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| {{#Wiki_filter:REGULATORY RNATION DlSTR IBUTlQN SYS'l (RIDS)ACCESSION NBR: 8707010156 DOC.DATE: 87/06/22 NOTARIZED: | | {{#Wiki_filter:REGULATORY RNATION DlSTR IBUTlQN SYS 'l (RIDS) |
| NO DOCKET 0 FACIL 50-244 Robert Emmet Qinna Nuclear Planti Unit ii Rochester G 05000244 AUD<.MANE AUTHOR AFFILIATION KOHEN'.W.Rochester Qas 8c Electric Corp.REC IP.MANE RECIPIENT AFFILIATION | | ACCESSION NBR: 8707010156 DOC. DATE: 87/06/22 NOTARIZED: NO DOCKET 0 FACIL 50-244 Robert Emmet Qinna Nuclear Planti Unit ii Rochester G 05000244 AUD<. MANE AUTHOR AFFILIATION KOHEN'. W. Rochester Qas 8c Electric Corp. |
| : STAHLE>C.Document Control Branch (Document Control Desk) | | REC IP. MANE RECIPIENT AFFILIATION |
| | : STAHLE> C. Document Control Branch (Document Control Desk) |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Informs NRC of status of mods being performed to address human engineering discrepancies (HEDs)identified in CRDR.Util found 252 out of 477 HEDs requiring remedial action.DIBTRIBUTION CODE: ADDED COPIEB RECEIVED: LTR J ENCL+SIZE: TITLE: OR/Licensing Submittal: | | Informs NRC of status of mods being performed to address human engineering discrepancies (HEDs) identified in CRDR. |
| Suppl 1 to NUREG-0737(Generic Ltr 82-33)NOTES: License Exp date in accordance eith lOCFR2i 2.109'(9/19/72). | | Util found 252 out of 477 HEDs requiring remedial action. |
| 05000244 RECIPIENT ID CODE/MANE PD1-3 LA STAHLEe C INTERNAL: A D LFNB FILE 01 EXTERNAL: LPDR NSIC CQP IES LTTR ENCL REC IP I ENT ID CODE/MANE PD1-3 PD NRR/DLPG/HFB RES DEPY GI NRC PDR COPIES LTTR ENCL 8 TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL tl 1 ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649-gggf ROGER W.KOBER vie osesioewv eLECTRK PRODVCTlOH June 22, 1987 YCLepHoNc ARCA Cooe 7II5 546 2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Mr.Carl Stahle PWR Project Directorate No.1 Washington, D.C.20555 | | DIBTRIBUTION CODE: ADDED COPIEB RECEIVED: LTR J ENCL + SIZE: |
| | TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33) |
| | NOTES: License Exp date in accordance eith lOCFR2i 2. 109'(9/19/72). 05000244 RECIPIENT CQP IES REC IP I ENT COPIES ID CODE/MANE LTTR ENCL ID CODE/MANE LTTR ENCL PD1-3 LA PD1-3 PD STAHLEe C INTERNAL: A D LFNB NRR/DLPG/HFB FILE 01 RES DEPY GI EXTERNAL: LPDR NRC PDR NSIC 8 |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL |
| | |
| | tl 1 |
| | |
| | ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-gggf ROGER W. KOBER YCLepHoNc vie osesioewv ARCA Cooe 7II5 546 2700 eLECTRK PRODVCTlOH June 22, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No. 1 Washington, D.C. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Control Room Design Review (CRDR)Status R.E.Ginna Nuclear Power Plant Docket No.50-244 | | Control Room Design Review (CRDR) Status R. E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Stahle:== |
| | |
| | The purpose of this letter is to inform you of the status of modifications being performed to address human engineering discrepancies (HEDs) identified in the Ginna Control Room Design Review (CRDR) Summary Report submitted to the Commission by a letter dated December 30I 1985. |
| | Four hundred and seventy-seven (477) HEDs were generated during the course of the CRDR review. Of these> two hundred and fifty-two (252) were declared by the RGGE CRDR Committee to require remedial action. Remedial action varied in effort from major modifications (e.g.i removal of the 115 kV panel from the control roomi installation of a new plant process computer and Safety Assessment System> installation of a new control room lighting systemi and incorporation of a complete main control board enhancement program) to training of the operators in such matters as the plant communication system and the use of the emergency operating procedures on the new plant specific simulator. |
| | In addition to the 252 HEDs that required remedial action, approximately 110 HEDsi such as those that addressed control room alarmsi controllersr annunciator designi addition of parameters to the plant process computer> indicator scalesi and annunciator tile design and layouti were to have further studies performed for ultimate re-review and disposition by the CRDR Committee. |
| | Originallyr the last of these studies was to be completed in 1988/ |
| | howeverr at the urging of the NRC Staff> these studies were accelerated and have now been completed. The results will be reported along with additional information requested by the Staff in a supplemental CRDR report to be submitted in July 1987. |
| | 870701 0156 870622 PDR ADQCN 05000244 P PDR |
| | |
| | <<(g W |
| | t |
| | |
| | The remaining HEDs< which did not require further evaluation or require remedial action< were classified by the CRDR Committee as requiring "no action" for a variety of reasons. |
| | To date, of the 252 action-required HEDs> 51 remain open> |
| | most of which are scheduled for completion by early 1988. |
| | However> for various reasons< including the accelerated schedule for completing evaluations< some tasks that were expected to be completed at this time are not yet complete. The following is a discussion of those tasks that have not been completed as scheduled including rescheduled completion dates. |
| | Several HEDs addressed individual problems with control board indicator scales. The problems were numerous enough to warrant a study of indicating scales in general to determine a uniform approach to the problem. In performing the study< our commitment was expanded from approximately 10 scales to approximately 70 new indicator scales. Installation of the new scales had originally been planned to be completed by April 1987. However< delivery of the new expanded list of scales is now expected to be in August 1987. Barring any unforeseen delay< installation will be comp-leted in September 1987. A "select" zone banding program for safety related indicators will be implemented upon completion of the new scale installations. |
| | Rheostat plates for emergency diesel generator automatic voltage control were to be installed during the refueling outage of 1987 as part of the many control board changes made in the paint< label and tape program. These plates are to be identical to those located on a recently installed local diesel generator control panel and are expected to be delivered in June 1987, at which time they will be installed. |
| | Several HEDs addressed the lack of labeling and the unconven-tional indicator movement of Foxboro controllers. Our original commitment was to complete a labeling program for the controllers during the 1987 spring outage. |
| | The ARD Corporation performed a controller study which resulted in several labeling suggestions. In addition> I6C personnel inves'- |
| | tigated an alternative solution to the unconventional indicator movement which consisted of replacing the present controllers on a one-for-one basis with a new controller. One of the new control-lers was mocked up in a control loop to provide the Operators an opportunity to become familiar with its characteristics. The Operators found the new controller to be unacceptable< and from a human factors standpoint> |
| | example> since each controller it was unreasonably has a self complicated. |
| | contained microprocessor'ix For control push buttons and three scales are located on the face of the controller. All scales and push buttons are required by ISC technicians for programming but only some of the push buttons and all scales are required by the operators for control. Based on |
| | |
| | "J |
| | ~ |
| | A l |
| | 4 - I 4 |
| | hi |
| | |
| | these results~ it was concluded that the appropriate action is to modify the present controllers as suggested by the ARD study< |
| | labels have been ordered and are expected to be delivered in June of 1987. Installation is to be completed by July of 1987. |
| | One HED addressed push button color coding and was thought to be minor in nature. However> upon reviewing all HEDs in prepar-ation for a Supplemental Report submittal< the review of this HED revealed that the Ginna push button color coding "convention" was not all encompassing. A more comprehensive "convention" is being established. This HED will be corrected during the 1988 refueling shutdown since corrective action will require modification to several function initiation push buttons. |
| | If you have any comments or questions< concerning our CRDR program> RG&E staff members are available to discuss the program with you. |
| | Ver truly yours> |
| | Roger N. Kober |
|
| |
|
| ==Dear Mr.Stahle:==
| | ~1 ~ |
| The purpose of this letter is to inform you of the status of modifications being performed to address human engineering discrepancies (HEDs)identified in the Ginna Control Room Design Review (CRDR)Summary Report submitted to the Commission by a letter dated December 30I 1985.Four hundred and seventy-seven (477)HEDs were generated during the course of the CRDR review.Of these>two hundred and fifty-two (252)were declared by the RGGE CRDR Committee to require remedial action.Remedial action varied in effort from major modifications (e.g.i removal of the 115 kV panel from the control roomi installation of a new plant process computer and Safety Assessment System>installation of a new control room lighting systemi and incorporation of a complete main control board enhancement program)to training of the operators in such matters as the plant communication system and the use of the emergency operating procedures on the new plant specific simulator.
| | t |
| In addition to the 252 HEDs that required remedial action, approximately 110 HEDsi such as those that addressed control room alarmsi controllersr annunciator designi addition of parameters to the plant process computer>indicator scalesi and annunciator tile design and layouti were to have further studies performed for ultimate re-review and disposition by the CRDR Committee.
| | 'I |
| Originallyr the last of these studies was to be completed in 1988/howeverr at the urging of the NRC Staff>these studies were accelerated and have now been completed.
| | ,1 |
| The results will be reported along with additional information requested by the Staff in a supplemental CRDR report to be submitted in July 1987.870701 0156 870622 PDR ADQCN 05000244 P PDR
| | 'A 0 |
| <<(g W t The remaining HEDs<which did not require further evaluation or require remedial action<were classified by the CRDR Committee as requiring"no action" for a variety of reasons.To date, of the 252 action-required HEDs>51 remain open>most of which are scheduled for completion by early 1988.However>for various reasons<including the accelerated schedule for completing evaluations<
| | I ll}} |
| some tasks that were expected to be completed at this time are not yet complete.The following is a discussion of those tasks that have not been completed as scheduled including rescheduled completion dates.Several HEDs addressed individual problems with control board indicator scales.The problems were numerous enough to warrant a study of indicating scales in general to determine a uniform approach to the problem.In performing the study<our commitment was expanded from approximately 10 scales to approximately 70 new indicator scales.Installation of the new scales had originally been planned to be completed by April 1987.However<delivery of the new expanded list of scales is now expected to be in August 1987.Barring any unforeseen delay<installation will be comp-leted in September 1987.A"select" zone banding program for safety related indicators will be implemented upon completion of the new scale installations.
| |
| Rheostat plates for emergency diesel generator automatic voltage control were to be installed during the refueling outage of 1987 as part of the many control board changes made in the paint<label and tape program.These plates are to be identical to those located on a recently installed local diesel generator control panel and are expected to be delivered in June 1987, at which time they will be installed.
| |
| Several HEDs addressed the lack of labeling and the unconven-tional indicator movement of Foxboro controllers.
| |
| Our original commitment was to complete a labeling program for the controllers during the 1987 spring outage.The ARD Corporation performed a controller study which resulted in several labeling suggestions.
| |
| In addition>I6C personnel inves'-tigated an alternative solution to the unconventional indicator movement which consisted of replacing the present controllers on a one-for-one basis with a new controller.
| |
| One of the new control-lers was mocked up in a control loop to provide the Operators an opportunity to become familiar with its characteristics.
| |
| The Operators found the new controller to be unacceptable<
| |
| and from a human factors standpoint>
| |
| it was unreasonably complicated.
| |
| For example>since each controller has a self contained microprocessor'ix control push buttons and three scales are located on the face of the controller.
| |
| All scales and push buttons are required by ISC technicians for programming but only some of the push buttons and all scales are required by the operators for control.Based on
| |
| ~"J A l 4-I 4 hi these results~it was concluded that the appropriate action is to modify the present controllers as suggested by the ARD study<labels have been ordered and are expected to be delivered in June of 1987.Installation is to be completed by July of 1987.One HED addressed push button color coding and was thought to be minor in nature.However>upon reviewing all HEDs in prepar-ation for a Supplemental Report submittal<
| |
| the review of this HED revealed that the Ginna push button color coding"convention" was not all encompassing.
| |
| A more comprehensive"convention" is being established.
| |
| This HED will be corrected during the 1988 refueling shutdown since corrective action will require modification to several function initiation push buttons.If you have any comments or questions<
| |
| concerning our CRDR program>RG&E staff members are available to discuss the program with you.Ver truly yours>Roger N.Kober
| |
| ~~1 t'I ,1'A 0 I ll}}
| |
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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 RNATION DlSTR IBUTlQN SYS 'l (RIDS)
ACCESSION NBR: 8707010156 DOC. DATE: 87/06/22 NOTARIZED: NO DOCKET 0 FACIL 50-244 Robert Emmet Qinna Nuclear Planti Unit ii Rochester G 05000244 AUD<. MANE AUTHOR AFFILIATION KOHEN'. W. Rochester Qas 8c Electric Corp.
REC IP. MANE RECIPIENT AFFILIATION
- STAHLE> C. Document Control Branch (Document Control Desk)
SUBJECT:
Informs NRC of status of mods being performed to address human engineering discrepancies (HEDs) identified in CRDR.
Util found 252 out of 477 HEDs requiring remedial action.
DIBTRIBUTION CODE: ADDED COPIEB RECEIVED: LTR J ENCL + SIZE:
TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33)
NOTES: License Exp date in accordance eith lOCFR2i 2. 109'(9/19/72). 05000244 RECIPIENT CQP IES REC IP I ENT COPIES ID CODE/MANE LTTR ENCL ID CODE/MANE LTTR ENCL PD1-3 LA PD1-3 PD STAHLEe C INTERNAL: A D LFNB NRR/DLPG/HFB FILE 01 RES DEPY GI EXTERNAL: LPDR NRC PDR NSIC 8
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL
tl 1
ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-gggf ROGER W. KOBER YCLepHoNc vie osesioewv ARCA Cooe 7II5 546 2700 eLECTRK PRODVCTlOH June 22, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No. 1 Washington, D.C. 20555
Subject:
Control Room Design Review (CRDR) Status R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
The purpose of this letter is to inform you of the status of modifications being performed to address human engineering discrepancies (HEDs) identified in the Ginna Control Room Design Review (CRDR) Summary Report submitted to the Commission by a letter dated December 30I 1985.
Four hundred and seventy-seven (477) HEDs were generated during the course of the CRDR review. Of these> two hundred and fifty-two (252) were declared by the RGGE CRDR Committee to require remedial action. Remedial action varied in effort from major modifications (e.g.i removal of the 115 kV panel from the control roomi installation of a new plant process computer and Safety Assessment System> installation of a new control room lighting systemi and incorporation of a complete main control board enhancement program) to training of the operators in such matters as the plant communication system and the use of the emergency operating procedures on the new plant specific simulator.
In addition to the 252 HEDs that required remedial action, approximately 110 HEDsi such as those that addressed control room alarmsi controllersr annunciator designi addition of parameters to the plant process computer> indicator scalesi and annunciator tile design and layouti were to have further studies performed for ultimate re-review and disposition by the CRDR Committee.
Originallyr the last of these studies was to be completed in 1988/
howeverr at the urging of the NRC Staff> these studies were accelerated and have now been completed. The results will be reported along with additional information requested by the Staff in a supplemental CRDR report to be submitted in July 1987.
870701 0156 870622 PDR ADQCN 05000244 P PDR
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The remaining HEDs< which did not require further evaluation or require remedial action< were classified by the CRDR Committee as requiring "no action" for a variety of reasons.
To date, of the 252 action-required HEDs> 51 remain open>
most of which are scheduled for completion by early 1988.
However> for various reasons< including the accelerated schedule for completing evaluations< some tasks that were expected to be completed at this time are not yet complete. The following is a discussion of those tasks that have not been completed as scheduled including rescheduled completion dates.
Several HEDs addressed individual problems with control board indicator scales. The problems were numerous enough to warrant a study of indicating scales in general to determine a uniform approach to the problem. In performing the study< our commitment was expanded from approximately 10 scales to approximately 70 new indicator scales. Installation of the new scales had originally been planned to be completed by April 1987. However< delivery of the new expanded list of scales is now expected to be in August 1987. Barring any unforeseen delay< installation will be comp-leted in September 1987. A "select" zone banding program for safety related indicators will be implemented upon completion of the new scale installations.
Rheostat plates for emergency diesel generator automatic voltage control were to be installed during the refueling outage of 1987 as part of the many control board changes made in the paint< label and tape program. These plates are to be identical to those located on a recently installed local diesel generator control panel and are expected to be delivered in June 1987, at which time they will be installed.
Several HEDs addressed the lack of labeling and the unconven-tional indicator movement of Foxboro controllers. Our original commitment was to complete a labeling program for the controllers during the 1987 spring outage.
The ARD Corporation performed a controller study which resulted in several labeling suggestions. In addition> I6C personnel inves'-
tigated an alternative solution to the unconventional indicator movement which consisted of replacing the present controllers on a one-for-one basis with a new controller. One of the new control-lers was mocked up in a control loop to provide the Operators an opportunity to become familiar with its characteristics. The Operators found the new controller to be unacceptable< and from a human factors standpoint>
example> since each controller it was unreasonably has a self complicated.
contained microprocessor'ix For control push buttons and three scales are located on the face of the controller. All scales and push buttons are required by ISC technicians for programming but only some of the push buttons and all scales are required by the operators for control. Based on
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these results~ it was concluded that the appropriate action is to modify the present controllers as suggested by the ARD study<
labels have been ordered and are expected to be delivered in June of 1987. Installation is to be completed by July of 1987.
One HED addressed push button color coding and was thought to be minor in nature. However> upon reviewing all HEDs in prepar-ation for a Supplemental Report submittal< the review of this HED revealed that the Ginna push button color coding "convention" was not all encompassing. A more comprehensive "convention" is being established. This HED will be corrected during the 1988 refueling shutdown since corrective action will require modification to several function initiation push buttons.
If you have any comments or questions< concerning our CRDR program> RG&E staff members are available to discuss the program with you.
Ver truly yours>
Roger N. Kober
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