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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M0721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Pass Dates ML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L0061999-10-0101 October 1999 Discusses GL 97-06 Issued by NRC on 971231 & Gpu Response for Three Mile Island .Staff Reviewed Response & Found No New Concerns with Condition of SG Internals or with Insp Practices Used to Detect Degradation of SG Internals ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212K8771999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Three Mile Island on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Provides Historical Listing of Plant Issues & Insp Schedule ML20212K8551999-09-30030 September 1999 Informs That During 990921 Telcon Between P Bissett & F Kacinko,Arrangements Were Made for Administration of Licensing Exams at Facility During Wk of 000214.Outlines Should Be Provided to NRC by 991122 ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211A4261999-08-19019 August 1999 Forwards Insp Rept 50-289/99-04 on 990606-0717.Two Severity Level 4 Violations Occurred & Being Treated as Noncited Violations ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210N7601999-08-10010 August 1999 Informs That NRC Staff Reviewed Applications Dtd 990629, Which Requested Review & Approval to Allow Authority to Possess Radioactive Matl Without Unit Distinction Between Units 1 & 2.Forwards RAI Re License Amend Request 285 ML20210N7191999-08-0606 August 1999 Forwards Notice of Partial Denial of Amend to FOL & Opportunity for Hearing Re Proposed Change to TS 3.1.12.3 to Add LCO That Would Allow Continued HPI Operation ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210B8231999-07-21021 July 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) for Three Mile Island Nuclear Station,Unit 2 in Response to Licensee Application Dtd 990309,requesting Reduction in Amount of Insurance for Unit to Amount Listed ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20209H9401999-07-15015 July 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Application for Exemption Dtd 990309. Proposed Exemption Would Reduce Amount of Insurance for Onsite Property Damage Coverage as Listed ML20209G2451999-07-15015 July 1999 Advises That Suppl Info in Support of Proposed License Transfer & Conforming Adminstrative License Amends,Submitted in & Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident ML20216D9861999-07-12012 July 1999 Forwards RAI Re 981019 Application Request for Review & Approval of Operability & SRs for Remote Shutdown Sys. Response Requested within 30 Days of Receipt of Ltr ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209D8451999-07-0808 July 1999 Forwards Insp Rept 50-289/99-06 on 990608-11.No Violations Noted.Overall Performance of ERO Very Good & Demonstrated, with Reasonable Assurance,That Onsite Emergency Plans Adequate & That Util Capable of Implementing Plan ML20209D6291999-07-0808 July 1999 Forwards Notice of Withdrawal & Corrected TS Pages 3-21 & 4-9 for Amend 211 & 4-5a,4-38 & 6-3 for Amend 212,which Was Issued in Error.Amends Failed to Reflect Previously Changes Granted by Amends 203 & 204 ML20209D5141999-07-0808 July 1999 Forwards RAI Re 981019 Application & Suppl ,which Requested Review & Approval of Revised Rc Allowable Dose Equivalent I-131 Activity Limit with Max Dose Equivalent Limit of 1.0 Uci/Gram.Response Requested within 30 Days 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License ML20196J7651999-06-29029 June 1999 Provides Updated Info Re Loss of Feedwater & Loss of Electric Power Accident Analyses to Support TS Change Request 279 Re Core Protection Safety Limit,As Discussed at 990616 Meeting ML20196J7701999-06-29029 June 1999 Forwards LAR 285 for License DPR-50,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20209C0391999-06-29029 June 1999 Forwards LAR 77 to License DPR-73,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-2 License to Amergen,Radioactive Matl May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20196G2061999-06-23023 June 1999 Requests That NRC Update Current Service Lists to Reflect Listed Personnel Changes That Occurred at TMI 05000289/LER-1999-006, Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements1999-06-23023 June 1999 Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements ML20196D2171999-06-17017 June 1999 Forwards Pmpr 99-9, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508- 0604.New Summary Personnel Table Was Added to Rept Period.Matl Scientist Joined Staff Period ML20196A0431999-06-15015 June 1999 Providess Notification That Design Verification Activities Related to Calculations Supporting Analytical Values Identified in Gpu Nuclear Ltr to NRC Has Been Completed 05000289/LER-1999-004, Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT1999-06-0909 June 1999 Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT ML20212K2541999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20212K2671999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20195E2751999-06-0404 June 1999 Informs That PCTs & LOCA Lhr Limits Submitted in Util Ltr for LOCA Reanalysis Performed in Support of TMI-1 20% Tube Plugging Amend Request Have Been Revised.Revised PCT & LOCA Lhr Limit Values Are Provided on Encl Table 1 ML20195E3281999-06-0404 June 1999 Forwards Application for Amend to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20195C5721999-06-0202 June 1999 Forwards Description of Gpu Nuclear Plans for Corrective Actions for 1 H Fire Barriers in Fire Zones AB-FZ-3,AB-FZ-5, AB-FZ-7,FH-FZ-2 & Previous Commitments for Fire Zones CB-FA-1 & FH-FZ-6 ML20207E2561999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Change in ECCS Analyses at TMI-1 ML20195B2461999-05-21021 May 1999 Forwards Itemized Response to NRC 990506 RAI for TS Change Request 279 Re Core Protection Safety Limit ML20206R6461999-05-13013 May 1999 Forwards Rev 39 of Modified Amended Physical Security Plan for TMI 05000289/LER-1999-003, Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC1999-05-0707 May 1999 Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC ML20206K6301999-05-0707 May 1999 Provides Addl Info Re TMI-1 LOFW Accident re-analysis Assumptions for 20% Average SG Tube Plugging as Discussed on 990421 ML20206H0781999-04-30030 April 1999 Forwards Rev 0 to 1092, TMI Emergency Plan. Summary of Changes Encl ML20206J4811999-04-30030 April 1999 Provides Summary of Activities at TMI-2 During First Quarter of 1999.TMI-2 RB Was Not Inspected During Quarter.Routine Radiological Surveys of Auxiliary & Fuel Handling Bldgs Did Not Identify Any Significant Adverse Trends ML20206E4121999-04-27027 April 1999 Requests That TS Change Request 257 Be Withdrawn ML20206C5211999-04-23023 April 1999 Requests Mod to Encl Indemnity Agreement Number B-64,on Behalf of Gpu & Affiliates,Meed,Jcpl,Penelec & Amergen Energy Co,Llc.Ltr Supersedes & Withdraws 990405 Request Submitted to NRC ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H5351990-09-10010 September 1990 Forwards Encls 1-3 of Generic Ltr 90-07 Re Operator Licensing Exam Schedule ML20059G0641990-08-31031 August 1990 Advises That Util Agreed to Revised Frequency of Once Every 12 Months for Corrective Actions Audits Per Tech Spec Change Request 65 Based on 900718 & 19 Discussions ML20059F1691990-08-30030 August 1990 Requests Exemption from Requirements of 10CFR50,App J, Section III.D.1(a) for Facility Re Schedule Requirements for Connecting Type a Testing w/10-yr Inservice Insp Interval, Per 10CFR50.12(a)(2) ML20064A4661990-08-30030 August 1990 Responds to 900803 SALP Rept 50-289/89-99.TMI Does Not Expect to Be Lead Plant for Installation of Advanced Control Sys.Maint Backlog Goals Established.Info on Emergency Preparedness & Engineering/Technical Support Encl ML20059C8791990-08-29029 August 1990 Forwards TMI-1 Semiannual Effluent & Release Rept for Jan - June 1990, Including Executive Summary of Effluent Release Rept,Disposal & Effluent Release Data & Assessment of Radiation Doses.No Changes to ODCM for Reporting Period ML20059D5491990-08-29029 August 1990 Responds to NRC Re Notice of Violation & Proposed Imposition of Civil Penalty Re Personnel Inattentiveness & Failure of Site Managers to Correct Condition.Shift & Immediate Supervisor Discharged ML20059C7851990-08-27027 August 1990 Forwards Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility, Updating Minor Changes to Pages 6,8,9 & 13 ML20059C1091990-08-24024 August 1990 Forwards Rev 6 to Physical Security Contingency Plan.Rev Withheld ML20059B8251990-08-24024 August 1990 Forwards Payment of Civil Penalty in Amount of $50,000,per NRC ML20056B4651990-08-20020 August 1990 Corrects Statement Made in 900716 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Rosemount Transmitters. Identified That Only Half of Operating Crews Provided W/ Briefing on Bulletin ML20058Q1851990-08-17017 August 1990 Requests That Distribution List for TMI-2 Correspondence Be Updated to Be Consistent W/Recently Implemented Organizational Changes.Ee Kintner,Mb Roche & Wj Marshall Should Be Deleted ML20058Q1721990-08-13013 August 1990 Forwards TMI-2 Effluent & Offsite Dose Rept,First Quarter 1990, Update ML20058Q1821990-08-13013 August 1990 Advises That Util Will No Longer Provide Annual Update to Dewatering Sys for Defueling Canisters Sys Description,Per NRC .W/Completion of Defueling & Shipment of All Defueling Canisters Offsite,Sys Has Been Deactivated ML20058M7201990-08-0303 August 1990 Forwards Rev 2 to TER 3232-019, Div Technical Evaluation Rept for Processed Water Disposal Sys. Mods Include Elimination of Pelletizer & Relocation of Druming Station to Discharge of Blender/Dryer ML20055J4581990-07-27027 July 1990 Responds to Violations Noted in Insp Rept 50-289/90-10. Corrective Actions:Missing Support Brace on Cable Tray Support Found & Corrected ML20055J4561990-07-27027 July 1990 Advises That Info Contained in Generic Ltr 90-06,not Applicable to Current Nonoperating & Defueled Condition of Facility.Generic Ltr Will Be Reevaluated,If Decision Made to Restart Facility ML20055H6901990-07-20020 July 1990 Forwards Rev 25 to TMI-2 Organization Plan for NRC Review & Approval.Rev Proposes Consolidation of Plant Operations & Maint Sections Into Plant Operation & Maint Section ML20055G4431990-07-19019 July 1990 Forwards Rev 12 to 990-1745, TMI-1 Fire Hazards Analysis Rept & Update 9 to FSAR for TMI-1 ML20055G8781990-07-19019 July 1990 Discusses Compliance W/Reg Guide 1.97 Re Containment High Range Radiation Monitors,Per 900507-11 Insp.Physical Separation of Power Cables & Required Isolation Will Be Provided to Satisfy Reg Guide Category 1 Requirements ML20055F9601990-07-11011 July 1990 Forwards, 1990 TMI Nuclear Station Annual Emergency Exercise Scenario to Be Conducted on 900912.W/o Encl ML20044A9531990-07-0909 July 1990 Forwards Util Response to Weaknesses Identified in Maint Team Insp Rept 50-289/89-82.Corrective Actions:Engineering Personnel Reminded to Assure Documented Approval Obtained Prior to Proceeding W/Work ML20055E0481990-07-0505 July 1990 Documents Action Taken by Util to Improve Heat Sink Protection Sys & Current Status of Sys.Main Feedwater Logic Circuits Modified Prior to Startup from 8R Outage to Eliminate Potential for Inadvertent Isolation ML20055E0011990-07-0202 July 1990 Forwards Revs 1 & 2 to Topical Rept 067, TMI-1 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.5.4 ML20055C9971990-06-28028 June 1990 Forwards Rev 27 to Physical Security Plan.Rev Withheld ML20055D2071990-06-28028 June 1990 Forwards Certification of TMI-1 Simulation Facility,Per 10CFR55.45.b.5.Resumes of Personnel Involved Encl. Resumes Withheld (Ref 10CFR2.790(a)(6)) ML20055D0861990-06-25025 June 1990 Documents Deviation from Requirements of Reg Guide 1.97,per Insp on 900507-11.Based on Most Limiting Analysis,Existing Range of 0-1,200 Psi Sufficient.Deviation Consistent W/B&W Owners Group Task Force Evaluation of Reg Guide ML20043H4851990-06-18018 June 1990 Forwards Application for Amend to License DPR-50,consisting of Tech Spec Change Request 179 ML20043H4031990-06-18018 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements or Corrective Actions. ML20043F9921990-06-11011 June 1990 Forwards Listing of Exam Ref Matl Sent on 900601 in Response to 900505 Ltr ML20043F0661990-06-0404 June 1990 Forwards Inservice Insp Data Rept for Period 880816-900304. Owner Rept for Repairs or Replacements Performed on ASME Section XI Class 1 & 2 Components,Also Encl ML20055C9041990-05-23023 May 1990 Advises That App a to Rept Is Set of Recommendations from Safety Advisory Board on Possible Research Opportunities ML20043B2391990-05-18018 May 1990 Revises Commitments in Encl Met Ed 800430 Ltr Re QA of Diesel Generator Fuel Oil.Requirement for QC Review for Acceptability Prior to Filling Diesel Generator Fuel Oil Storage Tanks Deleted from Procedure ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5311990-05-15015 May 1990 Responds to Violations Noted in Insp Rept 50-289/89-82. Corrective Actions:Periodic Insp Program Established Utilizing Checklist for Stored Equipment & Existing Tool Rooms Will Be Purged of Controlled or Unneeded Matls ML20043A2321990-05-11011 May 1990 Forwards TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5) Technical Rept 069.Evaluations Conclude That Test & Insp Results Demonstrate TMI-1 Reactor Bldg post- Tensioning Sys in Good Condition ML20042G2741990-05-0404 May 1990 Forwards Semiannual Update of Projects Listed in Categories A,B & C of long-range Planning Program Integrated Schedule ML20012F2621990-04-0202 April 1990 Responds to Violation Noted in Insp Rept 50-289/89-26. Corrective Actions:Util Policy of Shift Supervisor Involvement in Bypassing & Resetting Safety Sys Expanded to Include Shutdown Conditions & Technicians Briefed ML20012F2611990-04-0202 April 1990 Provides Supplemental Response to Station Blackout Rule. Target Reliability of 0.975 Chosen for Emergency Diesel Generators.Diesel Generator Reliability Program May Change Based on Final Resolution of Generic Issue B-56 ML20012F2731990-03-30030 March 1990 Confirms 900328 Conversations & Provides Technical Basis for Planned Actions to Correct Present Power Limitation Due to High Steam Generator Secondary Side Differential Pressure. Main Turbine Will Be Tripped from 80% Power ML20042D8281990-03-23023 March 1990 Fulfills Requirements of Tech Spec Section 4.19.5.a Re once-through Steam Generator Tubes post-inservice Insp Rept for Unscheduled Outage 8U-1 ML20012D7001990-03-22022 March 1990 Forwards Util Response to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Site Mgt & Staff Hour Categories Added to Response ML20012D7121990-03-21021 March 1990 Forwards Rev 0 to TMI-1 Cycle 8 Core Operating Limits Rept. ML20012C4771990-03-12012 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f). Current Design Adequate W/O Addl Tech Specs ML20012B8241990-03-12012 March 1990 Forwards Application for Tech Spec Change Request 199 to License DPR-50,revising Tech Specs Re Steam Generator Tube Insp Requirements ML20055C3931990-02-23023 February 1990 Documents Interpretation of Tech Spec 4.19.5.a Re once- Through Steam Generator Tube post-inservice Insp Rept for Refueling Interval 8R.Total of Eight Tubes Removed from Svc by Plugging ML20011F5251990-02-23023 February 1990 Documents Interpretation of Tech Spec 5.3.1.1 Re Design Features of Fuel Assemblies in Light of Issuance of Generic Ltr 90-02.Tech Spec Change Request Re Utilization of Dummy Fuel Rods or Open Water Channels Will Be Filed by 900420 ML20011F6651990-02-22022 February 1990 Forwards Updated Status Summary of Consideration of TMI-1 PRA Recommendations as of 891231.Changes to Torque Switch Settings for DH-V-4A & B Will Be Implemented in Refueling Outage 8 Re Closing Against High Differential Pressure ML20006C2901990-01-26026 January 1990 Provides Addl Info Supporting Deferral of Seismic Qualification Util Group Walkdowns to 10R Outage.Performance of Walkdowns Provide Proper Scheduling & Priority for Resolution of USI A-46 for TMI-1 ML20011E1221990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Audit Rept Determined That Operation of Decay Heat Closed Cooling Water Sys Consistent W/Design Basis Documents ML19354E8601990-01-25025 January 1990 Requests Approval for Use of B&W Steam Generator Plugs Mfg W/Alternate Matl (nickel-base Alloy/Alloy 600).Alloy 600 Has Superior Corrosion Resistance to Primary Water Stress Corrosion Cracking 1990-09-10
[Table view] |
Text
-
NRC ,snu 195 '
U.S. NUCLEAR HEGULATORY Cs ilSSloN DOCKET NUM6E R 4 24* ' - - 50-289
^
NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL To: K. R. Coller FROM: Met. Edison Co. DATE OF DOCUMENT Reading, Pa. 19603 3~9"77 P..C. Arnold DATE RECEIVE D ,
3-11-77 3 LETTER O NOTO RIZ E D PROP INPUT FORM NUMBER OF COPIES RECEIVED EOniclNAL S U NC L ASSIFIE D 1 gigned '
OCOPy ,
oesCRIPTION Ltr furn addl info to Change Request EN CLOSU RE Revised table 3.16-1 entitled " Safety No. 19, Amdt 2 to tech apeCs regarding Related Shock Suppressors"....(ISP) _
shock suppressors & trans the following:
(2P) (1 Cy enc 1 rec,d) '
I NOT REMOVE __
PLANT NAME: Three Mile Island Unit 1 ,
CKNOWLEDGED; 1480 299 SAFETY FOR ACTION /INFORMATION vmrTon 4 ASSIGiED AD: - A49TcWn An.
/ BRANCH CHIEF! Md e i [ 6) unAMeu cuTvv.
/ PROJECT MANAGER: 2r.us.f C ( PROJECT MANAGER:
/ LIC. ASST. : L 4 4 E as LIC. ASST. :
i A INTERNAL DISTRIBUTION i
[ REG FILb T SYSTEMS SAFETY i PLANT SYSTEMS SITE SAFETY G !
( HRC l'DR llEINEMAN TEDESCO ENVIRO ANAT_YSIS '
/ I & E ( 2. ) '
SCHROEDER BENAROYA DENTON & MUr T r t i
/ OELD YATNAR '
/ GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH. I MIPC MACARRY KIRKWOOD ERNST CASE BOSNAK BALLARD HANAUER SIHWEIL OPERATING REACTORS YOUNGBLOOD i HARLESS PAWLICKI STELLO !
SITE idCH. I PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH. GAMMILL BOYD ROSS / EISENHITT STEPP P. COLLINS NOVAK / SHA0 HULMAN HOUSTON ROSZTOCZY / BAER
- PETERSON CHECK / BITTLER SITE ANALYSIS i MELTZ / CRIMES VOLLMER !
HE,LTEMES AT & I BUNCH I SKOVHOLT SALT 7 MAN / J. COLLINS i RUTEERG KREGER I EXTERNAL DISTRIBUTION CONTROL NUMBE 9 4LPDR:N,,edt,n./4 _NAT, LAB: BROJ}31AVEN R\T. I.AR.
/ TIC:
REG V.IE ULRIKSON (ORNL) '7 910 P.,9 07 8 'l
{ NSIC: IA_PDR A_SLB_: _ _
/ ACR_S /(o CYS lict9INC/ 3E! TN5
. CONSULTANTS:
CM /3 ggKg y/g [
NRC FORM 195(2 76)
/
=,
A2M METHOPOLIIAN EDISON COMPANY POST OFFICE BOX 542 READING, PENNSYLVANIA 19603 TELEPHONE 215 - 929-3601 March 9, 1977 -
" 288 Regulatory Docket File Director of Nuclear Reactor Regulation 3,,,
Attn: Karl R. Goller, Assistant Director ,,
for Operating Reactors '< - ,
Division of Operating Reactors e%(
O U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ?>ll
~ "
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Docket No. 50-289 Operating License No. DPR-50 By letter dated February 17, 1977, you transmitted to us proposed changes to our Technical Specification Change Request No. 19, Amendment 2, regarding shock suppressors (snubbers), noting that unless we inform you in writing within twenty (20) days of any disagreement, you plan "to initiate steps to issue the enclosed change to the Technical Specifications of TMI-1".
We find all the proposed changes acceptable except those related to Section h.lT.l.
After further review by our safety committees and Engineering Department, we still maintain that conformance to our proposed Section h.lT.1 will provide quite adequate assurance of hydraulic snubber operability for TMI-1.
In support of this positien, we must point out that in 19Th we committed to inspect all safety-related snubbers every 120 days and we have diligently ecmplied with that commitment if plant conditions permit it, or during the first reactor shutdown thereafter. In one instance, due to highly reliable plant operation, reactor criticality and the attendant radiation levels did not permit the 120 days inspection interval to be met for those inaccessible snubbers. On this occasion, the plant operated for 170 days between snubber inspections. Following this period of plant operation, one inaccessible snubber was found to be isoperable due to faulty assembly and installation, which resulted in a loss of hydraulic fluid. As stated in the NRC Safety Evaluation supporting an amendment to our request, loss of hydraulic fluid does not prevent hydraulic snubbers frcm supporting associated piping or ecmpenents or from reducing their motion during a seismic event. In addition, as there were eight other snubbers on this line and two within seven (7) feet of the inoperable snubber, and due to the conservative design of this line, we are confident that no failure would have occurred even if there had been a seismic event.
1480 300
~.,u6. u
TABLE 3.16.1 Pace 2 of 15
--~~
SAFETY RELATFD SHOCK SUPPRESSORS ( SNUBBERS) w.
CD .
O Snuleber In Snubber Snubbers Snubbers M High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal Puring Normal MK No. Location Elevation Shutdown
- To Remove Operation Operation Ex. Bldg. Inside Sec. Shield RC- 13 321 No No Yes No H.E. Quad. -
Ex. Bldg. Inside Sec. h ld RC-lh 321 No No Yes No H.E. Quad 11x . Bldg. Inside Sec. Shield MUE-38 318 No No Yes No H.E. Quad.
MUE-39 Ex, Bldg. Inside Sec. Shield 318 No Ho Yes No U.K. Quad.
Rx. ldg. Inside Sec. Shield PR-23 3h 0 gO Ho Yes No H.E. Quad. RC-RV-1A Disch. Line Rx. Bldg. Inside Sec. Shield PR-2h 340 No Ho Yes No fl.E. Quad. RC-HV-1A Disch. Line Ex. Bldg. Inside Sec. Shield PR-25 340 No Ho Yes No U.E. Quad. RC-RV-1B Disch. Line Ex. Bldg. Inside Sec. Shield PR-26 3h0 nO Ho Yes No H.E. Quad. RC-RV-lH Disch. Line Ex. Bldg. Inside Sec. Shield PR-34 345 tIO No Yes No U.E. Quad. RC-RV-1A Disch. Line Ex. Bldg. Inside Sec. Shield PR-36 3h5 NO Ho Yes No H.E. Quad. RC-RV-1A Disch. Line Rx. Bldg. Inside Sec. Shield
"~ No Ho Yes No H.E. Quad. RC-RV-1B Disch. Line Ex. Bldg. Inside Se . Shield PR-37 345 No Ho Yes No H.E. Quad. RC-RV-1B Disch. Line pp_h7 Ex. Bldg. Inside Sec. Shield H.E. Quad. RC-RV-2 Disch. Line 355 No Ho yes no ] g lix . Bldg. Inside Sec. Shield PR-h8 355 NU Ho Yes No U.E. Quad. RC-RV-2 Disch. Line Ex. Bldg. Inside Sec. Shield USE-77 333 No Ho Yes No H.E. Quad.
Itx. Bldg. Inside Sec. Shield USE-78 334 No No Yes No H.E. Quad. 3 Rx. Bldg. Inside Sec. Shield USE-79 331 Ho Ho Yes No U.E. Quad.
Ex. b1dg. Inside Sec. 3hield USE-75 H.E. Quad. B2 h h h h
"E" TABLE 3.16.1 SAFETY REIATED SHOCK SUPPRESSORS ( SNUBBERS)
Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal
!E No. Location Elevation Shutdown
- To Remove Operation Operation Ex. Bldg. Inside Sec. Shield W-110 325 Ho Yes Yes No S.E. Quad.
- Bldg. Inside Sec. Shield faIE-20 S.E,. Quad. No Ho Ys No Rx. Bldg. Inside Sec. Shield
' 69 310 Yes Yes No S.E. Quad. No 1x. Bldg. Inside Sec. Shield NSE-85 332 Yes Yes Ho H.W. Quad. Ho
- x. B1 g. nside Sec. Shield USE-86 331 Yes Yes No H.W. Que.d. No Rx. Bldg. Inside Sec. Shield HSE-87 331 Yes Yes No H.W. Quad. No Rx. Bldg. Inside Sec. Shiel.d USE-88 33h Yes Yes do H.W. Quad. No I x. Bldg. Inside Sec. Shield USE-131 33h Ho Yes No N.W. Quad. No Rx. Bldg. Inside Sec. Shield USE-132 334 Ho Ho Yes No H.W. Quad.
"** O C' "*'d* U"
- U"I"Id USE-133 334 NO Ho Yes No U.W. Quad.
Rx. Bldg. Inside Sec. Shield USE-138 331 No Yes Yes No U.W. Quad.
USE-lh1
"** E' "" " ' "" 331 Ho Yes No U.W. Quad. nU Rx. dg. Inside Sec. Shield USE-lh2 331 nO Ho Yes No U.W. Quad.
Rx. B1 g. nside e . h ld faIE-43 310 gO No Yes No U.W. Quad.
IRJE l lti Rx. Bldg. Inside Sec. Shield 310 Ho Ho Yes No fl.W. Quad.
Ex. Bldg. Inside Sec. Shield 12 310 No No Yes No N.W. Quad.
CF-16
- C' "I* * * "" 310 Ho No Yes Ho H.W. Quad.
Ex. g. nie e . hed CF-16A 316 No No Yes no H.W. O.uad.
1480 302
Page 3 or 15 TABLE 3.16 1 SAFETY HEIATED Silo.CK SUPPRESSORS ( StrJBBERS) ,
Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During No. cal MK Ho . Location Elevation Shutdown
- To Remove Operation Operation NSE-76 Rx. Bldg. Inside Sec. Shield 332 No No Yes No N.E. Quad.
NSE-103- 334 No No Yes No N.E. Quad.
Rx. Bldg. Inside Sec. Shield USE-104 334 No No Yes No N.E. Quad.
Ex. Bldg. Inside Sec. Shield Yes No j NSE-105 334 No No k N.B. Quad.
"** bl U* " d* * * *1 NSE-108 334 No No Yes No U.E. Quad.
Ex. Bldg. Inside Sec. Shield NSE-110 331 No No Yes No N.E. Quad.
Rx. Bldg. Inside Sec. Shield Yes NSE-ll2 332 No No Nc-N.E. Quad. _
N** Uldd* "*'d* "* "I'ld NSE-ll3 338 No No Yes No N.E. Quad.
Itx. Bldg. Inside Se . Shield MS-201 338 No Yes Yes No N.E. Quad.
Ex. Bldg. Inside Sec. Shield NSE-80 332 No No Yes No S.E. Quad.
- C* "i* ** h NSE-81 331 No No Yes No S.E. Quad.
Ex. Bldg. Inside Sec. Shield NSE-82 331 No No Yes No S.E. Quad.
Ex. Bldg. Inside Sec. Shield d l NSE-96 338 No No Yes No 8.E. Quad.
Ex. Bldg. Inside Sec. Shield NSE-96A 338 No No Yes No S.E. Quad.
.c. Bldg. Inside Sec. Shield HSE-151 334 No No Yes No S.E. Quad.
h** 8 6* "1
- No USE-153 331 No Yes No S.E. Quad.
Ex. Bldg. Inside Sec. SMeld EF-ll6 330 No No Yes No S.E. Quad.
Ex. Bldg. Inside Sec. Shield FW-109 325 NO Yes Yes No S.E. Quad.
.80 303
"r. K. Boller, URC 2 3/9/77 GQL 0288 Most of the hydraulic snubbers' failures experienced at TMI-1 have resulted in loss of fluid. These failures are in the conservative direction since loss of fluid does allow free movement of the snubber piston and, therefore, no stress is placed cn the affected piping and/or ecmponents due to piston lock-up during thermal growth (1). Similar isolated failures can be expected to occur over the operating life of the plant. As few as two or three such failures could impose an arbitrary inspection interval on inaccessible snubbers which, during continued reliable plant operation, could only be satisfied by a reactor shutdown solely for this inspection purpose, regardless of the cause of those failures. We feel that this arbitrary inspection interval may not, in all cases, be sole and sufficient justification from a nuclear safety or economic standpoint to warrant reactor shutdown and otherwise, unnecessary reactor plant cycling. Reactor shutdovrs performed with the only purpose to inspect inaccessible snubbers shall be limited to those occasions where snubber failures strongly suggest the possibility of equipment design deficiencies, procedure inadequacies, or poor maintenance practices. As was stated in our Change Request No. 19, Amendment 2, we continue to believe that adherence to an arbitrary periodic inspection interval may be unnecessary frcm a nuclear safety standpoint and may have an unnecessarily harsh effect on plant operation.
TMI-l completed a very extensive snubber seal replacement program in May, 1976, which replaced all seal materials which had been demoi.strated to be incompatible with their operating environment with ethylene propylene seals.
Only one snubber failure has been discovered since, the failure due to improper installation. While this extensive program should greatly improve the operability of hydraulic snutbers, we agree, from cur operating experience and our knowledge of other plant operating experience, with the URC assessment in the Safety Evaluation supporting an amendment to our request that some failures continue to occur and are generally attributable to faulty assembly and installation causes similar to the one cited above. We also concur that snubber operability and surveillance requirements have a place in Technical Specifications, however, we strongly differ in that arbitrary inspection surveillance requirements which may not reflect specific plant problems should not by themselves govern plant operation. As discussed in the ACRS 196th General Meeting (page 2h9, lines 15-21), snubber reliability is strcngly dependent on plant-related factors. We therefore request the retention of the text of Section h.17.1 as submitted in our proposals.
In addition, we are submitting a revised Table 3.16.1 which more clearly specifies the proposed inspection schedule to be followed with hydraulic snubbers classified as "especially difficult to remove".
(1) Only one snubber piston lock-up has been experienced at TMI-1. The failure (A0 75-08) was due to painting of the piston surface, in violation of the manufacturer's instruction, during plant construction.
Sincerely, r
a? '
R. C.'^r"
- Vice president 1480 3N RCA:JMC:eg
Attachment:
Revised Table 3 16.1 for Technical Specification Change Request Lo, 19, A=enament 2.
TABLE 3.16.1 Pure 1 of 15 SAFifl'Y liEIW1Mi PHOCK SUPI'RESSoltS ( SNUBBERS)
Snubber in Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Formal During Normal MK Ho. Location Elevation Shutdown" To Remove Operation Operation R.B. Inside Sec. Shield RC-h 355 Ho Yes Yes No U.E. Quad.
I x. Bldg. Inside Sec. Shield RC-5 355 No Ho Yes No H.E. Quad. Top of PZR Near RC-V3 Rx. Bldg. Inside Sec. Shield pg_g 355 No Ho Yes No N.E. Quad. Top of PZR Near RC-V3 Itx. Bldg. Inside S . Shield RC-16 355 No Yes No U.E. Quad. Top of PZR Hear RC-V3 Ho Rx. Bldg. Inside Sec. Shield RC-17 355 Ho Yes No H.E. Quad. Hear RC-V1 No Rx. Bldg. Inside Sec. Shield
"- N.E. Quai. Hear RC-VI 355 No No J Yes No Itx . Bldg. Inside Sec. Shield RC-19 355 No No Yes No U.E. Qual. Hear RC-V1
"** "I E' "" d* ** ""d Ik. Yes No RC-23 355 No U.E. Qua.l. Hear RC-V1 I x. Bldg. Inside Sec. Shield RC-20 353 yo No Yes No H.E. Quad.
Ex. Bldg. Inside Sec. Shield RC-21 353 Ho No Yes No H.E. Quad.
RC-22
- no Yes No 353 No N.E. Quad.
"** U* "I ** "* 3h6 No Yes No k RC-9 No d H.E. Quad. Hear RC-V31 J F Itx . Bldg. Inside Sec. Shield ItC-7 353 No No Yes No U.E. Quad. Near RC-V31 Rx- g. Inside Sec. Shield RC-8 353 No No Yes No U.E. Quad. Near RC-V31 Ex. BlJg. Inside Sec. Shield RC-6 353 No No Yes No H.E. Quad.
lu . Bldg. Inside S . Shield RC-10 3h6 no No Yes No U.E. Quad.
Itx . Bldg. In ide Se . Shield RC-ll 328 no No Yes No H.E. Quad.
RC-12
- "* "*1"* * "I 328 No Yes No H.E. Quad. no 1480 305
Page 5 of 15 TAP'_.E 3.16.1 SAFETY liELATED S110CK SUPIItESSOll3 ( GNUBBERS)
Snubber In Snubber Snubbers Snubbers Iligh Radiation Especia]1v Inaccessible Accessihlm Snubber Area During Difficult During Normal Durinc; Normal MK No. Location Elevation Shutdown
- To Remove Operation Operation USE-69 Ex. Bldg. Inside Sec. Shield Yes No 33h No No S.W. Quad.
Ex. Bldg. Incide Sec. Shield USE-90 334 No No Yes No S.W. Quad.
Rx. Bldg. Inside Sec. Shield HSE-91 334 nO No Yes No S.W. Quad.
<x. Bldg. Inside Sec. Shield U 2 33h No no Yes No F-.W. Quad.
Ilx. Bldg. Inside Sec. Shield USE-122 342 No No Yes No S.W. Quad.
Ex. Bldg. Inside Se . Shield NSE-129 334 no Ho Yes No S.W. Quad.
'4 *
- Bldg. Inside Sec. Shield USE-130 33h No Ho Yes No S . b, . Quad.
py g g Ex. Bldg. Inside Sec. Shield 325 No No Yes No J.W. Quad.
Rx. Bldg. Inside Sec. Shield pgq) 5 325 no No Yes No S.W. Quad.
- EF-ll3 320 No Yes Yes No S.W. Quad.
Rx. E dg. Inside Sec. Shield Dif-b 302 no Yes Yes No S.W. Quad.
lix . Bldg. Inside Sec. Shield DH-5 302 no Yes Yes No S.W. Quad.
B In ide e. hield CF-6 316 No No Yes No fix . Bldg. Out ide S . Shield DU-32 340 No No No Yes U.E. Quad.
Itx . Bldg. Outside Sec. Shield 14S-202 No Ye u h h H.E. Quad.
- x. E dg. Outs Me Sec. W eld MS-203 337 No Yes ** Ho no H.E. Quad.
Rx. Bldg. Outside Sec. Shield Yes ** Ho No MS-206 337 No U.h,. Quad.
N** 8' " i "*
- No Yes ** No No MS-207 337 U.E. Quad.
1480 306
Page 6 of 15 T/ ALE 3.16.1 CAFETY RELATED SHOCE SUPPRESSORS ( SNUBBERS)
Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible ,
Accessible Snubber Area Iruring Difficult During Normal During Normal MK Ho . Location Elevation Shutdown
- To Remove Operation Operation
- x. Bldg. Outsiae Sec. Shield MS-292 337 No Yes ** No No N.E. Quad.
Ex. Bldg. Outside Se . SMcld MS-286 337 No Yes ** No No N.E. Quad.
PR-38
"** E' " * ' d 326 No Yes ** No No H.E. Quad.
Rx. Bldg. Outside Sec. Shield PR-3 326 No Yes ** No No N.E. Quad. l I Ex. g. u i e. d PR 10 6 326 No Yes ** No No U.E. Quad.
pg Rx. Bldg. Outside Sec. Shield 326 No Yes ** Uo No II.E. Quad.
Ex. g. a i ec, ed PR 12 6 326 No Yes ** No No II.E. Quad .
, pg_3g Rx. Bldg. Outside Sec. Shield 326 No Yes ** No Ho U.E. Quad.
Ex. Bldg. Outside Sec. Shield PR-M6 309 No No no Yes U.E. Quad.
Rx. g. utside Sec. M eld No Yes PR 15 6 309 No No H.E. Quad.
Rx. Bldg. Outside Sec. Shield PR 16 6 309 Ho No No Yes H.E. Quad.
Ex. Eldg. Outside Sec. Shield p 3 326 No Yes ** No No U.E. Quad. y Itx . Bldg. Outside Sec. Shield PR-50 326 No Yes ** Ho No U.E. Quad.
Rx. Bldg. Outside Sec. Shield 74 U.E. Quad.
309 no no No Yes Rx. Bldg. Outside Sec. Shield 309 no no Uc Yes H.E. Quad.
Ex. Bldg. Outside Sec. Shield MS-200 338 No Yes ** No No S.E. Quad.
Ex. b1dg. Outside Sec. Shield MS-2016 338 No Yes ** No Ho S.E. Quad.
Ex. Bldg. Outside Sec. Shield **
MS-205 338 Ho Yes Ho No S.E. Quad.
- I480 307
Page *( of 15 TABLE 3.36.1 SAFETY ltEIATED SHOCK SUPPRFSCORS ( SNUBBERS)
Onubber In Snubber Snubbers Snubbers liigh Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Formal MK No. Location Elevation Shutdown"
- To Remove Operation Operation MS-291 Ex. Bldg. Outside Sec. Shield 338 No Yes ,, No No S.E. Quad.
Rx. Bldg. Outside Sec. Shield No 3141 No Yes ,, No S.W. Quad.
Rx. Bldg. Outside Sec. Shield No ES-27A 3 141 No Yes ,, No S.W. Quad.
Rx. Bldg. Outside Sec. Shield Yes MUE 10 4 318 No No no f g S.W. Quad ,
_j Rx. Bldg. Outside Sec. Shield Yes 318 No No No S.W. Quad.
Ex. dg. Outside Sec. Shield No Yes n No No BS-5 335 S.W. Quad.
3g_6 Ex. Bldg. Outside Sec. Shield No 335 No ies ** No S.U. 0.uad. ___
BS-26 Ex. Bldg. Outside Sec. Shield 337 No Yes ,* No No S.W. Quad.
Ex. Bldg. Outside Sec. Shield Yes 297 No No No S.W. Quad.
itx. Bldg. Outside Sec. Shield 297 No No No Yes S.U. Quad. -
fix. Bldg. Outside Sec. Shield CF-7 297 No No No Yes S.W. Quad.
_g Rx. Bldg. Outside Sec. Shield 297 No No No Yes S.W. Quad.
Rx. Bldg. Outside Sec. Shield
,, 308 No Yes ** No No S.W. Quad.
Ex. Bldg. Outside Sec. Shield 307 No Yes ** No No S.W. Quad.
Rx. Bldg. Outside Sec. Shield 291 No No No Yes S.W. Quad.
Rx. B]dg. Outside Sec. Shield 291 No No No Yes 4.W. Quad.
I"x . Bldg. Outside Sec. Shield g_,3 291 No No No Yes S.W. Quad.
dx. Bldg. Outside Sec. Shield 25 293 No No No Yes S.W. Quad.
1480 308
TABLE 3.16 1 SAFIXY RELATFD SHOCK SUITHESSOHS ( SHUBBFRG)
Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible ,
Snubber Area During Difficult During Normal During E atl MK No. Location Elevation Shutdown
- To Remove Operation Operatien i
Ex. Bldg. OutafAa Sec. Shield o.W. Quad. 295 No No no Yes DH-24 , Ex. Bldg. Outside Sec. Shield 295 Ho no No Yes S.W. Quad.
Rx. Bldg. Outside Sec. Shield MS-208 '338 Ho Yes ** No No H.W. Cuad.
Ex. Bldg. Outside Sec. Shield MS-209 338 Ho Yes ** Ho No N.W. Quad.
Ex. Bldg. Outside Sec. Snield MS-210 338 ido Yes ** Ho ho U.W. Quad.
Rx. Bldg. Outside Sec. Jhield L'S-2H 338 No Yes ** No No N.W. Quad.
7,_gyg Rx. Bldg. Outside Sec. Shielu **
338 No Yes Ho No II.W. Quad.
Rx. Bldg. Outside Sec. Shield **
MS-213 338 No Yes No No U.W. Quad.
MS-2g Rx. bldg. Outside Sec. Shield **
N.W. Qu,u. 338 No Yes Ho No Ex. Bldg. Outside Sec. Shiel'd~
L' -215 336 No Yes ** No No N.W. Quad.
Ex. bldg. Outside Sec. Shield **
E-287 H.W. Quad.
338 l Ho Yes No Ho Rx. Bldg. Outside Sec. Shield ""
E-288 338 No Yes No No N.W. Quad.
FW-ll2 Ex. Bldg. Outside 9cc Ju[eid 320 No No No Yes H.W. Quad.
pg Rx. Bldg. Outside Sec. Shield 320 No Ho Ho Yes N.W. Quad.
Ex. Bldg. Outside Sec. Shield 141-108 320 No Ho No Yes H.W. Quad.
pg Ex. bldg. Outside Sec. Shield 320 No, No No Yes H.W. Quad.
DH-20 Rx. Bldc. Outside Sec. Shield 298 No no No Yu U.W. Quad.
DH-21 Ex. Bldg. Outside Sec. Shield H.W. Quad. 298 h h & Yu 1480 309
TABLE 3.16.1 SAFETY RELATED SIIOCK SUPPRESSORS ( SNIIBLhllS)
Snubber In Snubber Snubbers Snubbers j Especially Inaccessible Accessible Ni6h Radiation Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown
- To Remove Operation Opere. tion DN-22 Rx Bldg. Outside Sec. Shield 295 h h No Yes N.W. Oond.10-216 - Int. Bldg. on MS-V-1D 355 No Yes *** No No MS-217 Int. Bldg. on MS-V-lC 341 No Yes *** No No
!/.S-218 Int. Bldg. on MS-V-lC 341 No Yes *** No No q g IE-219 Int. Bldg. on !E-V-lc 355 No No No Yes MS-220 Int. Bldg. on MS-V-lD 355 No No No Yes
!E-221 Int. Bldg. on IE-V-3D 3h1 No Yes *** No No MS-222 Int. Bldg. on MS-V-1B 3h1 No Yes *** No No IE-223 Int. Bldg. on MS-V-1A 3h1 No Yes *** No No 10-22h Int. Bldg. on IE-V-1A 3h1 No No No Yes10-225 Int. Bldg. on IG-V-1B 355 No No No Yes10-226 Int. Bldg. on IE-V-lC 355 No No No Yes ,
~
10-227 Int. Bldg. on IE-V-1A 355 No No No Yes10-289 Int. Bldg. on MS-V-1A 355 No No No Yes10-290 Int. Bldg. on MS-V-1B 341 No No No Yes MS-228A Int. Bldg. on A- RV hdr. 337 No Yes *** No No IE-228B Int. Bldg. on A RV Ndr. 337 No Yes *** No !!o MS-229 Int. Bldg. on B RV Ndr. 337 No Yes *** Ho No 1480 310
~ ~ - . . - - . . --. _
Page 10 of 15 TABLE 3.16.1 SAITI'Y RELATED SHOCK SUPI'RESSORS ( SNUBBERS)
Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Hormal MK No . Location Elevation Shutdown
- To Remove Oparation Operation
!!S-230 Int. Bldg. on C RV Hdr. 337 No Yes *** No no 1E-231 Int. Bldg. on D RV Hdr. 337 No Yes ,,, No No IG-65 Int. Bide. 31h Ho Ilo No Yes
!E-233 Int. Bldg. 314 Ho Yes ,,, I;o No g g Int. Bldg. 314 No Yes *** H, No MS-234 314 Ho Yes *** Ho No fiS-235 Int. Bldg.
314 No Yes *** No No 10-236 Int. Bldg.
31h Ho Yes *** No No IE-237 Int. Bldg.
Int. Bldg. 314 No Yes *** Ho Ho MS-238 314 No Yes *** Ho No IE-239 Int. Bldg.10-240 Int. Bldg. 314 Ho Yes *** HU No 314 Ho Yes *** No No IE-2h3 Int. Bldg.
320 Ilo Yes *** No Ho IG-277 Int. Bldg.
320 No Yes *** Ho No IE-2T(A Int. Bldg.
IE-2h7 Int. Bldg. Near EF-P-1 300 No Ho Ho Yes MS-245 Inc. Bldg. Hear EF-P-1 300 No Ho No Yer 1E-246 Int. Bldg. hear EF-P-1 300 No Ho No Yes Ilo Ho Ho Yes iS-270 Int. Bldg. Near EF-P-1 300 1480 311
Page 11 of 15
~
TABLE 3.16.1 Sl!OCK SUPPRESCORS ( SMUEBERS)
CAFETY IMATED .
Snubber In Snubber Snubbers Snubbers liigh Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown
- To Remove Operation Operation MS-271 Int. Bldg. Near EF-P-1 300 No No No Yes FV-121 - Int. Bldg. B FW Catch lidr. 325 No No No Yes FW-122 Int. Bldg. B FV Catch lidr. 325 No No no Yes EF-Th Int. Bldg. Near EF-P-2A 302 No No No Yes EF-75 Int. Bldg. Near EF-P-2B 302 No Yes *** No No EF-76 Int. Bldg. Near EF-P-2B 302 No Yes *n, No No EF-85 Int. Bldg. 302 No No No Yes EF-87 Int. Bldg. Near EF-P-1 302 No No No Yes EF-88 Int. Bldg. Near EF-p-l 302 No no No Yes EF-89 Int. Bldg. 305 No Yes *** No No FW-116 Turb. Bldg. A FV Catch IIdr. a 323 No No No Yes FM-118 Turb. Bldg. A FV Catch IIdr. 323 No No No Yes DCll-58 Aux. Bldg. HX Vault 286 No Yes *** .'io No -
DCll-59 Aux. Bldg. HX Vault 286 No Yes *** No No DCil-68 Aux. Bldg. HX Vault 286 No Yes *** No No NSE-12 Aux. Bldg. IlX Vault 286 No Yes *** No No USI+-13 Aux. Bldg. HX Vault 286 No Yes *** No No USE-lh Aux. Bldg. IlX Vault 286 No Yes No No 1480 312
l' age 12 of 15 .
SAFETY llELATED SIIOCK SUI'I'llESSONS ( SNUBBEllS)
Snubber Snubbers Snubbers Snubber In Especially Inaccessible Accessible liich Radiation Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown
- To Remove Operation Operation NSE-15 Aux. Bldg. I!X Vault 28h No Yes ,,, No' No NSE Aux. bldg. HX Vault 28h No Yes ,,, no No NSI'-17 Aux. Eldg. liX Vault 284 No Yes ,,, No No MUE-6 Aux. Bldg. Valve Alley 283 Yes Yes yc3 No >
MUE--T Aux. Bldg. Valve Alley 283 Yes Yes No Yes Mull-318 Aux. Bldg. Valve Alley 288 Yes Yes U Yes MtRI-319 Aux. Bldg. Valve Alley 288 Yes Yes yc3 No 12JII-321 Aux. Bldg. Valve Alley 288 Yes Yes No Yes Mull-322 Aux. Bldg. Valve Alley 288 Yes Yes Yes No DIlli-196 Aux. Bldg. 297 No Yes *** .fo No IlSE-T Aux. Bldg. 295 No Yes ' * *
- No No NSE-8 Aux. Bldg. 295 Nc No No Yas NSE-9 Aux. Bldg. 293 No llo No Yes NGE-10 Aux. Bldg. 291 No Yes ***
No No N3E-11 Aux. Bldg. 291 No No No Yes NSF-18 Aux. Bldg. 291 No No No Yes NSE-33 Aux. Bldg. 297 No Yes *** No No HSE-37 Aux. Bldg. 293 No No No Yes 1480 313
Page 13 of 15 .
TABLE 3.16.1 SAFETY REI ATED S110CK SUPPHESSORS ( SNUBBFHS) .
Snubber In Snubber Snuocers Snubbers liigh Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown
- To Remove Operation Operation MUH-311 Aux. Bldg. N. End Valve Alley 295 No yes ... No No MUH-312 Aux. Bldg. H. End Valve Alley 295 No yes ... No No DHil-107 Aux. Bldg. DH-P-1A Room 275 No Yes *u No No IAiH-188 Aux. Bldg. DII-P-1A Room 275 No Yes *** No No SPS E-2 Sux. Bldg. Dil-P-1A Room 275 No Yes m No No SPSE-3 Aux. Bldg. DH-P-1A Room 275 No Yes m No No SPSE-12 Aux. Bldg. Dif-P-1A Room 275 No Yes m No No Dlill-197 Aux. Bldg. DH-P-1B Room 275 No Yes m No No .
Dlill-198 Aux. Bldg. DH-P-1B Room 275 No Yes m No No SPSE-7 Aux. Bldg. DH-P-1B Room 275 No Yes m No No SPSE-10 Aux. Bldg. DH-P-1B Room 275 No Yes m No No SPSE-11 Aux. Bldg. DH-P-1B Room 275 No Yes m No No _
BS-19 Aux. Bldg. BS-P-1A Room 275 No Yes m No No SPSE-5 Aux. Bldg. BS-P-1A Room 275 No Yes m No No SPSE-9 Aux. Bldg. BS-P-1B Rcom 275 No Yes m No No BS-21 Aux. Bldg. BS-P-1B Room 275 No Yes m No No USE-2 Aux. Bldg. 310 No Yes m No No USE-3 Aux. Bldg. 310 No Yes m No No 1480 314
v Page lh of 15 TABLl: 3.16.1 .
SAFETY RELA?TD S110CK SUPPHESSORS ( SNUBBERS) ".
Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normali Fi No. Location Elevation Shutdown
- To Remove Operation Operation l NSE-23 Aux. Bldg. NSP Discharge 322 No Yes No No man NSE-2h - Aux. BJdg. NSP Suction 324 No Yes *** No No NSI:-27 Aux. Bldg. 320 No Yes *** No No NSE-29 Aux. Bldg. US to SF Cooler 320 No Yes *** No No A L RW-72 Aux. Bldg. HX Vault 290 No Yes *** No No RW-73 Aux. Bldg. HX Vault 290 No Yes *** No No RW-75 Aux. Bldg. IIX Vault 290 No Yes *** No No RWE-8 Aux. Bldg. HX Vault 290 No Yes *** No No RWE-9 Aux. Bldg. HX Vault 290 No Yes *** No No RWE-10 Aux. Bldg. I!X Vault 290 No Yes *** No No RWE-ll Aux. Bldg. IfX Vault 290 No Yes *** No No RWE-12 Aux. b1dg. IIX Vault 290 No Yes *** No No RWE-13 Ar . Bldg. HX Vault 290 No Yes *** No No j l RWE-lh Aux. Bldg. HX Vault 290 No Yes *** No No IPE-1 Intake Ptunp House 290 No No No Yes IPE-2 Intake Pump House 290 No No No Yes IPE-3 Intake Pwnp House 290 No No No Yes IPE-b Intake Pump House 290 No No No Yes 1480 315
Page 15 of 15 TABLE 3.16.1 .
SAFETY REllTIG EHOCK StHTHEMDONS ( MLPBBF':0) ~,
6 Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During' Difficult During Normal During Normal MK No. Location Elevation Shutdown
- To Remove Operation Operation IPE-5 Intak- ump House 290 No no No Yes IPE-6 Intake Pump House 290 No No No Yes IPE-7 Intake Pump House 290 No No No Yes IPE-8 Intake Pump House 290 No No No Yes IPE-9 Intake Pump House 290 No No No Yes Cylinder No Yes Cylinder-Yes Reservoir-Yes RCP-1A Reactor Bldg. on RCP-1A 3h0 Reservoir-Ho ,
+ Reservoir-No Cylinder-Ho C711"d*#-" Cylinder-Yes Reservoir-Yes RCP-1B Reactor Bldg. cn RCP-1B 340 Yes +
Reservoir-!{o Reservoir-No yli nde r-No RCI3-10, Cylinder-No Cylinder-Yes Reservoir-Yes Reactor Bldg. on RCP-lc 3h0 Reservoir-No
- 8 + Reservoir-No Cylinder-No 7 " ~" Yes ylinder- es esenoWes RCP-lD Reactor Bldg. on RCP-1D 3h0 Reservoir-No + Reservoir-Ho Cylinder-No Modification s to this table d te to changes in Lich rada ntionnrnna sbould ba enh-ittoa to the NRC s part of the nex . license amendment.
,, To be inspec ted with the " inaccessible hydron1ie m nbbar " cronn u , To be inspet ted with the "acci suible hydrnulic nr abbern" Froup
+ Hydraulle sr ubber cylinders ti > be inspected with the "ir nece~ible hydron ic nnubber" _ 3 Reservoirs 1 o be inspected vi .h the "accensible hydraulic snubber: " Froup 1480 316