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| {{#Wiki_filter:REGULATORY ORMATION DISTRIBUTION SYS 9 (RIDS)ACCESSION NBR t 8003240381 DOC~DATE;80/03/17 NOTARIZED! | | {{#Wiki_filter:REGULATORY ORMATION DISTRIBUTION SYS 9 (RIDS) |
| NO DOCKET FACIL;50 204 Robert Emmet Ginna Nuclear Planti Unit li Rochester G 05000244 AUTH, NAME AUTHOR AFFILIATION WHITE,L,D, Rochester Gas 8 Electric Corp.RECIP NNAME.RECIPIENT AFFILIATION ZIEMANNiD~L, Operating Reactors Branch 2 | | ACCESSION NBR t 8003240381 DOC ~ DATE; 80/03/17 NOTARIZED! NO DOCKET FACIL;50 204 Robert Emmet Ginna Nuclear Planti Unit AUTH, NAME AUTHOR AFFILIATION li Rochester G 05000244 WHITE,L,D, Rochester Gas 8 Electric Corp. |
| | RECIP NNAME . RECIPIENT AFFILIATION ZIEMANNiD~ L, Operating Reactors Branch 2 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Responds to NRC'00211 ltr re addi info, on containment purge 8 vent sysExisting sys being modified per NUREG 0578 to.require individua'1 resetting of any conta,inment isolatiop-valve required toI open when initiating signal presents 1 DISTRISUTION CODE: ASSES COPIES RECEIVED:LTR l ENCL-4 SIZE I-~----TITLE: SEP Topics NOTES: JQ~+Ag+J1 E~''R.+AC~--'ECIPIENT COPIES RECIPIENT~COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL'CTION: | | Responds 8 |
| 19 BC Og8 INTERNAL: REG R 10 TA/EDO-13 ENGR BR 15 PLANT SYS BR 17 EFFT TRT" SYS EXTERNAL: 03 LPDR 23 ACRS 1 16 02 NRC PDR 08 ISE il CORE PERF BR 14 REAC SFTY BR-16 EEB STS GROUP LEADR 07 NSIC 1 2 1 1'1 1 MAR S5 1980 TOTAL NUMBER OF-COPIES REQUIRED: LTTR~ENCL P~'
| | to NRC'00211 ltr re addi info, on containment purge vent sysExisting sys being modified per NUREG 0578 to. |
| ZiZZZ iZS/////I/I///gal// | | require individua'1 resetting of any conta,inment isolatiop |
| //IIXI/I//E | | - |
| //Il/II////// | | valve required toI open when initiating signal presents DISTRISUTION CODE: ASSES TITLE: SEP COPIES RECEIVED:LTR Topics l ENCL -4 SIZE I-~ ---- |
| SZu ROCHESTER GAS AND ELECTRIC CORPORATION J''"'gw IIAtt o,89 EAST AVENUE, ROCHESTER, N.Y.14649 LEON D.WHITE, JR.VICE PRESIDENT TELEPHONE ARE*CDDE TIE 546.2700 March 17, 1980 Director of Nuclear Reactor Regulation Attention: | | 1 NOTES: |
| Mr.Dennis L.Ziemann, Chief Operating Reactors Branch No.2 U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | JQ ~ +Ag+J1 E~ '' R. +AC~ |
| | COPIES RECIPIENT ~ COPIES |
| | -'ECIPIENT ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR 19 BC Og8 ENCL'CTION: |
| | INTERNAL: REG 02 NRC PDR 1 R 08 ISE 2 10 13 TA/EDO-ENGR BR il CORE 14 REAC PERF BR SFTY BR 1 |
| | 1 15 PLANT SYS BR - |
| | 16 EEB '1 17 EFFT TRT" SYS STS GROUP LEADR 1 EXTERNAL: 03 LPDR 1 07 NSIC 23 ACRS 16 MAR S5 1980 TOTAL NUMBER OF- COPIES REQUIRED: LTTR ~ ENCL |
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| | P |
| | ~' |
| | |
| | ZiZZZ |
| | /I/I///gal// |
| | iZS//// |
| | //IIXI/I//E J ' '"' |
| | / /Il/II////// SZu gw IIAtt ROCHESTER GAS AND ELECTRIC CORPORATION o,89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR. TELEPHONE VICE PRESIDENT ARE*CDDE TIE 546.2700 March 17, 1980 Director of Nuclear Reactor Regulation Attention: Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No. 2 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| SEP Topic VI-4, Containment Isolation System R.E.Ginna Nuclear Power Plant Docket No.50-244 | | SEP Topic VI-4, Containment Isolation System R. E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Ziemann:== |
| | |
| | This letter is in response to your February which requested the following additional information concerning ll, 1980 letter, the Ginna containment purge and vent systems. |
| | : 1. The overriding of one type of safety actuation signal should not cause the blocking of any other type of safety actuation signal to the isolation valves. The Ginna plant engineered safety features apparently have several overrides that block even manual actuation. |
| | |
| | ===Response=== |
| | As stated in our letter to you on the subject system, dated December 14, 1979, the containment purge system has been designed to provide purging capability following a LOCA, when high containment radiation and SI signals may be present, to limit potential hydrogen concentrations in containment during the post accident period. In order to perform this safety function, the reset system is designed to override all containment isolation initiating signals as long as any actuating signal is present. |
| | The existing reset system is being modified in accordance with Section 2.1.4 and Appendix A 2.1.4 of NUREG 0578, to require individual resetting of any containment isolation valve which may be required to open while a C.I. initiating signal is present. At least three deliberate operator actions, including operation of the containment isolation 8003240 8'I |
| | |
| | Jl ROCHESTER GAS AND ELECTRIC C P. SHEET NO. |
| | DATE March 17, 1980 To Mr. Dennis L. Ziemann,- Chief key switch, must be performed by the operator before any two redundant isolation valves (potential release path) are opened (e.g., purge exhaust). This virtually precludes inadvertent violation of containment, isolation. Procedures require extensive review of plant conditions before initiating any action which would require the opening of an isolation valve after an event which has caused containment isolation. |
| | it If were decided to perform a containment purge during accident conditions, great care would be taken during this operation. The personnel performing this safety function would be aware of the significance of the action, and would be prepared to close the valves if necessary for any reason. |
| | Re-establishing containment isolation would be a quick, simple process (closing the appropriate valve switches). It is not considered that. this process requires any further simplification (such as having a system - level manual isolation switch). |
| | Another set of circumstances wherein the containment ventilation isolation valves are blocked from closing upon receipt of a safety actuation signal is described in our December 14, 1979 letter on this subject. In the event these valves are open, and high activity (but no SI signal) is present, administrative procedures ensure that the reset will not be used until the high activity alarm has been cleared. The SI signal will thus no longer be blocked, and be capable of effecting valve closure. |
| | : 2. The system level annunciation of the overridden status should be provided for every safety system impacted when an override is active. The Ginna plant apparently does not have this capability. |
| | |
| | ===Response=== |
| | As noted in our response to item (1) above, the reset panel matrix clearly displays any isolation valve which is in a reset status. |
| | The requirement referred to for system level annunciation of overridden status of safety systems is contained in Regulatory Guide 1.47, B assed and Ino erable Status Indication for Nuclear Power Plant Safet S stems which was z.ssued zn May 1973. The extent to which plants, such as R.E. Ginna, which were designed and constructed prior to the issuance of this Regulatory Guide, are required to implement its requirements is currently the subject of generic review under the SEP program and TMI related NRC staff programs. It is our position that status monitoring modifications should only be made on an integrated basis for all safety systems in accordance |
| | 'with careful consideration of the man-machine interface. |
| | |
| | T |
| | , ROCHESTER GAS AND ELECTRIC C P. SHEET NO. |
| | DATE March 17, 1980 To Mr. Dennis L. Ziemann, Chief Treating individual systems, such as containment isolation, without regard to maintaining a consistent= status monitoring approach to all safety systems could lead to operator confusion and error. |
| | : 3. The instrumentation and control systems provided to initiate engineered safety features should be designed and qualified as safety grade equipment. Discuss the qualification of the isolation channel and radiation channel equipment. in this regard. |
|
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|
| ==Dear Mr.Ziemann:== | | ===Response=== |
| This letter is in response to your February ll, 1980 letter, which requested the following additional information concerning the Ginna containment purge and vent systems.1.The overriding of one type of safety actuation signal should not cause the blocking of any other type of safety actuation signal to the isolation valves.The Ginna plant engineered safety features apparently have several overrides that block even manual actuation.
| | The containment isolation system, including the actuating channels, was designed and constructed as a Class IE system. |
| Response: As stated in our letter to you on the subject system, dated December 14, 1979, the containment purge system has been designed to provide purging capability following a LOCA, when high containment radiation and SI signals may be present, to limit potential hydrogen concentrations in containment during the post accident period.In order to perform this safety function, the reset system is designed to override all containment isolation initiating signals as long as any actuating signal is present.The existing reset with Section 2.1.4 require individual valve which may be signal is present.actions, including system is being modified in accordance and Appendix A 2.1.4 of NUREG 0578, to resetting of any containment isolation required to open while a C.I.initiating At least three deliberate operator operation of the containment isolation 80032408'I Jl ROCHESTER GAS AND ELECTRIC C P.DATE March 17, 1980 To Mr.Dennis L.Ziemann,-Chief SHEET NO.key switch, must be performed by the operator before any two redundant isolation valves (potential release path)are opened (e.g., purge exhaust).This virtually precludes inadvertent violation of containment, isolation.
| | Qualification of electrical and ISC equipment has been described in our report to A. Schwencer, dated February 24, 1978, on the subject. "Environmental Qualification of Electrical Equipment, R.E. Ginna Nuclear Power Plant Unit No. 1". This topic is currently being reviewed generically under the SEP program. |
| Procedures require extensive review of plant conditions before initiating any action which would require the opening of an isolation valve after an event which has caused containment isolation.
| | : 4. The overriding or resetting of the isolation actuation signal should not cause the automatic motion of any Engineered Safety Feature valve. Your letter of October 17, 1979 and November 19, 1979 indicate that a modification is planned for the upcoming March refueling outage. |
| If it were decided to perform a containment purge during accident conditions, great care would be taken during this operation.
| | Describe how the modification will prevent automatic valve position changes on resetting of isolation logic, including schematic diagrams or sketches as necessary. |
| The personnel performing this safety function would be aware of the significance of the action, and would be prepared to close the valves if necessary for any reason.Re-establishing containment isolation would be a quick, simple process (closing the appropriate valve switches).
| |
| It is not considered that.this process requires any further simplification (such as having a system-level manual isolation switch).Another set of circumstances wherein the containment ventilation isolation valves are blocked from closing upon receipt of a safety actuation signal is described in our December 14, 1979 letter on this subject.In the event these valves are open, and high activity (but no SI signal)is present, administrative procedures ensure that the reset will not be used until the high activity alarm has been cleared.The SI signal will thus no longer be blocked, and be capable of effecting valve closure.2.The system level annunciation of the overridden status should be provided for every safety system impacted when an override is active.The Ginna plant apparently does not have this capability.
| |
| Response: As noted in our response to item (1)above, the reset panel matrix clearly displays any isolation valve which is in a reset status.The requirement referred to for system level annunciation of overridden status of safety systems is contained in Regulatory Guide 1.47, B assed and Ino erable Status Indication for Nuclear Power Plant Safet S stems which was z.ssued zn May 1973.The extent to which plants, such as R.E.Ginna, which were designed and constructed prior to the issuance of this Regulatory Guide, are required to implement its requirements is currently the subject of generic review under the SEP program and TMI related NRC staff programs.It is our position that status monitoring modifications should only be made on an integrated basis for all safety systems in accordance
| |
| 'with careful consideration of the man-machine interface.
| |
|
| |
|
| T , ROCHESTER GAS AND ELECTRIC C P.DATE March 17, 1980 To Mr.Dennis L.Ziemann, Chief SHEET NO.Treating individual systems, such as containment isolation, without regard to maintaining a consistent=
| | ===Response=== |
| status monitoring approach to all safety systems could lead to operator confusion and error.3.The instrumentation and control systems provided to initiate engineered safety features should be designed and qualified as safety grade equipment.
| | The detailed design of the containment isolation modification which requires individual reset for each isolation valve is being reviewed as part of the Short-Term Lessons Learned Program. |
| Discuss the qualification of the isolation channel and radiation channel equipment.
| | Very truly yours, L. D. Whi e, Jr. |
| in this regard.Response: The containment isolation system, including the actuating channels, was designed and constructed as a Class IE system.Qualification of electrical and ISC equipment has been described in our report to A.Schwencer, dated February 24, 1978, on the subject."Environmental Qualification of Electrical Equipment, R.E.Ginna Nuclear Power Plant Unit No.1".This topic is currently being reviewed generically under the SEP program.4.The overriding or resetting of the isolation actuation signal should not cause the automatic motion of any Engineered Safety Feature valve.Your letter of October 17, 1979 and November 19, 1979 indicate that a modification is planned for the upcoming March refueling outage.Describe how the modification will prevent automatic valve position changes on resetting of isolation logic, including schematic diagrams or sketches as necessary.
| | LDW:np}} |
| Response: The detailed design of the containment isolation modification which requires individual reset for each isolation valve is being reviewed as part of the Short-Term Lessons Learned Program.Very truly yours, L.D.Whi e, Jr.LDW:np}}
| |
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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]
Category:UTILITY TO NRC
MONTHYEARML20059L4481990-09-18018 September 1990
Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21)
ML17309A4491990-09-13013 September 1990
Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld
ML17262A1331990-09-11011 September 1990
Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion
ML17261B1511990-08-29029 August 1990
Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively
ML17261B1481990-08-28028 August 1990
Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant
IR 05000244/19880261990-08-20020 August 1990
Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented
ML17261B1501990-08-20020 August 1990
Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented
ML17261B1371990-08-17017 August 1990
Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant.
ML17309A4481990-08-16016 August 1990
Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records
ML17261B1351990-08-15015 August 1990
Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function
ML17261B1361990-08-14014 August 1990
Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts
ML17261B1331990-08-13013 August 1990
Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002
ML17261B1261990-07-30030 July 1990
Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days
ML20055H9291990-07-23023 July 1990
Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21
ML17261B1091990-07-20020 July 1990
Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp
ML17309A4471990-07-17017 July 1990
Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b)
ML17261B0881990-07-13013 July 1990
Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability.
ML17261B0921990-07-11011 July 1990
Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723
ML20044B0481990-07-10010 July 1990
Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs
ML17309A4461990-07-0909 July 1990
Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions
ML17261B0931990-07-0909 July 1990
Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs
ML17261B0901990-07-0909 July 1990
Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion
ML17250B2151990-06-29029 June 1990
Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries
ML17261B0851990-06-28028 June 1990
Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21
ML17250B1991990-06-0808 June 1990
Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983
ML17250B1951990-06-0505 June 1990
Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept
ML17250B1851990-06-0101 June 1990
Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs
ML17261B0691990-06-0101 June 1990
Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear
ML17250B1811990-05-31031 May 1990
Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21)
ML17250B1801990-05-29029 May 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity
ML17250B1841990-05-29029 May 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined
ML17261B0961990-05-29029 May 1990
Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred
ML17250B1721990-05-18018 May 1990
Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage
ML20042G8931990-05-0808 May 1990
Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3
ML17261B0611990-04-26026 April 1990
Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements
ML17261B0591990-04-17017 April 1990
Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur
ML17261B0461990-04-12012 April 1990
Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys
ML17262A1431990-04-12012 April 1990
Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys
ML17250B1451990-04-0606 April 1990
Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed
ML17250B1441990-04-0505 April 1990
Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion
ML17261B0401990-03-30030 March 1990
Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501
ML17261B0321990-03-28028 March 1990
Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp
ML17261B0331990-03-28028 March 1990
Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date
ML17261B0231990-03-26026 March 1990
Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated
ML17261B0281990-03-23023 March 1990
Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods
ML17261B0221990-03-22022 March 1990
Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828
ML17261B0411990-03-20020 March 1990
Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4)
ML17261B0151990-03-19019 March 1990
Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses
ML17261B0101990-03-15015 March 1990
Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies
ML20012D2831990-03-14014 March 1990
Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl
1990-09-18
[Table view] |
Text
REGULATORY ORMATION DISTRIBUTION SYS 9 (RIDS)
ACCESSION NBR t 8003240381 DOC ~ DATE; 80/03/17 NOTARIZED! NO DOCKET FACIL;50 204 Robert Emmet Ginna Nuclear Planti Unit AUTH, NAME AUTHOR AFFILIATION li Rochester G 05000244 WHITE,L,D, Rochester Gas 8 Electric Corp.
RECIP NNAME . RECIPIENT AFFILIATION ZIEMANNiD~ L, Operating Reactors Branch 2
SUBJECT:
Responds 8
to NRC'00211 ltr re addi info, on containment purge vent sysExisting sys being modified per NUREG 0578 to.
require individua'1 resetting of any conta,inment isolatiop
-
valve required toI open when initiating signal presents DISTRISUTION CODE: ASSES TITLE: SEP COPIES RECEIVED:LTR Topics l ENCL -4 SIZE I-~ ----
1 NOTES:
JQ ~ +Ag+J1 E~ R. +AC~
COPIES RECIPIENT ~ COPIES
-'ECIPIENT ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR 19 BC Og8 ENCL'CTION:
INTERNAL: REG 02 NRC PDR 1 R 08 ISE 2 10 13 TA/EDO-ENGR BR il CORE 14 REAC PERF BR SFTY BR 1
1 15 PLANT SYS BR -
16 EEB '1 17 EFFT TRT" SYS STS GROUP LEADR 1 EXTERNAL: 03 LPDR 1 07 NSIC 23 ACRS 16 MAR S5 1980 TOTAL NUMBER OF- COPIES REQUIRED: LTTR ~ ENCL
P
~'
ZiZZZ
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//IIXI/I//E J ' '"'
/ /Il/II////// SZu gw IIAtt ROCHESTER GAS AND ELECTRIC CORPORATION o,89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR. TELEPHONE VICE PRESIDENT ARE*CDDE TIE 546.2700 March 17, 1980 Director of Nuclear Reactor Regulation Attention: Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No. 2 U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
SEP Topic VI-4, Containment Isolation System R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Ziemann:
This letter is in response to your February which requested the following additional information concerning ll, 1980 letter, the Ginna containment purge and vent systems.
- 1. The overriding of one type of safety actuation signal should not cause the blocking of any other type of safety actuation signal to the isolation valves. The Ginna plant engineered safety features apparently have several overrides that block even manual actuation.
Response
As stated in our letter to you on the subject system, dated December 14, 1979, the containment purge system has been designed to provide purging capability following a LOCA, when high containment radiation and SI signals may be present, to limit potential hydrogen concentrations in containment during the post accident period. In order to perform this safety function, the reset system is designed to override all containment isolation initiating signals as long as any actuating signal is present.
The existing reset system is being modified in accordance with Section 2.1.4 and Appendix A 2.1.4 of NUREG 0578, to require individual resetting of any containment isolation valve which may be required to open while a C.I. initiating signal is present. At least three deliberate operator actions, including operation of the containment isolation 8003240 8'I
Jl ROCHESTER GAS AND ELECTRIC C P. SHEET NO.
DATE March 17, 1980 To Mr. Dennis L. Ziemann,- Chief key switch, must be performed by the operator before any two redundant isolation valves (potential release path) are opened (e.g., purge exhaust). This virtually precludes inadvertent violation of containment, isolation. Procedures require extensive review of plant conditions before initiating any action which would require the opening of an isolation valve after an event which has caused containment isolation.
it If were decided to perform a containment purge during accident conditions, great care would be taken during this operation. The personnel performing this safety function would be aware of the significance of the action, and would be prepared to close the valves if necessary for any reason.
Re-establishing containment isolation would be a quick, simple process (closing the appropriate valve switches). It is not considered that. this process requires any further simplification (such as having a system - level manual isolation switch).
Another set of circumstances wherein the containment ventilation isolation valves are blocked from closing upon receipt of a safety actuation signal is described in our December 14, 1979 letter on this subject. In the event these valves are open, and high activity (but no SI signal) is present, administrative procedures ensure that the reset will not be used until the high activity alarm has been cleared. The SI signal will thus no longer be blocked, and be capable of effecting valve closure.
- 2. The system level annunciation of the overridden status should be provided for every safety system impacted when an override is active. The Ginna plant apparently does not have this capability.
Response
As noted in our response to item (1) above, the reset panel matrix clearly displays any isolation valve which is in a reset status.
The requirement referred to for system level annunciation of overridden status of safety systems is contained in Regulatory Guide 1.47, B assed and Ino erable Status Indication for Nuclear Power Plant Safet S stems which was z.ssued zn May 1973. The extent to which plants, such as R.E. Ginna, which were designed and constructed prior to the issuance of this Regulatory Guide, are required to implement its requirements is currently the subject of generic review under the SEP program and TMI related NRC staff programs. It is our position that status monitoring modifications should only be made on an integrated basis for all safety systems in accordance
'with careful consideration of the man-machine interface.
T
, ROCHESTER GAS AND ELECTRIC C P. SHEET NO.
DATE March 17, 1980 To Mr. Dennis L. Ziemann, Chief Treating individual systems, such as containment isolation, without regard to maintaining a consistent= status monitoring approach to all safety systems could lead to operator confusion and error.
- 3. The instrumentation and control systems provided to initiate engineered safety features should be designed and qualified as safety grade equipment. Discuss the qualification of the isolation channel and radiation channel equipment. in this regard.
Response
The containment isolation system, including the actuating channels, was designed and constructed as a Class IE system.
Qualification of electrical and ISC equipment has been described in our report to A. Schwencer, dated February 24, 1978, on the subject. "Environmental Qualification of Electrical Equipment, R.E. Ginna Nuclear Power Plant Unit No. 1". This topic is currently being reviewed generically under the SEP program.
- 4. The overriding or resetting of the isolation actuation signal should not cause the automatic motion of any Engineered Safety Feature valve. Your letter of October 17, 1979 and November 19, 1979 indicate that a modification is planned for the upcoming March refueling outage.
Describe how the modification will prevent automatic valve position changes on resetting of isolation logic, including schematic diagrams or sketches as necessary.
Response
The detailed design of the containment isolation modification which requires individual reset for each isolation valve is being reviewed as part of the Short-Term Lessons Learned Program.
Very truly yours, L. D. Whi e, Jr.
LDW:np
