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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
[Table view] |
See also: IR 05000289/1997009
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UNITEo STATES
NUCLEAR REGULATORY COMMISSION
d ! REGloN I
475 ALLENDALE ROAD
0,g , KING oF PRUSSIA, PENNSYLVANIA 1M06-14'$
January 27, 1998
EA 97 533
Mr. James Langenbach
Vice President and Director, TMl
GPU Nuclear Corporation
Three Mile Island Nuclear Station
Post Office Box 480
Middletown, Pennsylanla 17057 0191
SUBJECT: NOTICE OF VIOLATION
(NRC Integrated Inspection Report No. 50 299/97 09) S
Dear Mr. Langenbach:
This refers to the inspection conducted between September 7,1997, and November 1,1997,
at the Three Mile Island Nuclear Station in Middletown, Pennsylvania, the findings of which
were discussed with members of your staff during an exit meeting on November 13,1997.
During the inspection, apparent violations were identified related to your activities during the
12t refueling outage. The inspection report addressing these issues was previously
5
forwarded to you on December 2,1997. On December 22, 1997, a predecisional
enforcement conference (conference) was ennducted with you and members of your staff, to
discuss the violations, their causes, and your corrective actions.
Based on the information developed during the inspection and the information that you
provided during the conference, three violations of NRC requirements are being cited and
are described in the enclosed Notice of Violation (Notice). The circumstances surrounding the
violations are described in detail in the subject inspection report. The violations involve: (1)
inadequate post maintenance testing following replacement of the pressurizer power operated
relies' valve (PORV), in October 1995, that resulted in failure to detect that the PORV actuation
circuit was miswired rendering the PORV inoperable; (2) failure to follow procedures when
filling the reactor coolant system (RCS) on October 5,1997, that resulted in an uncontrolled
spill of water from the control rod drive mechanism (CROM) vents; and (3) Inadequacies in
the procedure for the control of radioactive (hot) particles that resulted in a worker receiving
a significant skin exposure on October 4,1997.
The most significant violation involved the inoperable PORV. During rewiring of the PORV
actuation solenold, following replacement of the PORV during the 11R refueling outage in
October,1995, the terminal connections on the solenoid were not clearly marked.
Nonetheless, neither the technician who landed the leads, nor the technician that
,
independently vetified the wiring, stopped and positively determine the correct terminal
locations. Instead, both technicians made incorrect assumptions as to the terminallocations.
As a result, the PORV was miswired and would not have opened in response to a manual or
automatic actuation signal. ,-
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The failure to perform adequate post maintenance testing following replacement of the
pressurizer PORV resulted in this condition not being identified. Specifically, following the
incorrect wiring of its actuation solenold, no test was performed to ensure that the PORV
l would open in response to en automatic or manual actuation signal. This f ailure corstitutes
a violation of the Technical Specification (TS) requirement to perform in service testing. At
the conference, you indicated that the failure to perform the post maintenance test (PMT) was
due to procedural and work scheduling inadequacles. Specifically, no PMT checkoff was
provided in the PORV replacement and inspection procedures, and there was incomotete
guidance in the job order package to direct the performance of the PMT.
Tne inability to open the PORV would have prevented it from performing its pressure relief
function either during power operations or during low temperature conditions during heatup
and cooldown. Even though the pressurizer safety valves (the primary pressure relief system),
were available to provk'e overpressure protection during power operations, and administrative
controls were in place to provide low te nperature overpressure protection, the diversity
provided by the PORV for these functions was not available for the entire operating cycle, a
period of 23 months. Additionally, the PORV would not have been available to provide a bleed
path for high pressure injection (HPI) cooling or to depressurize the RCS to establish long term
decay heat removal following a steam generator tube rupture. The unavailability of tha PORV
for pressure relief or HPI cooling had potential conseqeences in that it resulted, as determined
by your own calculations, in a 16% increase in the TM! core damage frequency, if an event
occurred needing the PORV to be opened. This was preventable if requirements for post-
maintenance testing had been met. Therefore, the violation has been categorized at Severity
Level lli in accordance with the " General Statement of Policy and Procedure for 'NRC
Enforcement Actions" (Enforcement Policy), NUREG 1600.
In accordance with the Enforcement Policy, a base civil penalty in the amount of $50,000ls
considered for the Severity Level lil violation that occurred prior to November 12,1995.
Because your facility has been the subject of escalated enforcement actions within the last
2 years,' the NRC considered whether credit was warranted for / dent //ication and Correct /v6
Act/on in accordance with the civil penalty assessment process in Section VI.B.2 of the
Enforcement Policy. Credit was warranted for identification because your staff identified,
during the 12R refueling outage, that the PORV had been miswired and that nc PMT had been
performed following the 11R refueling outage. Credit was also warranted for corrective
actions because your actions were considered both prompt and compruhensive. Those
actions included: (1) communication of management expectations for self-checking,
independent verification, and performance of post maintenance testing; (2) planned revisions
to the PORV maintenance procedure to clarify the FMT reqWrements, and to the job order
program to include the vendor manual wiring diagrams in the job order package; (3) review
of other work packages to ensure that all required PMTs had been performed; and (4) plans
to perform a process study to ivify and correct weaknesses in the PMT program,
e.g., A Notice of Violation and Pmposed Imposition of Civil Penalties in the amount of $210,000 was issued
on October 8.1997 (EAs 97 070. 97117,9,'-t27. and 97 256), for numerous violations related to several areas
of plant performance includicg engineering design controls, classification and environmental qualification of
components, corrective actions, and emergency preparedness.
.
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GPU Nuclear Corporation 3
Therefore, to encourage prompt identification and comprehensive correction of violations, I
have been authorized, after consultation with the Director, Office of Enforcement, not to
propose a civil penalty in this case. However, significant violations in the future could result
in a civil permity.
With respect to the overfill of the RCS, the shift supervlsor (6S), who was supervising the fill
and vent of the 11CS in October,1997, believed that there was not enough water available in
the reactor coolant bleed tank (RCBT) to complete the intended evolution. Although the SS
appropriately consulted his supervisor and was told that there was sufficient water available
in the RCBT, the SS, still believing that there was insufficient water available, used an
inappropriate procedure to fill the RCS from the borated water storage tank (BWST). Other
control room operators did not que#on the SS's decision. Your staff failed to adhere to the
limitations provided in the decay heat removal (DHR) system operating procedure (OP) when
they used the DHR pumps to provide makeup to the RCS directly from the BWST during the
fill and vent of the RCS, Additionally, they failed to follow the RCS fill and vent procedure
when they failed to terminate the RCS fill at the required point.-- As a result, borated water -
spilled onto the reactor vowsel head and control rod drive (CRD) components, potentially
degrading those components and creating a radiclogical condition warranting remediation.
While this violation is classified at Severity Level IV given the significance of the occurrence,
it raises concerns regarding the questioning attitude of the staff and management's
expectations for adherence to procedures. At the aonference, you indicated that the problem
was that the SS failed to comply with normal work practices specified in your conclect of
ciperations administrative procedure (AP), rather than's failure to adhere to the RCS fill and
vent procedure or the DHR system operating procedure. The NRC is concerned that plant
)- management may not be'providing a high. standard for procedure adherence and may be
providing operators with the impre,asion that it is acceptable to use procedures that were not
specifically prepared to support an activity.
Finally, with respect to the inadequate hot particle control procedure, an emergent hot particle *
area was discovered during surveys of newly exposed surfaces upon raising the reactor vessel
heed seal plate following work in the fuel transfer canal in October,1997. Upon discovery
of these conditions, the radiation control technician (RCT) assigned to the job elected to
proceed without consulting supervision. Although the area was subsequently decontaminated,
the surveys that were performed f*>llowing the decontamination were not adequate to verify
the removal of the hot particles. Additionally, a hot particle control area was not formally
established. Your radiological protection (RP) procedure RP for hot particle controls was
inconsistent with 10 CFR 20.1501 in that it did not provide sufficient direction to assure that
adequate surveys were performed and that adequate hot particle controls were established.
- This constituted a violation of Technical Sp cification requirements for the radiation protection
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program which require that procedures for personnel radiation protection shall be prepared
consistent with the requirements _of -10 CFR 20. As a result of the inadequate surveys and
lack of sufficient hot particle controla, a worker received a calculated dose of approximately
14 rem to the skin. While the violation is classified at Severity Level IV, the NRC :s concemed
that, when it was determined that hot particles were present, an evaluation, to determine the
quantities and magnitude of the hot particle contamination, was not performed. Consequently,
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GPU Nuoleer Corporation 4
an appropriate interval for personnel frisking for hot partici t9 was not established. Without
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these controls, there was a potentiel for skin exposures even more significant than the
exposure that cccurred.
With respect to the apparent violation involving the failure to follow procedures for the once-
through cteam generator (OTSG) locked high radiation area that was discussed at the
conference, the NRC concluded that the wutker that left the OTSG manway area unattended
with the high radiation area door unlocked failed to adhere to the requirements of your locked
high radiation area AP. However, based on the information provide j at the conference and
during subsequer't telephone conversations with Mr. Etheridge of your staff, the NRC
concluded that the potential for inadvertent entry into the high radiation area was low. The
manway opening was continuously monitored at a remote location with a video camera and
the individual monitoring the opening by camera was in direct communication with personnel
in the close proximity of the unlocked manwsy. Therefore, because it was licensee identified;
was correct 6J immediately; and was not ropetitive within the last two years, the violation of
the locked hig5 radiation area AP will not be cited in accordance with Section Vll.B.1 of the
Enforcement Policy.
You are requirnd to respoad to this istter and should follow the instructions specified in the
enclosed Notice when preparing your response. The NRC will use your response, in part, to
determine whether further enforcement action is necSwary to ensure compliance with
regulatory requirements,
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
enclosure, and your response will be placed in the NRC Public Docurr.ent Room (PDR).
Sincerely,
H ert J. Miller
Regional Administrator
Docket No. 50 289
License No. DPR 50
Enclosure: Notice of Violation
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GPU Nuclear Corp sation 5
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cc w/ encl:
J. Fornicola, Director, Nuclear Safety Review
M. Ross, Director, Operations and Maintenance
D. Smith, PDMS Manager
TMI Alert (TMIA)
M. Laggart. Manager, TMI Regulatory Affairs
E. Blake, Shaw, Pittman, Potts and Trowbridge (Legal Counsel for GPUN)
Commonwealth of Pennaylvania
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GPU Nuclear Coe, ation
DISTRIBUTION:
PUBLIC -
SECY
CA
LCallan, EDO
AThadani, DEDE
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JLloberman, OE
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HMiller, RI
FDavis, OGC
SCollins, NRR
RZimmerman, NRR
Enforcament Coordinators
Rl, Ril, Rlll, RIV
BBeecher, GPA/PA
GCaputo, 01
DBangart, OSP
HBell, OlG
TMartin, AEOD
OE:Chron
OE:EA
DCS
NUDOCS
DScrenci, PAO RI-
NSheehan, PAO RI
Nuclear Safety Information Center (NSIC)
NRC Resident inspector - Three Mile Island
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