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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted 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 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 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 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) 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 ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted 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 ML20196J5631999-07-0101 July 1999 Informs That Util 981203 Joint Application with Amergen Energy Co Marked Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196J5741999-06-30030 June 1999 Informs That as Result of Staff Review of Util Response to GL 92-01,rev 1,suppl 1,info Provided in Support of PT Limits License Amend & B&W Topical Rept,Staff Revised Info for Plant,Unit 1,in Reactor Vessel Integrity Database ML20196H6811999-06-29029 June 1999 Forwards Insp Rept 50-289/99-03 on 990425-0605.No Violations Noted.However,Adequacy of Assessment of Reactor Bldg Emergency Cooler Operability Prior to Conducting Maintenance on One Reactor Bldg Spray Sys,Questionable ML20212H8711999-06-21021 June 1999 Discusses Updated Schedule Commitment Submitted by Gpu on 990602 for Implementing Thermo-Lag 330-1 Fire Barrier C/As & Completion of Thermo-Lag Effort at TMI-1.Informs NRC Will Incorporate Commitment Into Co Modifying License ML20195K2821999-06-17017 June 1999 Forwards Request for Addl Info Re Kinetic Expansion Region Inspection Acceptance Criteria ML20212H6621999-06-0404 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Three Mile Island Nuclear Station ML20207E7201999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328. Organization Chart Encl ML20207B6541999-05-27027 May 1999 Forwards SER Accepting Util Program to Periodically Verify design-basis Capability of safety-related MOV at TMI-1 & That Util Adequately Addressed Actions Requested in GL 96-05 ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206S3411999-05-14014 May 1999 Forwards Insp Rept 50-289/99-02 on 990314-0424.Violations Occurred & Being Treated as non-cited Violations.Security Program Was Inspected During Period & Found to Be Effective ML20206N5831999-05-13013 May 1999 Requests Description of Proposed Corrective Actions for Fire Zones AB-FZ-3,AB-FZ-5,AB-FZ-7,FH-FZ-2,CB-FA-1 & FH-FZ-6. Confirmation That Corrective Actions & Commitments Made Will Be Completed by 991231,requested IR 05000298/19980091999-05-12012 May 1999 Refers to Insp Rept 50-298/98-09 Conducted Between 981227-990130.During Insp,Apparent Violation of 10CFR50.50 Identified & Being Treated as non-cited ML20206H3571999-05-0606 May 1999 Forwards RAI Re 981203 Application & Suppls & 0416,requesting Review & Approval of Revised Core Protection SL & Bases for TMI-1 to Reflect Average of 20% of Tubes Plugged Per Sg.Response Requested within 10 Days of Receipt ML20207A5401999-04-29029 April 1999 Informs That Licensee 980930 Response to GL 96-06,appears to Be Reasonable & Appropriate for Specific Design & Configuration of RB Emergency Cooling at Plant,Unit 1 & That Staff Satisfied with Licensee Resolution of Waterhammer ML20206D4001999-04-20020 April 1999 Informs of Completion of Review of Gpu Request for Exemption Submitted on 961231,970908,971230,980521,981014,981125 & 981223 from Requirements of 10CFR50,App R,Section III.G.2 for TMI Unit 1.Forwards Exemption & Safety Evaluation ML20205S6791999-04-16016 April 1999 Forwards Insp Rept 50-289/99-01 on 990131-0313.No Violations Noted.Identification by Licensee Staff of Elevated Tritium Activity in Monitoring Well Led to Investigation & Identification of Leak from Buried Radwaste Path ML20205P3391999-04-0909 April 1999 Discusses Results of Plant Performance Review for Three Mile Island Completed on 990225.Historical Listing of Plant Issues That Were Considered During PPR Encl IR 05000289/19980061999-03-26026 March 1999 Ack Receipt of 981112 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-289/98-06 .Action Does Not Change NRC Determination That Change to Hpis Valve Configuration Involved URI ML20204E3911999-03-17017 March 1999 Informs That Region I Plans to Conduct Open Predecisional Enforcement Conference to Discuss Apparent Violations Re Efs Issues as Described in Insp Rept 50-289/98-09,per ML20204B6771999-03-15015 March 1999 Submits Withdrawal of Amend Request for Operating License DPR-46.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring Neutron Detectors ML20207H7391999-03-0505 March 1999 Forwards Insp Rept 50-289/98-09 on 981227-990130.Two Apparent Violations Being Considered for Enforcement Action.First Violation Deals with Failure to Follow Procedures for Control of Emergency Boration Source ML20203F4911999-02-0505 February 1999 Forwards Request for Addl Info Re Licensee 981125 Amend Application Re TS Change Request 277 for OTSG Inservice Insp During 13R for Three Mile Island,Unit 1 ML20202H6771999-02-0303 February 1999 Documents Basis for NRC Staff Generic Approval of Requests to Relocate TS Requirements from Tss.Staff Generic SER Finding Relative to Relocated TS Requirements Encl ML20196K3511999-01-22022 January 1999 Refers to Gpu Responses to Second NRC RAI Re GL 92-08 & Review of Gpu Analytical Approach for Ampacity Derating Determinations.Forwards SE & SNL Technical Ltr Rept Concluding That No Outstanding Safety Concerns Identified ML20199H6471999-01-20020 January 1999 Forwards RAI Re Gpu TS Change Request 277 OTSG Cycle 13 for Plant Unit 1.NRC Has Determined That Addl Info Needed to Complete Review ML20199G7401999-01-12012 January 1999 Forwards Insp Rept 50-289/98-08 on 981101-1226.No Violations Noted.Operator Workaround Program Found to Be Acceptable ML20206S0221999-01-0808 January 1999 Responds to Re Changes to Physical Security Plan Identified as Rev 38,submitted Under Provisions of 10CFR50.54(p).Based on NRC Determination,Changes Do Not Decrease Overall Effectiveness of Security Plan 1999-09-30
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Mr. Vice President and Director Three Mile lebnd GPU Nuclear, Inc.
Route 441 South P. O. Box 480 Middletown, PA 17057-0480 SUBJECT: NRC INTEGRATED INSPECTION NO. 50-289/97-09 (EA 97-533) AND 50-289/97-10
Dear Mr. Langenbach:
This letter refers to your March 30,1998, correspondence, in response to our January 27, 1998 and February 26,1998, letters.
Thank you for informing us of the corrective and preventive actions regarding Violations EA 97-533 (02014) and 97-10-01 documented in your letter. These actions will be examined during a future inspection of your licensed program. We appreciate your correction of the inaccuracies, as identified in your response to the second violation.
Your cooperation with us is appreciated.
Sincerely,
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Original Signed By:
Michele G. Evans, Chief Project Branch No. 7-Division of Reactor Projects Docket No. 50-289 cc (w/o ev of Licensee Pa= nonne Letteri: f J. C. Fornicola, Director, Nuclear Safety Assessment M. J. Ross, Director, Operations and Maintenance /
J. Wetmore, Manager, TMI Nuclear Safety and Licensing y cc (w/cv of Licensee Resnonne Letterh TMI-Alert (TMIA)
f} ../ I E. L. Blake, Shaw, Pittman, Potts and Trowbridge (Legal Counsel for GPUN)
Commonwealth of Pennsylvania 9905070129 990501 *
PDR ADOCK 05000299 :
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Mr. ' Distribution (w/cv of Licensra Resoonse Letter):
Region 1 Docket Room (with concurrences)-
. Nuclear Safety Information Center (NSIC)
PUBLIC '
NRC Resident inspector M. Evans, DRP -
N. Perry, DRP D. Haverkamp, DRP -
A. Linde, DRP J. Yerokun,~ DRS B. McCabe, EDO
~ C. Thomas, NRR.
T. Colburn, NRR '
R. Correia, NRR F. Talbot, NRR inspection Program Branch, NRR (IPAS)-
DOCDESK L DOCUMENT NAME: G:\ BRANCH 7\rp9709 IO.tml Ta recehe a copy of this document. Indicate in the box: "C"= Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE RI/DRP l RI/DRP lhi / l l l NAME DHaverkamp MEvans re E DALE 04/28/98 Og/ 0 /98 04/ /98 04/ /98 04/ /98 0FFICIAL RECORD COPY
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( Route 441 south NUCLEAR Post Office Box 480 Middletown, PA 17057 0480
. Tel 717 944 7621 March 30,1998 1920-98-20123 U.S. Nuclear Regulatory Commission Mtention: Document Control Desk Washington, DC 20555
Dear Sir:
Subject: Three Mile Island Nuclear Station, Unit 1, (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Response to Notices of Violation (NOV) 97-09-02, dated January 27,1998 And NOV 97-10-01, dated February 26,1998 The attachment to this letter transmits the GPU Nuclear (GPUN) Inc. responses to the NOVs referenced above. Each violation identified in the NOVs is addressed separately to include: (1)
the reason for the violation; (2) corrective actions taken and results achieved; (3) corrective actions to be taken, if applicable, to avoid future violations; and (4) the dates of full compliance achievement. The public health and safety were not affected by these events.
The two violations involved procedural non-compliance and usage issues. While we determined that the root causes for each event were different, we have concluded that programmatic improvements should be considered in addition to the specific actions identified in this response.
We plan to expand the list of applicable procedures required by administrative controls to be carried and signed off during performance of plant evolutions by June 30,1998. We also plan to conduct a self-assessment and benchmarking review of the procedural controls currently in place. The review will consider industry guidance and good practices employed by other nuclear plants to determine what changes should be made to improve procedure control or usage at TMI.
The target date for completion of this review is September 30,1998. A schedule for the development and implementation of requisite improvements is expected to be in place by October 31,1998.
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1920-98-20123 Page 2 of 3 This NOV response is being submitted pursuant to the requirements of 10 CFR 2.201, and contains no information subject to the provisions of 10 CFR 2.790(b). If you have any questions concerning this matter please contact Mr. G. M. Gurican, Sr. II Nuclear Safety & Licensing Engineer, at TM1 phone No. (717) 948-8753.
Sincerely,
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sf JamM Vice President and Director, TMI JWUGMG Attachment F
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1920-98-20123 Page 3 of 3 t
I, James being duly sworn, state that I am the TMI Vice President and an Officer of GPU Nuclear, Inc. and that I am duly authorized to execute and file this response on behalf of i GPU Nuclear. To the best of my knowledge and belief, the statements contained in this document l
are tme and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other GPU Nuclear employees and/or consultants.
Such information has been reviewed in accordance with company practices and I believe it to be i reliable. l l
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JaYes ' !
Vice President, TMI GPU Nuclear, Inc.
, 3-30- 9F i 7 A Notary Public of PA NotarialSeal Unda L Allier, Notary Pubile EMires 2002 Member, ^. . ;,^ .-_ Associehon of Nolanes cc: NRC AdministratorRegionI TMI Senior Resident Inspector TMI Project Manager File 98053 -
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ATTACHMENT RESPONSE TO NOTICES OF VIOLATION January 27,1998, IR 50-289/97-09-02 (EA 97-533)
And February 26,1998, IR 50-289/97-10-01 Notice of Violation 97-09-02 Technical Specification (TS) 6.8.1 requires, in part, that Written procedures be implemented covering the applicable procedures recommended in Appendix 'A' of Regulatory Guide 1.33, Revision 2, February 1978. Regulatory Guide 1.33, Appendix
'A', Section 3.0 recommends, in part, instructions for filling and venting the reactor coolant system (RCS) and for operation of decay heat removal systems.
Operating procedure (OP) 1103-2, " Fill and Vent of the Reactor Coolant System," section 3.1.2, step 17.c, requires, in part, that when the level at the center control rod drive mechanism (CRDM) is observed at one to two feet below the top, terminate the RCS fill and hold level.
OP 1104-4, " Decay Heat Removal System," section II of Enclosure 2, "Make Up to the RCS Directly from the BWST," provides a caution that make up to the RCS directly from the borated water storage tank (BWST) must be carefully monitored since large volumes of water can be transferred very rapidly. Step 1 of section II states, in part, that controlling the level in the RCS using this method is not considered to be, nor should it be, used as a major RCS fill and vent method.
Contrary to the above, on October 15,1997, the licensee failed to properly implement operating procedures 1103-2 and 1104-4 while filling and venting the RCS following a refueling outage. Specifically, while filling the RCS from the reactor coolant bleed tank (RCBT)in accordance with OP 1103-2, make up to the RCS was established directly from the BWST, contrary to the instructions in Enclosure 2 of OP 1104-4. The additional makeup caused a prompt rise in pressurizer level. Even though the operators observed the level increase in the control room terminated the RCS fill from the RCBT, the makeup from the BWST was not immediately terminated due to communications difficulties. Consequently, approximately 50 gallons of RCS water overflowed out of the CRDM vents onto the reactor vessel head area.
GPUN Response:
1. Reasons for Violation GPUN agrees with the violation. In this event, the Shift Supervisor (SS) used poor judgement and inappropriate procedural implementation during the performance of the RCS fill and vent evolution by establishing a flow path from the BWST at a time when it was inappropriate to do so because of the potential for overfill. The SS did not understand Management's expectation that the BWST would not be used for filling the RCS when the pressurizer level was above 100 inches; and, the SS incorrectly assumed that he was filling to 390 inches and thought that he needed much more water than was available in the Reactor Coolant Bleed Tank.
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In addition, the evolution was started during a shift turnover, and supervisory methods and verbal communications between team members were less than adequate; also, the use ofimproper communications equipment contributed to a delay in event termination.
2. Corrective steps taken and results achieved.
a. A revision of OP 1104-4 has been made to provide a more specific warning that addresses the use of the BWST as a fill source to strictly prohibit its use when the pressurizer level is at 100 inches or above. This revision also adds signoff requirements to specific steps within the procedure.
b. Management has issued instructions to all crews concerning its expectations with respect to the inappropriateness of performing significant plant evolutions while a i shift turnover is in progress. Management has reemphasized the need for strict procedural compliance as well as the need to have a questioning attitude.
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Procedural compliance has been stressed with all crews including the requirements: to have procedures available; to properly signoff procedural steps for significant evolutions; and, when procedures are not available, to obtain the procedure and resolve any questionable issue prior to conduct of the evolution.
These Management expectations were documented in an internal memorandum to all departments from the Director of Operations & Maintenance.
d. Communication enhancements have been made with the modification of the format for conducting the Operations Department outage shift turnover meeting.
This has been accomplished by the inclusion of a final summary " repeat back" by the oncoming Shift Supervisor, prior to concluding the meeting, in order to ensure understanding of direction and intent.
e. By memo from the Plant Operations Director to all Shift Supervisors and crews l the use of appropriate communications equipment, specifically the M&I phone system, are to be used for significant plant evolutions that require numerous transmissions of detailed information.
3. Corrective steps to be taken to avoid further violations.
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a. The listing of significant evolutions requiring specific procedures for implementation identified in AP-100lG, " Procedure Utilization," will be expanded to meet Management's expectations informally communicated by the Director of Operations and Maintenance via internal memorandum dated March j 3,1998. This expansion of AP-100lG will increase the number of evolutions that ;
require having a procedure in-hand when performing the evolution. l b. To achieve a higher standard of administrative controls, GPUN intends to make i programmatic improvements to strengthen procedural compliance and l documentation. A self-assessment and benchmarking review of procedural l
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controls and usage at TMI will be conducted, considering industry good practices and guidance. The implementation of any requisite improvements in procedural controls / usage resulting therefrom will be instituted by changes to atTected i
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procedures.
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4. Dates of full como~liance.
Full compliance has been achieved Corrective action 3.a will be completed by June 30,1998. Corrective action 3.b (1) will
, be completed by September 30,1998; and, the schedule for implementation of the requisite procedure changes 3.b.(2) will be developed by October 31,1998. i I
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Notice of Violation 97-10-01 ,
Technical Specifications 6.5.1.1, " Technical Review and Control," and 6.8.2,
" Procedures and Programs," require, in part, that any substantive changes, including the '
change ofintent to procedures that affect nuclear safety, shall be reviewed and approved prior to implementation.
Contrary to the above, on November 20,1997, GPUN did not review and approve a substantive change to an existing inservice test (IST) surveillance procedure 1300-3K,
"IST of Reactor River Water Pumps and Valves," before the closure of the reactor building emergency cooler inlet and outlet valves to conduct a leak test. The IST procedure was written and approved to determine the cooler inlet and outlet valve open and closed times, but did not allow the valves to be closed for the seven hour leak test.
GPUN Response:
1. Reasons for Violation GPUN concurs there was a violation of Technical Specification 6.5.1.1 and 6.8.2.
However, for accuracy it should be noted that on November 20,1997 the Operators did not rely upon use of the Sun >eillance Procedure 1300-3K to conduct the investigation of leakage from the Nuclear Services system. This trouble shooting activity was performed using the guidance of AP-1029 and OP-100lG. On November 24,1998 the Operators did use SP-1300-3K for guidance to conduct valve cycling as allowed by OP-1001J,
" Tech. Spec. Surveillance Program Testing," which states: "where the intent of a test is other than to satisfy a TS surveillance testing requirement, the appropriate TS surveillance procedure may be used for instructional guidance and as a vehicle to document performance."
Nevertheless, GPUN has determined that on November 20,1998 the requirements of procedures AP-1029," Conduct of Operations," and OP-100lG," Procedure Utilization,"
were not met, in that the crew's determination that there would be no adverse affects on the operability of the RR system due to closing of the RR-V-3s was not logged. Prior to closing the valves the crew did discuss and determine that there would be no adverse affects on operability because an ES signal would cause the valves to open in the event of a LOCA, if the valves were closed. However, the procedurally required logging of this determination did not take place.
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l GPUN has also determined that AP-1029 currently does not contain adequate guidance l and controls for the conduct of trouble-shooting activities. It is Management's expectation that evolutions of this nature would be controlled by means of a trouble shooting plan based on appropriate guidance using a graded approach and/or by a Special Temporary Procedure (STP). The STP process is designed to assure that proper precautions are established, and that reviews of design basis requirements and other safety considerations are conducted prior to executing the STP. l In addition, a contributing cause for not initiating a STP for this plant evolution was the l failure to effectively translate a change in design basis assumptions into operating procedures (n.b., the necessity for the assumption was later negated by reanalysis).
Specifically, the initial assumption made was that an overpressure on the Reactor Building Emergency Coolers needed to be maintained in order to address GL 96-06 ,
concerns. This assumption was not identified by the System Performance Team (SPT) l for consideration of potential impact upon operating procedures when the SPT performed !
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the analyses prepared for the original Generic Letter response.
I 2. Corrective stens taken and results achieved.
a. Management has re-emphasized its expectations that crews are to comply with the requirements for obtaining permission and logging all work related to the performance of evolutions not covered by written procedures, and to be aware of ,
the administrative requirements and in particular the documentation requirements j stipulad in AP-1029. i
3. Corrective steps to be taken to avoid further violations.
a. GPUN will develop new/ revised guidance to effectively strengthen work controls l relevant to the conduct of trouble shooting within AP-1029," Conduct of i Operations." The guidance on trouble shooting considerations will address more
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formally, Management's expectations as previously outlined in an internal memoran.fum dated March 3,1998, from the Director of Operations and Maintenance, and will be based on a graded approach for the use of a trouble shooting plan and/or an STP.
b. This event will be incorporated into the operating experience presentations for Licensed Operator training and requalification, as well as, in the Engineering Support Personnel training. The event review will emphasize how the change control processes should provide identification of the relationship between the design basis assumptions and the operational requirements for plant systems.
c. A self-assessment and benchmarking review of procedural usage as described in Corrective Action 3.a for the response to NOV 97-09-02 above will be conducted.
d. The System Performance Teams (SPTs) are accountable for ensuring that changes made in design assumptions, as related to Operations or Maintenance activities are thoroughly evaluated and, when needed, incorporated into plant procedures, training, and design documents. The SPTs minimum membership includes representatives from Operations, Maintenance, and Engineerin ,e departments.
GPUN will review this specific event with the System Engineers, who are the J
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SPT leaders. The review will emphasize how the change review process could have provided identification of the relationship between the design basis assumptions and the operational reqqirements for the system. Additional .
' guidance will .be incorporated into the next revision to the System Engineering Guideline (Document #990-2471) to capture the lessons learned from this event.
- The SPT and System Engineer review goes above and beyond the existing 10CFR50.59 review requirements as provided by the GPUN Safety Review Processes that are required for plant modifications and/or procedure changes.
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4. Dates of full comoliance:
Full compliance has been achieved.
Corrective actions 3.a and 3.b to avoid future violations related to this NOV will be completed by December 31,1998. Corrective action 3.c will be completed as identified above under corrective action 3.b for NOV 97-09-02, in two parts, namely: the self-assessment study is scheduled for September 30,1998 and its implementation schedule for October 31,1998. Corrective action 3.d will be achieved by June 30,1998.
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