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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:NRC TO PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA
MONTHYEARML20056A3691990-07-30030 July 1990 Discusses Office of Investigations Rept 1-87-008 Re Observation of Sleeping or Appearance of Sleeping on Duty & Forwards Notice of Violation ML20055F4161990-07-0909 July 1990 Final Response to FOIA Request.App a Record Encl & Available in PDR ML20247E0681989-07-20020 July 1989 Forwards Board Decision Approving Method for Disposing of accident-generated Water at Plant,Per Recipient Petition. Appeal of Decision Presently Before Appeal Board.W/O Encl. Related Correspondence NUREG-0557, Final Response to FOIA Request.Records Available Through Gpo1989-06-26026 June 1989 Final Response to FOIA Request.Records Available Through Gpo ML20245E9571989-06-26026 June 1989 Final Response to FOIA Request.Records Available Through Gpo ML20245G0301989-06-22022 June 1989 Responds to Re Offsite Radiation Monitoring & Emergency Warning Sys in Vicinity of TMI-2.NRC Opinion That Existing Real Time Monitoring Sys Will Remain Operational for at Least Next Several Yrs Expressed ML20246M2231989-05-0808 May 1989 Responds to Raising Concerns Re Actuation of Emergency Warning Signal in York,Pa on 890317.Emergency Brochure Issued to All Local Residents Adequate.Actuation Was Isolated Malfunction of One Signal ML20235N1981989-02-23023 February 1989 Final Response to FOIA Request for Records.Forwards Document Listed in App A.App a Document Available in PDR ML20206D9201988-11-0909 November 1988 Responds to Re NRC 880331 Response to Questions Raised Concerning Conditions at Plants & Recipient Proposal to Station Senior Operator in Control Room at All Nuclear Plants to Oversee Plant Operations ML20195G2121988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App D Document & Releasable Portions of Documents E/1 Through E/3. App D & Releasable Portions of Documents E/4 Through E/6 Available in Pdr.Portions Withheld (Ref FOIA Exemption 5) ML20154L0711988-09-20020 September 1988 Provides Response to TMI Alert,Inc/Susquehanna Valley Alliance Interrogatory 31(ii) Re NRC Experience &/Or Tests Performed on Moisture Separators & Vapor Superheaters. Related Correspondence ML20207E8801988-08-0303 August 1988 Forwards Programmatic EIS for TMI-2 & Suppls 2 & 3.W/o Encls ML20195E8821988-06-15015 June 1988 Third Partial Response to FOIA Request for Documents.App C, E,F & G Documents Encl & Available in Pdr.App D Documents Available in Pdr.Portions of Records Subj to Request Withheld (Ref FOIA Exemptions 4,5,6 & 7) ML20195F8041988-06-15015 June 1988 First Partial Response to FOIA Request for Documents. Forwards Apps B & C Documents.Documents Available in Pdr.App a Documents Also Available in Pdr.Apps D Through G Documents Withheld (Ref FOIA Exemption 5).Releasable Portion Encl ML20151M6061988-04-19019 April 1988 Responds to FOIA Request for Info Re Scores of Reactor Operators & Senior Reactor Operators.Forwards Requalification Exam Summary Source Sheets Listed in Encl App W/Personal Privacy Info Deleted ML20149G0731988-02-10010 February 1988 Responds to Re Announced Reorganization of NRC at TMI-2.NRC Personnel Stationed at Site,Region I & NRC Headquaters Will Continue to Provide Effective Regulatory Oversight of Cleanup Activities ML20147E2561988-01-15015 January 1988 Partial Response to FOIA Request for Documents Re Environ Qualification at Facility.Forwards Documents Listed in App C.Documents Also Available in PDR ML20149E9901988-01-11011 January 1988 Partial Response to FOIA Request Re MOU Between NRC & Dept of Labor.Forwards App B Documents.Apps a & B Documents Available in Pdr.App C Documents Totally Withheld (Ref FOIA Exemption 5) ML20147D4821988-01-0606 January 1988 Partial Response to FOIA Request for Documents.Forwards App B Documents.Documents Also Available in Pdr.Portions of App B Documents Withheld (Ref FOIA Exemptions 6 & 7) ML20237C5961987-12-17017 December 1987 Final Response to FOIA Request for Documents Re Plant. Article from NRC 1979 Annual Rept & Listing of NUREG Repts Re Plant Encl.Nureg Repts May Be Purchased from Pdr.All Encls Available in Pdr.W/O Encl IA-87-834, Final Response to FOIA Request for Documents Re Plant. Article from NRC 1979 Annual Rept & Listing of NUREG Repts Re Plant Encl.Nureg Repts May Be Purchased from Pdr.All Encls Available in Pdr.W/O Encl1987-12-17017 December 1987 Final Response to FOIA Request for Documents Re Plant. Article from NRC 1979 Annual Rept & Listing of NUREG Repts Re Plant Encl.Nureg Repts May Be Purchased from Pdr.All Encls Available in Pdr.W/O Encl ML20235V1381987-10-13013 October 1987 Final Response to FOIA Request for Records.App a Document, Consisting of Dj Collins 870721 Memo to Wd Travers Re Testing of Processed Water Encl & Available in PDR ML20235R8521987-09-30030 September 1987 Responds to Re EIS for Meltdown of Large Reactors & NRC Compliance W/Nepa.As Result of TMI-2 Accident on 790329,NRC Included Class 9 Accidents in Assessments in Fes Re Licensing of Plants.Related Info Encl ML20216D4921987-06-22022 June 1987 Responds to 870610 Motion Requesting That ASLB Reconsider 870521 Decision Re Leak Rate Falsification at Plant. Comments Re Decision Should Be Sent to NRC Staff.Served on 870623 ML20214S0691987-06-0202 June 1987 Forwards Rd Parks Notice of Deposition.Deposition Period of 870622-24 Confirmed.Certificate of Svc Encl.Related Correspondence ML20209H0531987-04-29029 April 1987 Partial Response to FOIA Request for Documents Re INPO Accreditation of Training Programs.Forwards App B Document. Document Also Available in PDR ML20206U0981987-04-20020 April 1987 Forwards Transcript of Recipient 870409 Deposition,For Review.Any Corrections Should Be Made in Tabular Format as Indicated on Encl Sheet.W/O Transcript.Related Correspondence ML20206T6591987-04-20020 April 1987 Forwards Transcript of Recipient 870410 Deposition,For Review.Any Corrections Should Be Made in Tabular Format as Indicated on Attached Sheet.W/O Transcript.Related Correspondence DD-87-03, Advises That Time for Commission to Review Director'S Decision DD-87-03 Expired on 870331.Commission Declined Review.Served on 8704031987-04-0202 April 1987 Advises That Time for Commission to Review Director'S Decision DD-87-03 Expired on 870331.Commission Declined Review.Served on 870403 ML20205A3211987-03-24024 March 1987 Final Response to FOIA Request for IE Inspectors Failure to Rept Info Re 790328 Hydrogen Explosion at TMI-2. App a Document Available in PDR IA-87-163, Final Response to FOIA Request for IE Inspectors Failure to Rept Info Re 790328 Hydrogen Explosion at TMI-2. App a Document Available in PDR1987-03-24024 March 1987 Final Response to FOIA Request for IE Inspectors Failure to Rept Info Re 790328 Hydrogen Explosion at TMI-2. App a Document Available in PDR ML20212K5181987-03-0606 March 1987 Forwards Director'S Decision 87-03 Denying Remaining Portion of 830323 Petition to Halt All Work Based on Rd Parks Allegations & Fr Notice.Portion of Petition Re Polar Crane Load Test Previously Denied in Director'S Decision 83-18 ML20213A0101987-01-29029 January 1987 Final Response to FOIA Request for Documents Re Plant. Forwards App G Document.Documents Also Available in PDR ML20212R6291987-01-27027 January 1987 Forwards Transcript of 870113 Deposition.Review & Signature Requested.W/O Encl.Related Correspondence NUREG-1019, Forwards Response to 860915 & 30 Questions Re Steam Generator Tube Rupture & Turbine Bypass Valve1987-01-13013 January 1987 Forwards Response to 860915 & 30 Questions Re Steam Generator Tube Rupture & Turbine Bypass Valve ML20211Q7551986-12-18018 December 1986 Final Response to FOIA Request for Insp Rept 50-289/86-14 on 860825-0905.App a Document Available in PDR ML20214P4751986-11-26026 November 1986 Responds to 860919 Request That Filter Be Installed on Condenser Offgas Sys Line at TMI-1 to Reduce Possible Radioactive Releases to Environ.Nrc Does Not Believe Placing Filter on Sys Will Provide Measurable Improvement in Safety ML20214A6351986-11-14014 November 1986 Forwards Three Draft Documents to Be Discussed at 861117 Meeting in Buena Park,Ca.W/O Encls.Related Correspondence ML20215H9741986-10-22022 October 1986 Requests to Be Contacted to Arrange Appearance as Witness in Commission Inquiry Into Leak Rate Data Falsifications at Facilities in 1978-1979,per 860806 Subpoena.Served on 861023 ML20215L1871986-10-0909 October 1986 Responds to Appeal Re Denial of FOIA Request for Three Categories of Records Concerning Equipment Qualification at Facility.Forwards Documents 14-16 Listed on App.Documents 1- 13,17 & 20-22 Withheld (Ref FOIA Exemption 5) ML20210U4431986-10-0202 October 1986 Forwards Info Requested at 860923 SALP I Meeting,Including Clarification of Apps Listed in Table in Ref to 10CFR50 & Listing of Subjs of Amends 111-117 to License DPR-50 ML20214Q1991986-09-19019 September 1986 Forwards Response to 860616 & 0710 Ltrs Re Tube Failure in once-through Steam Generator on Reinjection of Emergency Feedwater During TMI-2 Accident Possibly Causing Primary to Secondary Leaks & Large Release of Iodine ML20212P6521986-08-29029 August 1986 Confirms 860828 Telcon Re Agreement to Appear as Witness in Commission Inquiry Into Leak Rate Data Falsifications at TMI-2.Recipient Interviews & Statement Encl.W/O Encls. Served on 860902 ML20203L6971986-08-27027 August 1986 Forwards Subpoena Requiring Appearance at Sept 1986 Hearing Re TMI-2 Leak Rate Falsification.Served on 860828 ML20205C5931986-08-0808 August 1986 Requests Return of Page 3 of Encl 2 to NRC Rept, Results of NRR Investigation & Evaluation of 10 Licensed Operators Involved in TMI-2 Preaccident Leak Rate Testing Irregularities. Served on 860811 ML20205C6281986-08-0808 August 1986 Requests Return of Page 3 of Encl 2 to NRC Rept, Results of NRR Investigation & Evaluation of 10 Licensed Operators Involved in TMI-2 Preaccident Leak Rate Testing Irregularities. Served on 860811 ML20205C6471986-08-0808 August 1986 Requests Return of Page 3 of Encl 2 to NRC Rept, Results of NRR Investigation & Evaluation of 10 Licensed Operators Involved in TMI-2 Preaccident Leak Rate Testing Irregularities. Served in Aug 1986 ML20205C5511986-08-0707 August 1986 Forwards Subpoena Requiring Appearance as Witness at Hearings in Sept 1986 Re Leak Rate Test Data Falsifications During 1978 & 1979.W/o Encl.Served on 860811 ML20205C6321986-08-0707 August 1986 Forwards Subpoena Requiring Appearance as Witness at Hearings in Sept 1986 Re Leak Rate Test Data Falsifications During 1978 & 1979.W/o Encl.Served on 860811 ML20205C4371986-08-0707 August 1986 Forwards Subpoena Requiring Appearance as Witness at Sept 1986 Hearing Re Responsibility for Leak Rate Test Data Falsifications at Facility in 1978-79.Estimated Date of Testimony Is 860930.W/o Encl.Served on 860811 1990-07-09
[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] |
Text
-
U.S. NUCLEAR REGULATORY COMMISSION Nac 704A aEovEst Ncvstmsi
,f* " %,.g
% p fD$k~$(9h$h TES4NSE TyeE 5 5 RESPONSE TO FREEDOM 01 I '*^' XL f'F^'
INFORMATION ACT (FOIA) REQNEST
^
" ## M (e..e[
s DOCKET Nuv5ER 5: vf eapacem LEQUESTER S h R. Loa O PART 1.-RECORDS RELEASED OR NOT LOCATED ISee checked bones)
No agency records subrect to the request have been located.
No adotoral agency records subiect to the aquest have been located.
Agency records subpect to the request that are ioentifed in Appendia are already avadable for public inspection and copymg in the NRC Pubiec Document Room, 1717 H Street N.W., Washegton, DC Agency records subtect to the request that are contifed in Appendia b are bemg tride avadable for pubhc espect.on and copying B the NRC Publc Document f;oom,1717 H Street. N W., Washington, DC. m a foeder under tNs FOl A numcer and requester eame -
The nonpropnetary vers *on of the proposa41s) that you ag eed to exept e a tetepmoae conversaton uth a member of rny staff is now being made avadable for pubhc inspect on and coyog at the NRC Publ.c Document Room,1717 H Street. N W , WasNngton, DC. m a fok3er under thrs Fora number and requester name.
Encioned e information on how you rnay obtain access to and t*e charges for copying records placed in tN NRC Pubhc Document Room.1717 H Street, N W.. WasNngton, DC.
Agency records subect t ta t*e request are enclosed Any applicable charge fe copes of the records proveed and payment procedures are noted in the comments sectron.
Records subtect to the request have been referred to another Federal agencytes) for rewev -M direct respor'se to you.
In vow of NRC's response to the request, no further action e be ng taken on appesi letter da'ed PART ll A-lNFORMAT10N WITHHELD FROM PUBLIC OISCLOSURE Certain informaton m the requested recor 5)is being uthheid from put>l.c d sclosur e a rsuant to the FOIA esemptor's descnbod m and for the reasons stated m Part II. sec-tons 8. C, and O. Any re6 eased portioes of the documents for wNch only part of t record a be,ng uthheid are being made asadab'e for pubhc inspecton and copymg m the NRC Publ.c Document Room,1717 H Street. N W., Washegion, DC. m a folder under this FOIA t' umber and requester name Comments 8801210053 FOIA 880115 PDR PDR WEISge7-696 s'
$!G 8J p *E;TC* Dv5 ON 08 AES aqq- aOS f b fl / .4 C ,
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NIC FORM 464 Pe i i aN. j
Re: F0IA-87-696 APPENDIX C RECORDS IN PDR UNDER REQUEST NUMBER Exhibits to 01 Report ROI, 1-84-021 Exh. 26 Ltr dated 12/10/82 to H. D. Hukill from John Stolz with two enclosures: ;
(a) Safety Evaluation Report By The Office of Nuclear Reactor Regulation For GPU Nuclear Corporation.
- (b) Technical Evaluation Report (TER) (78 pages)
Exh. 27 Ltr dated 3/1/83 from H. D. Hukill to J. F. Stolz. (1 page)
Exh. 28 Memo dated 3/2/83 to N. C. Kozanas from P. B. Magitz, subject:
Corporate Quality Assurance. (3 pages)
Exh. 29 Meno dated 3/9/83 to Allgaier, Heil, Magitz and Wayne, subject: 2nd Meeting Minutes. (5 pages)
Exh. 34 Ltr dated 5/25/84 to D. Hukill frem D. Eisenhut. (12 pages)
- Please Note: This report, as contained in 01 files, is without the l Proprietary Information sections.
I l
l l
1 i
1 tJNION OF CONCERNED SCIENTISTS 1616 e s- . w s.3io . w..si ,4e.. oc 2oo36 . <2o2,332.o,oo October 15, 1987
,. FREEDOM 0F INFORMATION Director, Division of Rules and Records ACT REQUEST Office of Administration U.S. Nuclear Regulatory Commission
[M -/7-d b Washington, D.C. 20555 - 3jd /N~/b 7 RE: Freedom of Information Act Request
Dear Director,
Pursuant to the federal Freedom of . Information Act, the Union of Concerned Scientists hereby requests the following:
- 1. Any report (s) done by the Office of Investigations related to the request by UCS that the NRC investigate whether GPU made material false statements relating to the environmental qualification of safety equipment at Three Mile Island, Unit 1.
- 2. Any report (s) done by the Office of Inspection and Audit related to UCS's request for an investigation into the staff's conduct in re-iterating without review GPU's unfounded claims regarding environmental qualification.
Please note that both UCS requests for investigations were
- made as part of a petition filed by UCS pursuant to 10CFR 2.206, May 9, 1984. Harold Denton, then Director of NRR, stated on September 25, 1984, that GPU had made "invalid" statements and that the matter had been referred to OI. See "Director's
, Decision Under 10CFR 2.206, September 24, 1984, pp. 32-34." In j addition, Robert Pollard and I were interviewed by George Mulley i of OIA in the summer of 1984 in regard to the OIA investigation l of the NRC staff. Therefore, it is clear that both l investigations were at least begun.
I look forward to your response within ten days, as provided l by law.
l Very truly yours, ,
/
G' Ellyn .. Weiss General Counsel gMk D Cambridge Office: 26 Church Street Cambridge, %1as.achu cit 02238 16171.*> l ?.*> ~d2 l
[ 'o UNITED STATES E ' 3 .. 'e NUCLEAR REGULATORY COMMISSION
{g "i f 27 9 W ASHING ton, D. C. 20555 I~k '
%,..'. .' . / Dec ernber 10, 1982 V -
Docket N 50-289 Mr. Henry D. Hukill Vice President GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 17057, ,
SUBJECT:
SAFETY EVALUATION REPORT FOR ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE: Three Mile Island Nuclear Station, Unit No. 1
Dear Mr. Hukill:
This letter transmits the Safety Evaluation Report for the Environmental Qualification of Safety-Related Electrical Equipment at your facility. This evaluation is based on your response to our previous Safety Evaluation Report, dated July 2,.1981 and subsequent submittals as referenced in the enclosed Technical Evaluation Report. This Safety Evaluation Report presents the results of the Environmental Qualification Review for safety-related electrical equipment, '
exposed to a harsh environment, in accordance with NRC requirements. We request that you provide your plans for qualification or replacement of the equipment in NRC Categories I.B, II. A and II.B (presented in the Technical Evaluation Report), and the schedule for accomplishing your proposed correttive actions to us within ninty (90) days of the receipt of this letter.
As indicated in the conclusion section of the Safety Evaluation Report, we request that you reaf firm the justification for continued operation and within thirty (30) days of receipt of this letter, submit inforrnation for items ir.
i NRC Catgories I.B. II. A and II.B (presented in the Technical Evaluation Report)
! for which justification for continued operation was not previously submitted to the NRC. We suggest that the clarification set forth in item 8 of Generic Letter No. 82-09, "Clarification Questions and Answers on Environmental Quali-fication Requirements," should be considered in your justification for continued operation.
The Technical Evaluation Report contains certain identified infomation which yochave previously claimed to be proprietary. We request that you infom us as indicated in the proprietary section of the Safety Evaluation Repo'rt
- whether any portions of the identified pages still require proprietary protectior..
l l At your option, the staf f will be available to discuss the findings in the l Safety Evaluation Report as augmented by the Technical Evaluation Report.
l Questions regarding this letter should be directed through the NRC Project i Manager for your plant.
{cZ/}-W'/*bV$
.%WYhW* yi,
(
Mr. Henry D. Hukill The reporting and/ot:recordkeeping requirements contained in this letter I affect fewer than ten respondents; therefore, OMB Clearance is not required under P.L.96-511.
. Sincerely,
.AA
- J"hh F. Stolz, Chi erating Reactors Branch f4 ivision of Licensing ,
Enclosures:
- 1. Safety Evaluation Report
- 2. Technical Evaluation Report cc w/o TER
Enclosure:
See next page e
S 4
. i
'. GPU Nuclear Corporation 50-289, TMf-1 Mr. R. J. Toole Jordan D. Cunningham, Esq.
Panager, TMI-l .
Fox, Farr and Cuoningham g
GPU Nuclear Corpor&ti'on ' . ?320 North 2nd Street -
P. O. Box 480 Harrisburg, Pennsylvania 17110 Middletown, Pennsylvania 17057 Ms. Louise Bradford THIA Board of Directors' 1011 Green Street P.A.N.E. Harrisburg, Pennsylvania 17102 P. O. Box 268 Middletown, Pennsylvania 17057 m. Marjorie 11. Aamodt R.' D. #5 Coatesville, Pennsylvania 19320
- Docketing and Service Section Earl B. Hoffm'an U. S. Nuclear Regulatory Commission Dauphin County Comissioner Washington, D. C. 20555 Dauphin County Courthouse Fmnt and Market Streets Chauncey Kepford Harrisburg, Pennsylvania 17101
. Judith H. Johnsrud .
Enviror. mental Coalition on Nuclear Power Union of Concerned Scientists .
433 Orlando Avenue
c/o - Harmon & Weiss. .
Stete College, Pennsylvania 16801' 1725 I S treet, N. W.
Suite 506 "
Washington, D. C. 20006
"~
, Mr. Steven C. Sholly Union of Concerned Scientists 1346 Connecticut Avenue, N. W.
J. B. Liebeman, Esq. Dupont Circle Building, Suite 1101 Berlock, Israel & Lieberman Washington, D. C. 20036 26 Broadway "
New York, New York 10304 ~
I lir. Ronald C. Haynes, Regional Administrator
! U. S. N. R. C. , Region I l 631 Park Avenue I King of Prussia, Pennsylvania 19406 l
l ANGRY /TMI PIRC l
1037 Maclay Street .
Harrisburg, Pennsylvania 17103 1
John Levin, Esq.
i Fennsylvania Public Utilities Co. mission Box 3265 -
Harrisburg, Pennsylvania 17120 l
l
. , - - -r - , , . - -
. i . , . . n v...o v s . ., ,, ., , . . . . . . , , , , . . ...m
, Bureau of Radiation Pro..ction 1725 I .Stree., NW
. Department of Environmental Resources
505 Executive House P. O. Box 2357 Judge Gary L.11ilhol.lin - -
.Harrisburg, Pe~nnsylvania 17120 4412 Greenwich Parkway, fM Uashington, D. C. 20007 G. F. Trowbridge, Esq. i Dauphin County Office Emergency Shaw, Pittman, Potts & Trowbridge Preparedness 1800 M Street, N.W. Court House, Room 7 -
Washington, D. C. 20036 Front & Market Streets Harrisburg, Pennsylvania 17101 Mr. E. G. Wallace Licensing Manager
- GPU Nuclear Corporation 100 Interpace Parkw2y Parsippany, New Jersey 07054 WU11es.S'. Jordan,"III,Esq..
. ' . .. .- . . . : ..e.,- - .. a
- ys. Lennie Prough Harmon & Weiss . U. S. H. R. C. - Till Si te ',
. .- 17251 Street, HY, Suite SOS - -
p, o, gox 311 -
264 Walton Street Lemoyne, Pennsylvania 17043 8
Mr. Robert B. Borsum .
Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodront Avenue Bethesda, Maryland 20S14 Mr. David D. Maxwell, Chairman Board of Supervisors Londonderry Township ,
RFDfl - Geyers Church Road Middletown, Pennsylvania. 17057 Mr. C. W. Smyth Supervisor of Licensing TM1-1 GPU Nuclear Corporation l Regional Radiation Representative P. O. Box 480 Middletown, Pennsylvania 17057 EPA Recion Ill Curtis Building (Sixth Floor) 6th and Walnut Streets
- Philadelphia, Pennsylvania 19106 Governor's Office of State Planning Mr. Richard Conte and Development Senior Residen: Inspe::or (7g;.1) ATTN: Coordinator, Pennsylvania U.S.N.R.C. Slate Clearinghouse l P. O. Box 311 Middletown, Pennsylvania 17057 P. O. Box 1323 l
- Harrisburg, Pennsylvania 1712C l
- i .
. 1 SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION '
, FOR GPU flVCLEAR CORPORATION
( TMI-1 DOCKET NO. 50-289 1
ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC EQUIPMENT !
INTRODUCTION General Design Criteria 1 and 4 specify;that safety-related electrical equipment in nuclear facilities must be capable of perfodning its safety-related function under environmental conditions associated with all I normal, abnormal, and accident plant operation. In order to ensure compliance with the criteria, the NRC staff required all licensees of operating reactors to submit a re-evaluation of the qualification of
~
- safety-related electrical equipment which may be exposed to a harsh environment. -
BACKGROUND
~ '
l On February 8, 1979, the NRC Office of Inspection and Enforcement (IE) i issued to all licensees of operating plants (except those included in the
(
l systematic evaluation program (SEP)) IE Bulletin (IEB) 79-01, "Environ-mental Qualification of Class IE Equipment." This Bulletin, together l with IE Circular 78-08 (issued on May 31, 1978), required the licensees to perform reviews to assess the adequacy of their environmental qualifica-tion programs.
l On January 14, 1980, NRC issued IE Bulletin 79-01B which included the 00R guidelines and NUREG-0588 as attachments 4 and 5. respectively.
Subsequently, on May 23, 1980, Comission Memorandum and Order CLI-80-21 l
was issued and stated the 00R guidelines and portions of NUREG-0585 forr the requirements that licensees must meet regarding environmental l
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EVALUATION The acceptability of the licensee's equipment environmental qualification program was reviewed for the Division of Engineering by the Franklin Research Center (FRC) as part of the NRR Technical Assistance Program in support of NRC operating reactor licensing actions. The consultant's review is documented in the report "Re' view of Licensee". Resolutions of Outstanding Issues from NRC Equipment Environmental Qualification Safety Evaluation Reports," which is attached.
We have reviewed the evaluation performed by our consultant contained in the enclosed Technical Evaluation Report (TER) and concur with its bases and findings. Our review has also revealed certain discrepancies in the TER which are being corrected by this SER as follows:
- o Delete the third paragraph on page 1-9 of the TER.
o Delete the second paragraph on page 1-10 of the TE,R. .
The staff has also reviewed the licensee's justification for continued l
l operation regarding each item of safety-related electrical equipment l
l identified by the licensee as not being capable of meeting environmental qualification requirements for the service conditions intended.
CONCLUSIONS l
l Based on the staff's review of the enclosed Technical Evaluation Report l
and the licensee's justification for continued operation, the following l
conclusions are made regarding the qualification of safety-related elec-trical equipment.
l
e 1
'. 1. Continued operation until completion of the licensee's environmental qualification program has been determinea to not present undue risk to the public health and safety. Furthertnore, the staff is contihutng to review the licensee's envirorrnental qualification program. If any additional qualification deficiencies were identified during the course of this review, the licensee would be required to reverify the justification for continued operation.
The staff will review this information to ensure that continued operation until completion of the licensee's environmental qualification program will not present undue risk to the public health and safety. ,
The major qualification deficiencies that have been identified in the enclosed FRC TER (Tables 4-1, 4-2, 4-3 and 4-4) must be resolved by the licensee. Items requiring special attention by the licensee are sunnarized below:
o Submission of infonnation within thirty (30) days for iterns in NRC categories 1B, 2A and 2B for which justificItion for continued operation was not previously submitted to NRC or FRC.
Section 4.3.3 of the FRC TER identifies a concern regarding incontainment environmental service conditions. The staff has reviewed this concern and concludes that the containment temperature / pressure profiles for the worst case LOCA given in Figures14-63A and 14-66 of the FSAR are '.
acceptable for use in equipment environmental qualification.
The licensee cust provide the plans for qualification or replacement of the unqualified equipment and the schedule for accomplishing its prop 0sec correction action.
( f. .
~~
PROPRIETARY REVIEW Enclosed in the FRC Technical Evaluation Report (TER) are certain identified pages on which t'he information is claimed to be proprietary, i During the preparation of the enclosed TER, FRC used test reports and other documents supplied by the licensee that included material claimed to be proprietary by their owners and originators. NRC is now preparing to publicly release the FRC TER and it is incumbent on the agency to seek review of all claimed proprietary material. As such, the licensee is requested to review the enclosed TER with their owner or originator and notify NRR within seven (7) days of receipt of this SER whether any portions of the identified pages still
- require proprietary protection.
If so, the licensee must clearly identify this information and the .
specific rationale and justification for the protection from public disclosure, detailed in a written response within twenty (20) days of receipt of this SER. The level of specificity necessary for such continued protection should be consistent with the criteria enumerated in 10 CFR 2.790(b) of the Commission's regulations.
l l
l