01/98 05I01/03 BP AP-CVCS. 3 LOSS OP ALL CHARGING FLOW 000 02/26/99 02/26/99 02/26/04 EF AP CW.I LOSS OF A CIRC WATER PUMP 010 07/16/98 05/01/98 05/01/03 BP AP-ELEC. 1 LOSS OF 12A AND/OR 128 BUSSES 017 03/22/99 05/01/98 05/01/03 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 009 03/22/99 03/22/99 03/22/04 EF AP-ELEC.3 LOSS OF 12A AND/OR 128 TRANSFORMER (BELOW 350 F) 005 05/01/98 05/01/98 05/01/03 BF AP-ELEC. 14/16 LOSS OF SAFEGUARDS BUS 14/16 000 06/09/97 06/09/97 06/09/02 EF AP-ELEC. 17/18 LOSS OF SAFEGUARDS BUS 17/18 001 02/27/98 06/09/97 06/09/02 EF AP-FW. 1 PARTIAL OR COMPLBTE LOSS OF MAIN FEEDWATBR 011 02/27/98 02/27/98 02/27/03 BF AP IA.1 LOSS OF INSTRUMENT AIR 015 05/01/98 05/01/98 05/01/03 EP AP PRZR.1 ABNORMAL PRESSURIZER PRESSURE 010 04/14/99 09/29/94 09/29/99 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 006 02/24/96 05/14/98 05/14/03 EF AP-RCC.2 RCC/RPI MALFUNCTION 008 ll/16/98 02/06/97 02/06/02 EF AP-RCC.3 DROPPED ROD RECOVERY 004 11/16/98 02/27/98 02/27/03 EF AP-RCP. 1 RCP SEAL MALFUNCTION 012 05/01/98 05/01/98 05/01/03 EP r
AP-RCS. 1 REACTOR COOLANT LEAK 014 04/14/99 05/01/98 05/01/03 EF AP-RCS. 2 LOSS OP REACIOR COOLANT FLOM 010 12/14/98 05/01/98 05/01/03 EF AP-RCS. 3 HIGH REACIOR COOLANT ACTIVITY 007 08/05/97 08/05/97 08/05/02 BF AP-RCS. 4 SHUIDOWN LOCA 009 05/01/98 05/01/98 05/01/03 EF AP-RHR. 1 LOSS OF RHR 013 01/25/99 05/01/98 05/01/03 EF
REPORT NO. 01 GINNA NUCLEAR POWER PLANT 04/14/99 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES PRAP STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE DATE REVIEW REVIEW ST AP-RHR. 2 LOSS OF RHR 46IILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 007 05/15/97 03/21/95 03/21/00 EF AP SW.1 SERVICE WATER LEAK 014 01/14/99 06/03/98 06/03/03 EF AP TURB.l TURBINE TRIP WITNOUI RX TRIP REQUIRED 010 02/12/99 10/10/97 10/10/02 EF AP TURB.2 TURBINE LOAD REJECTION 016 02/27/98 05/13/98 05/13/03 EP AP TURB.3 'IURBINE VIBRATION 008 12/04/96 02/10/98 02/10/03 EF AP TURB.4 LOSS OF CONDENSER VACUUM 014 05/01/98 05/01/98 05/01/03 EP AP TURB.5 RAPID LOAD REDUCTION 003 02/27/98 07/10/95 07/10/00 EF TOTAL FOR PRAP 31
