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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058E8621990-11-0101 November 1990 Forwards Understanding of Current Status of Unimplemented GSIs at Facility,Per 900626 Response to Generic Ltr 90-04. Timely Completion of Encl GSIs Urged ML20058G1561990-10-31031 October 1990 Requests That Matl Listed in Encl 1, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams, Be Furnished by 901207 for Retake of Operating Exams Scheduled for 910122 ML20058B3101990-10-23023 October 1990 Forwards Insp Rept 50-382/90-22 on 900905-1001 & Notice of Violation IR 05000382/19900231990-10-17017 October 1990 Submits Revised Schedule for Electrical Distribution Sys Functional Insp 50-382/90-23.Insp Team Will Arrive at Plant Site on 910107 ML20058B2681990-10-17017 October 1990 Informs That Util Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058A6711990-10-16016 October 1990 Forwards Insp Rept 50-382/90-21 on 900910-14.No Violations or Deviations Noted ML20058A4771990-10-16016 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-17 ML20062B6231990-10-12012 October 1990 Confirmation of Action Ltr CAL-90-06,confirming That Plant Will Not Enter Mode 2 Until NRC Confirms Actions Assuring That Adequate Safety Exists for Continued Power Operation IR 05000382/19900151990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-15.NRC Unable to Clearly Determine Actions Intended to Address Overall Retest & Program Weaknesses ML20059N7041990-10-10010 October 1990 Ack Receipt of Util 900717 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20059K8651990-09-14014 September 1990 Forwards Interfacing Sys LOCA Insp Rept 50-382/90-200 on 900730-0810.Deficiencies in Availability of Design Calculations,Check Valve Maint & Plant Equipment Labeling Noted ML20059K3601990-09-14014 September 1990 Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise ML20059D5901990-08-28028 August 1990 Forwards Insp Rept 50-382/90-17 on 900625-29.No Violations or Deviations Noted.Exercise Weakness Re Performance of Emergency Responders Noted ML20056B4841990-08-22022 August 1990 Forwards Errata to Amend 62 to License NPF-38,consisting of Revised Bases Page Re Time Intervals for Surveillance Requirements,Per 900717 Application & Generic Ltr 89-14 ML20056B2731990-08-16016 August 1990 Ack Receipt of 900720 & 0803 Ltrs Re Objectives & Guidelines for Annual Emergency Preparedness Exercise.Objectives Appear Reasonable.Exercise Scenario & Associated Matls Should Be Submitted at Least 60 Days Prior to Exercise for NRC Review ML20058P3441990-08-15015 August 1990 Advises That Although Adequate Info Provided to Justify Continued Plant Operation Until Plant Completes Final Rept Per Schedule Delineated by NRC Bulletin 88-11,adequate Bases Not Provided for 40-yr Plant Life ML20056A0301990-07-30030 July 1990 Forwards Insp Rept 50-382/90-11 on 900625-29.No Violations or Deviations Noted IR 05000382/19900021990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-02 ML20055G7951990-07-19019 July 1990 Forwards Insp Rept 50-382/90-14 on 900625-29 & Notice of Violation.Actions Taken Re Previously Identified Insp Findings Also Examined ML20055E6501990-07-0909 July 1990 Discusses Generic Implications & Resolutions of Control Element Assembly (CEA) Failures at Maine Yankee.Waterford Unit 3 Does Not Have Old Style CEAs Installed in Reactor Core & Does Not Plan to Use Any in Future ML20055C9751990-06-26026 June 1990 Forwards Page 6a for Insertion in Insp Rept 50-382/90-09 ML20055C7781990-06-15015 June 1990 Forwards Insp Rept 50-382/90-09 on 900501-31.No Violations or Deviations Noted.One Unresolved Item Identified.Licensee Test Acceptance Criteria Did Not Appear to Account for Effect of Flow on Valve Closing Time ML20059M9171990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4121990-03-0202 March 1990 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Imposed by NRC 900202 Order.Corrective Actions Will Be Examined During Future Insp ML20055C2991990-02-23023 February 1990 Advises That 890410 Changes to Emergency Plan,Acceptable ML20248G1871989-10-0202 October 1989 Forwards Insp Rept 50-382/89-25 on 890828-0901.No Violations or Deviations Noted ML20248C6531989-09-27027 September 1989 Forwards Insp Rept 50-382/89-23 on 890801-31.Violations Noted.Enforcement Conference Scheduled for 891011 in Region IV Ofc to Discuss Violation,Reason for Occurrence & Corrective Actions ML20248A4091989-09-26026 September 1989 Requests That Jl Pellet Be Removed from Distribution for Controlled Documents Updates & Revs ML20247Q4211989-09-22022 September 1989 Provides Results of Review of Amend to Rev 5 of Inservice Testing Program for Pumps & Valves.Amend to Rev 5 Acceptable for Implementation & That Testing Requirements Impractical for Item for Which Relief Being Granted ML20247R5681989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-92,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, for Signature ML20247J6851989-09-15015 September 1989 Forwards Insp Rept 50-382/89-16 on 890717-21 & Notice of Violation ML20247D4781989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-05 ML20247F2211989-09-0808 September 1989 Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62 ML20247H8501989-09-0808 September 1989 Ack Receipt of 890531 & 0821 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07. NRC Disagrees W/Licensee Denial of Violation.Implementation of Corrective Actions Will Be Reviewed During Future Insp ML20246P6081989-09-0606 September 1989 Forwards Summary of 890712 Meeting w/C-E Owners Group & Utils Re General Design Features of Diverse ESFAS to Be Installed,Per 10CFR50.62.Safety Evaluation on Plant Design Expected to Be Issued in Near Future ML20246N3131989-08-31031 August 1989 Ack Receipt of Re Violations Noted in Insp Rept 50-382/89-08 & 890516 Notice of Violation.Requests Supplemental Response Re Examples 1-3 of Notice ML20247A5841989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.Agenda & List of Attendees Also Encl ML20246M6491989-08-29029 August 1989 Forwards Amend 56 to License NPF-38 & Safety Evaluation. Amend Increases Frequency of Channel Calibrs from Quarterly to Monthly on Waste Gas Holdup Sys Explosive Gas Monitoring Sys ML20245J0021989-08-14014 August 1989 Confirms 890808 Conversation W/Rp Barkhurst Re Util Participation in NRC Impact Survey Scheduled for 891010 & Submits Info Re Survey ML20245L3311989-08-11011 August 1989 Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation IR 05000382/19890121989-08-11011 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-12.Excluding Incident 1,Violation 382/8912-02 Should Stand as Cited. Response W/Corrective Actions Requested within 30 Days ML20245J2451989-08-0909 August 1989 Advises That Requalification Exams Scheduled for Wk of 890911 Changed to Wk of 890905 to Accommodate New INPO Schedule Issued in May 1989 IR 05000382/19890051989-07-31031 July 1989 Discusses Insp Rept 50-382/89-05 on 890213-17 & Forwards Notice of Violation.No Addl Info Was Provided to Change NRC Position & Therefore Util in Violation of Requirements.Basis for NRC Determination of Violation Provided IR 05000382/19890061989-07-28028 July 1989 Ack Receipt of 890706 Supplemental Response Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-06 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20196E6931999-06-22022 June 1999 Forwards Corrected Ltr Re Changes to Rev 19 to Emergency Plan.Original Ltr Had Error in Subject Line ML20196E0831999-06-21021 June 1999 Forwards Insp Rept 50-382/99-12 on 990524-27.No Violations Noted.Purpose of Insp Was to Conduct Assessment of Emergency Preparedness Program ML20196D9941999-06-18018 June 1999 Forwards Insp Rept 50-382/99-11 on 990524-28.No Violations Noted ML20195J8091999-06-17017 June 1999 Forwards Safety Evaulation Re First 10-yr Interval Inservice Insp Relief Request for Plant,Unit 3 ML20196C8711999-06-15015 June 1999 Discusses Insp Rept 50-382/99-08 & Forwards Notice of Violation Re Unescorted Access Which Was Mistakenly Granted to Individual Whose Background Investigation Indicated That He Had Failed Prior Drug Screening with Another Employer ML20196F3721999-06-0909 June 1999 Corrected Ltr Forwarding Rev 19 to Emergency Plan ML20195G3711999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981223,which Transmitted Waterford 3 Steam Electric Station Emergency Plan,Rev 24,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20207E8541999-06-0303 June 1999 Forwards SE Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressurizer Safety Valves at Plant,Unit 3 ML20207G3441999-06-0303 June 1999 Forwards Insp Rept 50-382/99-09 on 990411-0522 & Notice of Violation.One Violation Identified & Being Treated as Noncited Violation C ML20207D3771999-05-27027 May 1999 Ack Receipt of 990401 & 0504 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-01 on 990303 ML20207A5121999-05-24024 May 1999 Refers to Which Responded to NOV & Proposed Imposition of Civil Penalty Sent by .Violations A,B & E Withdrawn & Violations C & D Changed to Severity Level IV ML20206U7851999-05-18018 May 1999 Forwards Insp Rept 50-382/99-06 on 990405-09.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML20206N6961999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S4411999-05-10010 May 1999 Forwards Insp Rept 50-382/99-05 on 990228-0410.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3841999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamental Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam,With Answer Key,Encl for Info.Without Encl ML20206K0951999-05-0606 May 1999 Discusses Insp Rept 50-382/99-08 Issued 990503 Without Cover Ltr Documenting EA Number & Subject Line Indicated NOV Which Was Incorrect.Corrected Cover Ltr Encl ML20206F4701999-05-0303 May 1999 Forwards Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Re Failure to Review & Consider Derogatory Access Authorization Background Info as Required by PSP Identified & Being Considered for Escalated Enforcement Action ML20206K1211999-05-0303 May 1999 Corrected Cover Ltr Forwarding Insp Rept 50-382/99-08 on 990405-07.One Violations Noted & Being Considered for Escalated EA ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M0561999-04-0909 April 1999 Forwards Insp Rept 50-382/99-04 on 990301-19.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20205J8781999-04-0505 April 1999 Forwards Insp Rept 50-382/99-02 on 990117-0227.No Violations Noted.Inspectors Determined That Six Violations Occurred & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20205J0901999-04-0202 April 1999 Informs That Info Submitted by & 970313 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) ML20205A4681999-03-26026 March 1999 Forwards Insp Rept 50-382/99-03 on 990308-12.Two Violations of Radiation Protection Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205A6141999-03-25025 March 1999 Forwards SE Accepting Request to Use Mechanical Nozzle Seal Assemblies (Mnsas) as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Application at Plant,Unit 3 ML20205F3311999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Plant,Unit 3 PPR Review,Which Was Completed on 990211.Performance at Plant,Unit 3 Was Acceptable ML20204E4941999-03-17017 March 1999 Discusses TSs Bases Change Re 3/4.4.1,3/4.6.1.7,3/4.6.3, 3/4.7.12 & 3/4.8.4.Forwards Affected Bases Pp B 3/4 4-1, B 3/4 6-3,B 3/4 6-4,B 3/4 7-7 & B 3/4 8-3 ML20207F1251999-03-0303 March 1999 Forwards Insp Rept 50-382/99-01 on 990125-29 & 0208-12 & Notice of Violations ML20203H8501999-02-17017 February 1999 Forwards SE Accepting Licensee 970701 Submittal of Second Ten Year ISI Program & Associated Relief Request for Plant, Unit 3.Nine Relief Requests Had Been Authorized Previously & Proposed Alternatives Remain Authorized ML20203D7211999-02-11011 February 1999 Forwards Request for Addl Info Re Licensee 970317 & 990111 Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Response Should Be Provided within 60 Days 1999-09-09
[Table view] |
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.. . JUL 1- 1987
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In Reply Refer To:
. Docket: 50-382.
- i. -
1 LouisianaPower&LightComhany ATTN: J.'G. Dewease, Senic Vice President l Nuclear Operations.
N-80' , j
, 317 Baronne Street New Orleans, Louisiana 70160 Gentlemen:
This forwards, for your information, reports recently received Ly the Commission
.under the reporting requirements of 10 CFR Part 21. The attachments 1 and 2 were inadvertently omitted from our letter of June 23, 1987.
Although no response is required to this letter, we shall be please:I to answer any questions which you may have regarding this matter.
Sincerely, original Signed Dy J. P. Jnudon J. E. Gagliardo, Chief Reactor Projects Branch Attachments:
- 1. Arizona Nuclear Power Project letter dated March 2, 1987
- 2. ISOMEDIX letter dated March 30, 1987
- 3. SOR,. Inc, letter dated April 27, 1987 l cc: .
Louisiana . wer & Light Company ATTN: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B i
'Killona, Louisiana 70066 Louisiana Power &. Light Company ATTN: N. S. Carns, Plant Manager P. O. Box B
.Killona, Louisiana 70066 (cccont'dnextpage)
I t A P .' P J C: , A . RI p,\
5 kW:cs JPJaudon J G- liardo /v
'(f]/'/87 J/(/87 y//87 / i 8707060699 870701 DR ADOCK Of y2 i
Louisiana Power & Light Company !
Middle South' Services ATTN: Mr. R. T.- Lally P. O. Box 61000 New Orleans, Louisiana 70161 Louisiana Power & Light Company ATTN: K. W. Cook, Nuclear Safety and Regulatory Affairs Manager 317 Baronne Street P. O. Box 60340 New Orleans, Louisiana 70160 Louisiana Radiation Control Program Director bec to DMB (IE19) bec distrib. by RIV: ,
RPB D. Weiss, RM/ALF i RRI R. D. Martin, RA >
SectionChief(RPB/A) DRSP RPSB RSB MIS System Project Inspector, RPB RSTS Operator R. Hall RIV File NRR Project Manager i i
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- f. ,,
. Attachment 1 Arizona Nuclear Power Project ' ' t- .
eo eensaou . enormx. AmzonAescra-rou ./ ,,,
March 02, 1987 023-02100-JGH/DRL U. S. Nuclear Regulatory Commission Region V 1450 Maria lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. F. Kirsch, Director Division of Reactor Safety and Projects Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, 3 Docket Nos. 50/528, 529, 530
Subject:
Final Report - RER-QSE 87-11 A 10CFR21 and 50.55(e) Reportable Condition Relating to Unit 2 "A" Diesel Generator Engine Fire File: 87-006-216
Reference:
(A) Telechone conver==+4an between R. C. Sorenson and D. R.
Larkin on February 26, 1987. (Initial Notification -
RER-QSE 87-11)
Dear Sir:
The NRC was notified of a Reportable Condition in the Unit 2 "A" Diesel Generator at PVNGS by reftrence (A).
Attached, is our final written report which satisfies the reporting requirements of 10CFR21 and 50.55(e) with the exception of paragraph 21.21(b)(3), subpart vi with regard to the names and locations of other facilities which may be affected. A copy of this report will be sent to Cooper Energy Services for their evaluation. I Very truly yours, I
C Ha'yn Vice President Nuclear Production JGH/DRL:Idf DESIGEATED 02ICINAL Attachments }
Cartifies By_ ty) ,(fy,g,x %
cc: See Page 2 'I -*
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4 023-02100-JCH/DRL March 02, 1987 Final Report - EER-QSE 87-11 1 Mr. D. F. Kirsch Director "
Page Two cc: J. M. Taylor Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A. C. Gehr (4141)
R. P. Zimmerman (6295)
Records Center Institute of Nuclear Power Operations
. 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339
7
(.
- FINAL REPORT - RIR-QSE 87-11 DEFICIENCY EVALUATION 50.55(e)
ARIZONA NUCLEAR POWER PROJECT (ANPP) 1 PVNGS UNITS 1, 2, 3 ,
I. Description of Deficiency On February 8, 1987 at 2031 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.727955e-4 months <br />, fire alarms for the Unit 2A diesel generator engine were received in the control room.
73ST-2DG-01 (Integrated Safeguards Testing) was being performed on the Unit 2A diesel generator. The control room operators dispatched an Auxiliary Operator to investigate the cause of the alarms. Ihe Auxiliary Operator reported an engine fire near the 4R and SR cylinders. The Unit 2A diesel engine was tripped and the Fire Protection Department was notified. The fire was extingushed at approximately 2052 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.80786e-4 months <br /> by manual hosing down with water. The Shift Supervisor immediately secured the area for safety considerations and root cause analysis.
Investigations to determine the extent of obvious damage and possible root causes were conducted on February 9. The following observations were made:
A. The 3R, 4R, SR, and 6R valve covers sustained various degrees of fire damage. The 4R aluminum alloy valve cover showed the most damage and portions were melted away. Valve cover SR was melted to a lesser degree than 4R. Valve covers 3R and 6R were charred but no permanent damage was noted.
B. The exhaust manifold showed charring at the 3R, 4R, SR, and 6R areas.
C. The lube oil header box showed charring and some deformation at the 4R, SR, and 6R areas.
D. Junction Box No. 3 for pneumatic trips was charred and some instrument root valve handles were burned.
E. The 3R, 4R, and SR fuel injection pumps showed varying amounts of fire damage.
F. The 4R and SR fuel injectors showed fire damage.
G. The crankcase, crankshaft inspection ports, instrument tubing, jacket water header, and explosion doors showed evidence of sooting and charring.
H. The SR fuel injection tube was found disengaged from the connector at the fuel injector. The ferrule was still in the injector.
Evaluation The fire has been determined to be caused by the disengaged fuel injection tube at the 5R injector. This fuel injection tube assembly was purchased from Cooper Energy Services as a
l 1
replacement part and was recently installed. After the tube became disengaged from the injector fitting, pulsating fuel sprayed onto the 4R and SR valve covers and other nearby engine responents. 1he ;
fuel eventually contacted the exhaust manifold and combustion occurred. Diesel fuel from the SR injector pump continued to feed the fire until the engine was stopped. This fire is considered by ANPP and the vendor, Cooper Energy Services (C.E S.), to be an external engir' fire with external engine damage.
During the investigation, ANPP determined that the nuts supplied with all the fuel tube assemblies (original equipment and _
replacements) were not manuf actured to SAE J521b specifications.
The nu u suppu eo to Au r do not have the proper 45 degree chamfer as specified in SAE J521b. Although not the root cause of the Unit 2 diesel engine failure, the ferrule manufacturer (Weatherhead, DANA Corporation) states that the 45 degree chamfer is required fcr a reliable assembly.
Root Cause The root cause for the fuel injection tube disengagement has been determined to be incorrect implementation of established manufacturing procedures f or fuel injection tubes at the vendor _'s racility The fuel injection tube assembly consists of a piece of T/2 inch 0.D. steel tubing with a 3/16 inch wall thickness, two flareless tube ferrules, and two tube nuts. ANPP purchased the replacement assemblies with the ferrules set on the tube by Cooper Energy Services.
C.E.S has determined that one of its employees has not been following the procedure that C.E.S. established for setting the ferrules. The " technique *' that the employee used to set the ferrules resulted in fuel tube assemblies that had inferior pull off strength compared to assemblies set by C.E.S. procedure. C.E.S.
states that the employee has been fabricating replacement fuel injection tubing assembifes and was not involved in the fabrication of the lines originally supplied.
Transportability The failed tube assembly was a replacement that was installed recently. The fuel injection tubes that were originally supplied with the engines have many hours of run time with no tube disengagement problems. The only suspect fuel injector tubes at 1
PVNGS are the replacements.
Unit 1 and Unit 2 Operability When the Unit 2A diesel fuel line failure occurred, and during the subsequent investigation, Units 1 and 2 were in Mode 5 (Cold Shutdown).
A valkdown of the diesel generator engines in Units 1, 2, and 3 has been performed by Operations Engineering and documented on EER 87-DG-064. 1he following fuel oil line assemblies have been identified as replacement assemblies purchased from C.E.S.:
s Engine Assemblies WO Numbers IMDGA-H01 3L,4L,8L,2R,7R,8R,9R 00209666 1MDGB-H01 3L,7R 00209666 2MDGA-H01 2L,9L,4R,5R,8R,9R 00209661 I 2MDGB-H01 3L WR 198405 .
3MDGA-H01 2L,2R,8R WR 196150 3MDGB-H01 SL WR 196150
.These items will be replaced with properly manufactured assemblies under the referenced work orders and work requests. The suspect assemblies on all the diesel engines will be replaced before each unit' enters Mode 4 (Hot Shutdown).
Safety.Significant Assessment Each PVNGS unit has redundant diesel generators as part of the Class 1E AC electrical systems. These diesels are provided to mitigate potential events described in the FSAR which assume a loss of
~
offsite power and which could be initiated during operations in Hodes 1 through 4. A diesel generator failure would constitute a substantial safety hazard. If a diesel engine fuel oil tube disengaged during plant operation the resultant loss of engine power and possible external engine fire could render the diesel generator inoperable.
II. Analysis of Safety Implications Based on the above, this condition has been evaluated as Reportable under the requirements of 10CFR50.55(e) since, if it were to remain uncorrected, it could adversely affect the safety of operations of the plant. This condition is also considered Reportable under the requirements of 10CFR21 since it could create a substantial safety hazard. This report satisfies the requirements of 10CFR21 with the exception of section 21.21(b)(3) Subpart vi with regard to the names and locations of other facilities which may be affected. A copy of this report will be sent to Cooper Energy Services for their evaluation.
III. Corrective Action A. Unit 2A Diesel J l
The fire damaged components from the Unit 2A diesel have been repaired or replaced as required. The following is a list of major components included in the 2A diesel repair.
- 1. 4R and SR power head assemblies
- 2. 4R and SR power head covers and inspection docts
. 4R and SR fuel injector assemblies and fuel lines
- 4. 3R, 4R, and SR fuel' injection pumps
- 5. 4R and SR inlet and exhaust rockers and push rods
- 6. Various control valves at,the No. 3 junction box. _
e
4 After the engine was repaired, it was restarted and has successfully completed 73ST-2DG01 (Integrated Safeguards Test).
B. Fuel Injection Tube Assemblies I The suspect assemblies in all 3 units are being replaced as described in Section 1 - Unit 1 and Unit 2 operability and as stated in EER-87-DG-072. Also, the suspect spare assemblies from the ANPP parts warehouse will be reworked to ensure proper ferrule engagement on the tube prior to release from the warehouse.
ANPP has also decided to repair the diesel engine tubing nuts to ensure conformance with the SAE chamfer requirement. The repair of the nuts will be accomplished under EER-87-DG-074 and will be completed prior to Mode 4 entry in each unit.
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aso menix g
i f March 30, 1987 Mr. Gary G. Zech, Chief Vendor Program Branch Office of Inspection and Enforcement -
U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Zech:
. As you may know, Isomedix provides gamma radiation services related to the qualification of nuclear reactor safety-related equipment. During the past few months, the nuclear equipment qualification program af Isomedix has been under close review by both our customers (equipment manufacturers and test labs) and utility end users. The scope of this review has included our past and present operating procedures and controls as well as current and historical test records. Based upon our review and the recommendations of our customers, we have instituted some changes to operating procedures and documentation methods.
One item which was noted concerns the measurement tolerance associated with the dose and dose rate values certified by Isomedix on our test reports. Dur-ing a period of the late 1970's, a value of 3% was stated as the accuracy of the dose measurement. This value was based upon literature published regard-ing the Harwell Red 4034 Perspex dosimeter, the system primarily used to moni-tor these irradiations. However, the reporting of this tolerance value ceased by the early 1980's, and from that time until recently our test reports have not stated a value for the measurement tolerance associated with reported dose
, or dose rate values.
More recently, our Technical Department studied the Harwell Red 4034 dosimetry ]
system and estimated the tolerance associated with this system to be i 8% (4% l precision, 4% bias) at the 95% confidence level. This value has been stated j in our Standard Dosimetry Procedures since 1984, and is currently being quoted {
to customers when we are requested to bid on a job as well as listed on cur- '
rent test reports. However, the magnitude of this value has become a cause of concern to one of our customers and is the reason that this report is written.
Our survey of previous test records included the test files of the Automatic l Switch Company of Florham Park, NJ. This customer has used our radiation ser-vices for three equipment qualification testing programs involving solenoid ]
l valves and three involving pressure / temperature switches. Our evaluation of l test data for these programs was reported to ASCO, and they have requested l that we report our findings to your agency under 10CFR21. Their concerns are i as follows: O t- {
-e7040304tt-870330 ,
R PT21 EMV1h ISOMEDlX INC.
}O CORPORATE Off/CES = 11 APOLLO DRIVE. WHIPPANY, NEW JERSEY 07981
- C01) 887-4700 FAX 8871476 . TELEX 317361 I, -..
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. . . . . ~ . . - . . . . . . . . . . . - . . - - - ..- . .. . . - - . . . . . .. . . . . . - - . . .
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Mr. Gary G. Zech March 30, 1987 2
- 1) That the minimum doses stated in the test reports for ASCO tests cannot be assured due to the negative measurement tolerance associated wit 6 each dose measurement. ,,
~
- 2) That the maximum dose rates stated in the test reports cannot be assured due to the positive measurement tolerance associated with each measurement.
Note: ASCO also voiced concerns regarding dose rate uniformity, test sample temperature, and test records. These subjects were listed by Mr. Steve Alexander of your staff during his April,1985 ir.spection, and were addressed in our response dated June 26, 1955. The tests in question were performed ~
between 1978 and 1984, and as such do not reflect the program revisions which were instituted in response to the 1985 E.Q. inspection.
With respect to the question of tolerance for dose and dose rate measurements, our report to ASCO listed a value of 2% for the associated time measure-ments, based strictly upon the test tolerance for calibration of timers. Fol-lowing the issuance of this report, a review of calibration records for the past 5 years was performed for the timers in question. These records show that, in fact, the 5 error associated with these timer measurements has aver-aged less than 0.7%. Based upon this result, the total tolerance associated '
with Isomedix dose rate measurements (dose / time) is estimated to be i 8.6%,
while the tolerance associated with total dose measurements (dose rate x time) is estimated to be i 9.6%.
During the time of the April 1985 E.Q. inspection, the'sub,tect of test tolerance was discussed with Mr. Alexander. Based upon our conversations at that time, it was our understanding that the 10% margins applied to test doses, as prescribed by IEEE 323, were designed to compensate for errors asso-ciated with the measurement process. As the inspection report shows, this subject was not listed at a deficiency or even a coisnent by the inspector.
For this reasen we had not taken action with regard to specifying measurement tolerances in our reports. Since our estimate of total dose tolerance is within 10%, it is our belief that the test requirements for minimum dose have been met.
In the case of the dose rate measurements, the tolerance must be considered in regard to dose rate limitations imposed by the purchase order. The ASCO tests were typically performed at dose rates well below the purchase order limita-tions, so that a potential increase of g 10% will not cause a deviation. In one case, however, test records show a dose rate of 3.97 Mrads/ hour, whereas the P.O. states the rate.to be below 4 Mrads/ hour. There most certainly have been other instances where the test dose rate was within 10% of the specified maximum value, and in these cases the potential exists for deviations from specifications. The degree of deviation would not exceed 10%, however, so the effect of this upon a qualification test is likely not significant. As stated above, this report is sent at the request of our customer, due to their con-
}
cerns over the qualification status of their products. While we do not feel that the situation is critical, we wish to bring these facts to the attention of NRC in order to receive a determination from you regarding them.
IsOMEDIX INC.
C049tATTOFFCEs e 11 APOLLO DRIVE. WHIPPANY NEW JEASEY 07961
. ** b
- Mr. Gary G. Zech March 30, 1987
- 3 Obviously, any effects upon the ASCO tests will also affect testi performed for other customers, since the same systems were used to performithe work. We would therefore appreciate hearing from you regarding this matter in order to guide our planning in this area and to assist our customers whose projects may be affected.
Sincerely yours,.
ISOMEDIX INC.
hil/V Stevein R. Thompson W ^-
Quality Assurance Manager SRT:js cc: G. Dietz ,
W. Owens J. Young L. Olsen, ASCO
\
ISOMEDIX INC.
CORPORATE OFFCES
- 11 APOLLO DRIVE. WHIPPANY. NEW JERSEY 07951 * (201) N7 4700
j Attachment 3 '
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April 27,1987 To: All Nuclear Power Plant Quallfled Pressure Switch Users Re: Preliminary 10CFR PART 21 Notice SOR is investigating a potential problem with our gauge pressure switches.
We direct your attention to NRC information Notice IN 87-16. This notice addresses the SOR Series 1, 4, 5, 6, 8,. 9,12 and 54 switches.
We have discovered several switches at Davis-Besse Nuclear Generating Station which have contained a gas bubble formation bbtween the diaphragm layers within the sensing element of the switches. The cause of the prcblem has not yet been isolated. The use of 316 stainless steel diaphragms has not completely eliminated the bubble formation as previously concluded in IN87-16. .
An indicator of a bubble formation is the increase in deadband of the pressure switch (i.e.: the rise of the increasing set point and/or the fall of
-the decreasing set point). The formation of the bubbie may cause the set point to shift outside the technical specification limits.
SOR continues to investigate the phenomena. For any questions, please contact the factory at (913) 764-2630, and ask for Nuclear Sales.
Regards: '
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u s v a: L .,
James R. Johnson Vice President - General Manager 042787-07/ES132 4 704300252 870427 gDR ADOCK 05000346 PDR &
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