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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 ML20195G3721999-06-0707 June 1999 Informs That Proposed Indicators Failed QA Assessments for Digital Verification,Validation & Control of Software. Proposed Mod Can Be Completed on-line ML20195B5021999-05-27027 May 1999 Provides Suppl Info to 990203 Request of Beco That NRC Consent to Indirect Transfer of Control of Util Interest in License DPR-35.Request Described Proposed Merger of Bec Energy with Commonwealth Energy Sys ML20207D4681999-05-24024 May 1999 Provides Addl Info to That Included in Beco Ltr 98-123 Dtd 981001,addressing NRC Concerns Described in GL 96-06, Concerning Waterhammer in Reactor Bldg Closed Cooling Water Sys ML20195B9051999-05-20020 May 1999 Forwards Completed Renewal Applications for Listed Operators.Without Encls ML20206J4901999-05-0606 May 1999 Forwards Completed License Renewal Application,Including Forms NRC-398 & 396 for Sc Power,License OP-6328-3 ML20206P0711999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, for K Walz,License SOP-10886-1.Encl Withheld IAW 10CFR2.790(a)(6) ML20206D3621999-04-27027 April 1999 Informs NRC That Final Five Sys self-assessments Required to Fulfill Commitment Made in 980828 Response to Insp Rept 50-293/98-04 Were Completed on 990422.Completion Was Delayed by High Priority Refueling Outage 12 Preparatory Work ML20205R9871999-04-21021 April 1999 Forwards Affidavit of JW Yelverton of Entergy Nuclear Generation Co Supporting Request for Withholding Info from Rept on Audit of Financial Statements for Year Ended 971231. Pages 16 & 18 of Subj Rept Also Encl ML20207B0891999-04-20020 April 1999 Forwards e-mail Message from Constituent,J Riell Re Y2K Compliance of Nuclear Power Plant in Plymouth,Massachusetts. Copy of Article Entitled Nuke Plants May Not Be Y2K Ready Also Encl ML20206A2741999-04-16016 April 1999 Dockets Encl Ltr Which Was Sent to AL Vietti-Cook Re Condition of Approval of Transfer of License & License Condition for DPR-35.Encl Resolves Issues Between Attorney General of Commonwealth of Massachusetts & Applicants ML20205P9131999-04-16016 April 1999 Submits Applicant Consent to Listed Condition of Approval of Transfer of License & License Condition for License DPR-35 & Affirmatively Request That NRC Adopt Listed Language in Order ML20205P9271999-04-16016 April 1999 Withdraws Motion for Leave to Intervene & Petition for Summary Or,In Alternative,For Hearing.Requests That NRC Adopt Condition of Approval of Transfer of License & License Condition Agreed to Beco & Entergy Nuclear Generation Co ML20205Q9231999-04-15015 April 1999 Forwards Proprietary & non-proprietary Addl Info in Support of Request to Transfer of Plant FOL & Matls License to Entergy Nuclear Generation Co.Proprietary Info Withheld,Per 10CFR2.790 ML20205P9631999-04-15015 April 1999 Provides Attachments a & B in Support of Request for Transfer of Plant Operating License & NRC Matl License from Beco to Entergy Nuclear Generation Co as Submitted in Ref 1. Info Provided in Response to Request at 990413 Meeting ML20205H9281999-04-0707 April 1999 Requests Withdrawal of Uwua Locals 369 & 387 Unions Joint Intervention in Listed Matter ML20205F3731999-04-0202 April 1999 Submits Addl Info Provided in Support of Request for Transfer of Pilgrim Nuclear Power Station Operating License & Matls License.State of Ma Order Authorizing Divestiture & Copy of Financial Arrangement Encl ML20204H3771999-03-26026 March 1999 Informs That Local 387,Utility Workers Union of America,AFL- Cio Voted to Approve New Contract with Entergy Nuclear Generation Co & Voted to Accept Boston Edison Divestiture Agreement ML20205D4231999-03-24024 March 1999 Forwards Decommissioning Funding Rept for Pilgrim Nuclear Power Station,In Accordance with 10CFR50.75(f)(1) 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARBECO-90-108, Forwards Anticipated Operator Licensing Exam Schedule Requested by Generic Ltr 90-07, Operator Licensing Natl Exam Schedule,1990-09-12012 September 1990 Forwards Anticipated Operator Licensing Exam Schedule Requested by Generic Ltr 90-07, Operator Licensing Natl Exam Schedule, ML20059D6641990-08-30030 August 1990 Forwards Revised Emergency Plan Implementing Procedures,Per 10CFR50,App E,Section V.W/O Encl ML20059D6791990-08-30030 August 1990 Notifies That Two Remaining Actions for Implementation of SPDS at Plant Complete,Per .Spds Procedures Modified,Identifying Sampling Panel C-19 Return Valves to Operator BECO-90-100, Advises That Valve MO-1001-50 Cannot Be Shown to Meet 30-day Mission for PASS in post-accident Environ Due to Elevated Radiation Dose Rates.Util Currently Developing Solution to Allow PASS to Meet 30-day Availability Requirement1990-08-27027 August 1990 Advises That Valve MO-1001-50 Cannot Be Shown to Meet 30-day Mission for PASS in post-accident Environ Due to Elevated Radiation Dose Rates.Util Currently Developing Solution to Allow PASS to Meet 30-day Availability Requirement BECO-90-102, Forwards Fitness for Duty Program Performance Data for Jan- June 19901990-08-23023 August 1990 Forwards Fitness for Duty Program Performance Data for Jan- June 1990 BECO-90-095, Informs That Kn Taylor Permanently Reassigned to Nuclear Training Dept as of 900717.Taylor Will Remain in Position Which Does Not Require License Certification1990-08-0808 August 1990 Informs That Kn Taylor Permanently Reassigned to Nuclear Training Dept as of 900717.Taylor Will Remain in Position Which Does Not Require License Certification BECO-90-092, Forwards, Decommissioning Funding Rept, Per 10CFR50.33(k) & 50.75(b)1990-07-26026 July 1990 Forwards, Decommissioning Funding Rept, Per 10CFR50.33(k) & 50.75(b) ML20044B3111990-07-11011 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Corrective Actions Include Replacement of Transmitters Identified in Suspect Lots & Implementation of Surveillance Program ML20044A7891990-06-19019 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status of Each Issue Encl ML20043D7181990-05-31031 May 1990 Advises That Response to NRC 900426 Safety Evaluation Re Util 880804 & 890619 Responses to Generic Ltr 88-01 Will Be Sent on 901115 ML20043A8211990-05-15015 May 1990 Notifies of Change of Senior Operator Status for Cj Martin, Per 10CFR50.74.CJ Martin Will No Longer Participate in Licensed Operator Requalification Training Program ML20042F2211990-05-0101 May 1990 Advises That Scheduled Completion of SPDS Human Factors Validation Activities Scheduled for 900630 & Sys Availability Test by 900731 ML20043B3881990-05-0101 May 1990 Responds to Violations Noted in Insp Rept 50-293/90-05. Corrective actions:82 Excess Flow Check Valves Installed & Operability of Valves Verified by Performing Surveillance Testing ML20012F5601990-04-0202 April 1990 Responds to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Instituted Biofouling Control Program in 1982 & Program Has Been Effectively Implemented at Plant & Complies W/Generic Ltr ML20012F3631990-03-30030 March 1990 Requests Temporary Waiver of Compliance from Requirements of Tech Spec Table 3.2.C-1, APRM Upscale Rod Block in Startup & Refuel Modes to Avoid Unnecessary Delay in Critical Path Surveillance Testing ML20012C6501990-03-15015 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire for Applicable Areas Delineated in Survey Encl ML20012D1931990-03-15015 March 1990 Forwards Proposed Scope & Objectives of Annual Exercise 90-04-B Scheduled for 900618 Per Lazarus 890609 Ltr, Emergency Exercise Objective & Scenerio Guidelines. Exercise Will Test & Evaluate Util EPIPs ML20012C7191990-03-14014 March 1990 Forwards Explanation of Errors in 890707 Application Re Corrective Action Plan & Advises That Errors Do Not Affect Technical Basis on Which Exemption Granted.Util Corrective Action Plan Remains Unchanged ML20011F5381990-02-26026 February 1990 Responds to Violations Noted in Insp Rept 50-293/89-12 on 891002-1119.Corrective Actions:On 891109,operations Personnel Directed,Via Night Orders,To Be More Diligent W/ Tagout Documentation & Boundary Tagging Clarified ML20011F2301990-02-23023 February 1990 Notifies of Change in Status of Senior Licensed Operator. DW Gerlits Terminated Senior Reactor Operator License on 900201 But Will Retain Position as Senior Sys & Safety Analysis Engineer ML20006G1411990-02-23023 February 1990 Advises That Tj Mcdonough Reassigned Effective 900126. Individual Will No Longer Participate in Licensed Operator Requalification Training Program ML20011F6521990-02-21021 February 1990 Forwards Inservice Insp Plan for 1990 mid-cycle Spring Outage for Facility.Augmented Insp Will Be Performed for Three IGSCC Category a Welds Using Guidance in Generic Ltr 88-01 & Criteria in NRC Bulletin 88-08,Suppl 3 ML20011F4481990-02-20020 February 1990 Forwards Revised Operability Evaluation of Salt Svc Water Pumps for Plant.Evaluation Concludes That Salt Svc Water Pumps Operable & Requirements of Tech Spec 3.5.B.1 for Pumps Met ML20006G0051990-02-20020 February 1990 Forwards Update to long-term Plan,In Accordance W/Section V.A of Plan for Long-Term Program. Util Implementing Plant Betterment Mods & Activities ML20011E7551990-02-0909 February 1990 Requests Temporary Relief from Tech Spec 4.7.A.2.b.1.d, Limiting Condition for Operation. ML19354E7661990-01-23023 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Bolting in Anchor Darling.... Review Determined That No Subj Anchor Darling Swing Check Valves or Similar Valves Installed at Facility ML20011F4441990-01-19019 January 1990 Forwards Operability Evaluation Re Salt Svc Water Pumps P208 B,C,D & E,Per 900117 Telcon.Evaluation Concluded That Salt Svc Water Pumps P208 B,C,D & E Operable & Tech Spec 3.5.B.1 Requirements Met ML20006A0761990-01-15015 January 1990 Forwards Executed Amend 10 to Indemnity Agreement B-48 ML20006A2591990-01-15015 January 1990 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Develop Program to Enhance Maint,Analysis & Testing Already Conducted on motor-operated Valves ML20005G7701990-01-11011 January 1990 Discusses Revised Schedule for Operability & Availability of Spds,Per 891221 Notification to Nrc.Rev Necessitated by Software Problems Affecting 891231 Schedule Projected in Util 890710 Ltr ML20005G7451990-01-11011 January 1990 Provides Bases for Environ Qualification of Instrumentation Monitoring Effluent Radioactivity & Status of Standby Power Per Reg Guide 1.97,Rev 3 & Generic Ltr 82-33 ML20005G8061990-01-11011 January 1990 Advises That Commitment to Complete Enhancements of Control Panels as Part of Dcrdr,Per NUREG-0737,Item I.D.1 by Oct 1989 Not Met.All Three Panels at Simulator Enhanced & Installation of Revised Meter Scales in Progress ML20005F0761990-01-0404 January 1990 Forwards Revised Inservice Test Program in Response to Generic Ltr 89-04.List of Inservice Test Program Relief Requests Previously Submitted & Acceptable,Per Generic Ltr 89-04,encl ML20005E5601989-12-29029 December 1989 Certifies That Util Has Established Fitness for Duty Program That Meets Requirements of 10CFR26.Drug & Alcohol Level Screening Match Rule Imposition & Implementation Will Be Effective on 900103 ML20042D4821989-12-26026 December 1989 Responds to Violations Noted in Insp Rept 50-293/89-10. Corrective Action:Radiological Section Standing Order 89-09 Issued Allowing Only Radiological Supervisors to Exercise Locked High Radiation Area Door & Key Control ML20011D6851989-12-14014 December 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML20011D1631989-12-14014 December 1989 Forwards Pilgrim Nuclear Plant Station Final Assessment Rept, Summarizing Results of self-assessments & Evaluations Conducted Throughout Implementation of Plant Restart Plan & Power Ascension Program ML19325F2751989-11-10010 November 1989 Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Util Installed H2/02 Analyzers Procured in 1980 & Therefore Exempt from Bulletin Requirements ML19327C0911989-11-0606 November 1989 Forwards Response to Suppl 3 to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Since cyclic- Thermal Heatup/Cooldown Not Present in Piping,Failure Due to Cyclic Thermal Fatigue Will Not Occur ML19325E8581989-11-0101 November 1989 Discusses Litigation Before FERC Re Plant.Util Will Undertake Review of Matls Developed by Opposing Parties in Proceedings.Required Repts Will Be Submitted to NRC After Reportability Has Been Determined ML19325E5251989-10-27027 October 1989 Responds to Generic Ltr 88-20,Suppl 1,describing Plan for Completing Individual Plant Exam for Severe Accident Vulnerabilities.Performance of Level 1 PRA Based on Current Plant Design & Operation Intended ML19325E5661989-10-27027 October 1989 Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Revised Inservice Testing Program Which Will Include Statement of Conformance to Technical Positions Will Be Submitted by 891215 ML19324B8191989-10-25025 October 1989 Informs That C Leonard & J Stokes Reassigned to Positions Which Do Not Require License Certification Effective 891003 & 891020,respectively ML19327B2291989-10-20020 October 1989 Responds to Generic Ltr 89-07 Re Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs.Changes Made to Contingency Plan,Per 10CFR50.54.Plan Withheld (Ref 10CFR73.21) ML19325E0981989-10-20020 October 1989 Responds to NRC Re Violations Noted in Insp Rept 50-293/89-07.Corrective Actions:Terminal Block Replaced, post-work Functional Test of Ref Temp Switches Performed & Procedure Tp 88-78 Revised to Correct Relay Numbers BECO-89-142, Responds to NRC Re Violations & Proposed Imposition of Civil Penalty from Insp Rept 50-293/89-95. Corrective Action:Two Responsible Util Operators Suspended Because Breakers Incorrectly Positioned for Test1989-09-22022 September 1989 Responds to NRC Re Violations & Proposed Imposition of Civil Penalty from Insp Rept 50-293/89-95. Corrective Action:Two Responsible Util Operators Suspended Because Breakers Incorrectly Positioned for Test BECO-89-144, Requests Interim Approval for Relief from Testing of RHR Sys Valves 63 & 64 Until Refueling Outage 8 Scheduled for 9103151989-09-22022 September 1989 Requests Interim Approval for Relief from Testing of RHR Sys Valves 63 & 64 Until Refueling Outage 8 Scheduled for 910315 BECO-89-135, Forwards Util Anticipated OL Exam Schedule,Per 890706 Generic Ltr 89-12 Request1989-09-11011 September 1989 Forwards Util Anticipated OL Exam Schedule,Per 890706 Generic Ltr 89-12 Request BECO-89-131, Forwards Tech Spec Figures 6.2-2 & 6.2-1,replacing Title of Director of Nuclear Engineering W/Title of Station Director & Adding New Title of Vice President of Nuclear Engineering1989-09-0505 September 1989 Forwards Tech Spec Figures 6.2-2 & 6.2-1,replacing Title of Director of Nuclear Engineering W/Title of Station Director & Adding New Title of Vice President of Nuclear Engineering BECO-89-129, Submits Addl Info Re 890707 Request for Exemption from Certain Containment Leakage Testing Requirements of 10CFR50. Plant mid-cycle Maint Outage,Previously Scheduled for Oct 1989,has Been Rescheduled for Spring 19901989-09-0101 September 1989 Submits Addl Info Re 890707 Request for Exemption from Certain Containment Leakage Testing Requirements of 10CFR50. Plant mid-cycle Maint Outage,Previously Scheduled for Oct 1989,has Been Rescheduled for Spring 1990 1990-09-12
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o BOSTON ECISON COMPANY QENEMAL Orrects 800 SovtaTON STREET BosTO N. M AS S ACNUS ETT5 0 219 9 A. V. M O RIB 1 MANAGER NUCLEAR QPERATIONS SUPPQRT OEPARTMENT BECo Ltr. #80-253 Mr. Thomas A. Ippolito, Chief License No. W -E Operating Reactors Branch #2 Docket No. 50-293 Division of Licensing -
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Cable Peretration Fire Stop Washington, D.C. 20555 Qualification Testing for Pilgrim Nuclear Power Station Unit *1
References:
(a) NRC letter TAC 411077 dated Oct. 7, 1980, T. A. Ippolito (NRC) to A. V. Morisi (BECo)
(b) Conference call between Messrs. T. A. Venkataraman and J. D. Keyes (BECo) and M. Williams (NRC) on 10/10/80 (c) Fire Protection System Review APCSB 9.5-1, dated March 1, 1977 for Pilgrim Station Unit
- 1 and its Appendix II
Dear Mr. Ippolito:
In accordance with the requests for additicnal information on item 3.1.19 and 3.2.4 of the SER conveyed to BECo per References (a) and (b), we submit the following information on BECo's Cable Penetration fire Stops Qualifi-cation Tests, the recommendations that were concluded at the end of the tests, and additional information on Kerite cables in use at Pilgrim Station.
All penetration fire seals were tested using the time-temperature exposure curve specified by ASTM E-119 using criteria specified in IEEE 634. It is to be noted that BECo's qualification criteria fall in line with the recuiranents that are presently being oursued by the industry and a host of licensees.
Additional information relative to the Kerite cables is provided in Attachment A. We believe this information will satisfy SER requirements on Item 3.2.4.
The following is a summary of cable penetration fire stop testing that was performed for Pilgrim Nuclear Power Station Unit #1. We have detailed the different types of cable penetrations that were tested and qualified in 0Y their as-installed status along with the engineered fixes that were 9 9l qualified for the failed fire seals.
Be1021oQ$
C'.STON EDISQN COMPANY Mr. Thomas A. Ippolito, Chief October 13, 1980 Page Two Based on the results obtained for all the three tests as summarized in at-tachment B to this letter, BECo proposes the following recomendations for upgrading the cable penetratior, fire seals at Pilgrim Station.
- 1. Wall Penetrations Conduit Sleeves / Cable Trays The As-Built configuration (Reference (c) Sheet II-A4 and II-AS) of conduit sleeves / cable trays that exist at PNPS Unit #1 specified 6 inches of "non-burnin9" Instafoam in the center of the wall thickness. This configuration was tested and qualified in the modified condition as Sleeve #5, Test #2.
Recommendation I
BECo will upgrade all wall conduit / tray sleeves by adding 2" of ;
Kaowool and I inch of Flamemastic 77 on both sides of the sleeve / tray.
{
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- 2. Floor Penetrations A. Floor Blockout
]
l Typical floor penetrations that exist at PNPS #1 and as detailed in Reference (c) Sheet II-A3 had 6 inches of Instafoam with 2 inches of Kaowool on both sides. This configuration was tested in its As-Built condition (Sleeve 2 & 4 of Test 2) and did not pass IEEE 634 criteria for acceptance for 3-hour rating. The seals were requalified with fixes (Sleeve 1, Test 2; Sleeve 1, 2 & 4 of Test 1).
Recommendations All floor penetration seals of the above As-built configuration will .
be upgraded to 3-hour rating by providing 1" Flamemastic 77 interposed !
on top of Kaowool along with a' coating of 1/8" dry Flamemastic to a j length of 3 feet on the Kaowool side of the-penetration. (See Sleeve l
It is to be noted that the As-Built status of the penetration had the grout side on the floor level. -If the fire in its conservative form is postulated to occur at the penetration location below the floor level on the Kaowool side, Sleeve #2 of Test i establishes that the seal will qualify for 3-_ hour rating. If the fire is postulated at the I
floor level on the grout side (non conservative), the penetration will need upgrading on the Kaowool side as described above.
OC3 TON ' EDISON COMPANY Mr. Thomas A. Ippolito, Chief October 13, 1980 Page. Three B. Vertical Projected Conduit Penetration Typical floor- penetrations that exist at PNPS #1 and as detailed in Reference (c) Sheet II-Al, had 6" of Instafoam with 1" of non-shrinkable grout on the floor side with 2" of Kaowool on the ceiling side below.
Recomenda tione ,
No modifications are recomended to these types of penetration seals. This recomendation is supported by the performance of sleeve #3 and #6 of Test 2 and Sleeve 83 and e6 of Test #1.
C. Vertical Tray Penetrations Typical As-Buil t floor tray penetrations had 6" Instafoam with .1" grout on the floor side and 2" of.Kaowool on the ceiling side below the floor.
The As-Built configuration was tested with fix 2. The fix included l" thick !
Flamemastic 77 on top of grout, as well as if ' dry Flamemastic 77 over cables in the tray for a length of 3 feet. Tray-l Tes 3 tested with fire on Kaowool side ;
passed the test criteria. Test results of '. ray-2 of Test #3 supported the post-
'clization that a fire on the grout side could lower the fire seal rating, since !
the penetration seal failed the IEEE 634 criteria for thermocouple temperatures )
recorded at the Kaowool surface on the cold side. However, an evaluation of l thennocouple readings (#21, #22 and #25) establishes that the test configuratien will rass the IEEE 634 criteria if the penetration seal surface is level with the siab surface.
Recomenda tions BECo will upgrade all tray penetrations by adding 4" of Kaowool to the existing 2" of Kaowool with 1" of Flamemastic 77 added to its final surface.
General BECo has compir.ted an extensive plant survey of all its As-Buil t penetrations for upgrading as well as surveillance purposes. In order to accomplish the l recomended fixes detailed above BECo requests the review and approval of these fixes as mandated by the SER. Upon receiving an approval BECo intends ,
to proceed ahead with the modifications.
1 On a conservative time estimate we have detennined that these fixes can be accomplished by the next refueling outage.
C;5 TON EDISON COMPANY Mr. Thomas A. Ippolito, Chief October 13, 1980 Page Four.-
-If during your review of.the above, you should require additional infonna-tion,please do not hesitate to contact us.
Very truly yours, JK/mam
't i
Attachments A. Kerite Co., Letter to Boston Edison Company da ted 10/10/80 with attached Test _ Reports. l l
-B. Stone & Webster Co., Letter to Boston Edison Company dated 10/14/80 i with attached " Summary of Cable Penetration Fire Stop Testing for l Pilgrila Unit #1".
ATTACHMENT A 49 Day Street Seymour, Connecticut 06483 (203) 888-2591 o? Y o the kerite company n
t' October 10, 1980 l
1 Mr. Rich Ventakaramen l Boston Edison Company 800 Boylstoa Street l Boston, MA 02199 l j
Dear Sir:
SUBJECT:
KERITE CABLES PROVIDED FOR PILGRiH #1 NUCLEAR STATION At the request of Mr. Keith Petty, Stone & Webster Engineer-Ing Corporation, we are enclosing copies of IEEE 383 prototype flame tests. Test #77VG65-P covers Kerite SKV non-shielded cables furnished, Test #80VG10-P covers the 600V power cables, and Test #76VG6-C covers the 600V control cables. These tests were performed on cables with the same insulation and jacket ma- I terials as those furnished for Pilgrim Nuclear Station.
This clearly demonstrates the Kerite cables furnished Boston Edison Company for Pilgrim Nuclear Station #1 will not propagate a fire when tested in accordance with IEEE 383 Yours truly, THE KERITE COMPANY
. N. Sleig National Manager l Power Plant Generation j ENS:ss '
Encs, i
1 a subsidiary of HARVEY HUBBELL INCORPORATED Hu u.
i . ...: .... . . . i . .
. . . . . . . , . . . . ~ .-
tha kerite company REPORT ON FLAME TEST CONDUCTED ON POWER CABLES 1
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TEST NO. 77 VG 65-P 3 REF.NO. 1G-11/10/77 l 2G-11/10/77 !
3G-11/10/77 I
! November 10, 1977 I
! A. OBJECTIVE The objective of this flame test is to demonstrate that an HTK insulated, HT-l NS jacketed power cable will not propagate a fire.
B. CABLE TESTED !
j 1/c,1000 kemil, 5 KV,155 mils HTK insulation,125 mLis IITNS jacket.
I
[ C. TEST FACILITY
- The tests were conducted on November 10,1977 at The Kerite Company Fire !
Test Facility. An American Gas Furnace Company 10-inch wide ribbon burner was used to provide the flame source. A direct readout Omega Pyrometer was used in conjunction with a thermocouple to monitor flame temperature throughout j the test. A laboratory timer was used to measure the duration of the test. The i test specimen was installed in a 12-inch wide, 3-inch deep,11-foot high, ladder type tray, l
D. TEST PROCEDURE (IEEE 383) )
A single layer of three 8-foot lengths of test cable was mounted in the center l six inches of the tray, allowing a space of one-half cable diameter between cables. !
The flame source was adjusted so that the temperature was approximately i 1500 F and approximately 15 inches in length. Under dynamic conditions, the j- following manometer readings were recorded for both air and fuel in centimeters of water.
- i l
Air Fuel
, Test No.1 4. 2 2. 7 j
- Test No. 2 4. 7 2. 6 1
- Test No. 3 4. 8 2. 7 l l
e
.. s - - _ . - , . ,
l tha kerite company Test No. 77 VG 65-P 32 11/iFl7 These pressures,were measured for both air and fuel at the inlet of the mix-er.
The flame source was placed three inches away from the cables and allowed to burn for twenty minutes. At the end of twenty minutes, the flame source was shut off and the cable was allowed to burn until it self-extinguished or was totally consumed. All pertinent data was recorded. The temperatures indicated in the next section were measured by a thermocouple located 2 7/8" from the burner face. The test was performed three times for reproducibility.
E. TEST DATA Test No.1 Test No. 2 Test No. 3
- 1. Time for specimen to ignite 1 min. 23 sec. 1 min. 32 sec. 1 min.15 sec.
- 2. Time specimen continued to bum after removal ci flame source 0 sec. 11 min. 1 min. 30 sec.
- 3. Max. length of sample burned 221/2" 291/2" 25"
- 4. Minutes Flame Impingement Temperature (OF)
Start 1500 1500 1450 1 1550 1625 1550 2 1400 1550 1450 3 1275 1500 1525 4 1300 1600 1500 5 1350 1650 1425 6 1300 1625 1525 7 1325 1575 1350 8 1350 1700 1350 9 . 1350 1650 1500 10 1325 1650 1500 11 1350 1575 1500 12 1350 1650 1600 13 1350 1675 1575 14 1350 1725 1575 15 1350 1700 1575 16 1350 1650 1550 17 1325 1650 1550 18 1350 1725 1550 19 1350 1625 1600 20 1350 1650 1600 e
th'2 kerite company Test No. 77 VG 65-P
- p. 3 11/10/77 F. CONCLUSIONS AND RECOMMENDATIONS This cable shows no evidence of propagating a fire. This type of cable thus qualifies as a fire resistant cable in the context of the IEEE 383-74 specification.
G. ATTESTATION The above test was personally witnessed by the und< algned and the data pre-sented above is accurate and complete to the best of my ,nowledge and belief.
l l
l l
h L4o
[/ John V. Osborn JVO/dm V Technician APPROVED hul I
. Basconi, Mechanical Engineer he' Subscribed and sworn to before me this lith day of September,1977.
0nte- l$ll
/ Notary Public
. My Commitsien Expires March 31,1979 i
l
- -w- x. . . - - ~ . _ . . . _ _ _ - . ~ . - _ - - -.x m thb kerite company.
' ~' '~
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. REPORT ON FLAME TEST CONDUCT D ON POWER CABLE
' TEST NO. 80VG10-P-
, Ref. No. 1G-3-25-802 l 2G-3-25-802 3G-3-25-802 March 25, 1980 A. OBJECTIVE 4
T[ha' objective of this flame test is to demonstrate that an HiK insulated, FR jacketed i . power cable will not propagate a fire. , ,
i l j B. -CABLE TESTED l 1 . ,
! No. 6 AWG Str, 600v, 5' 5 mils, HTK and 65 mils FR Jacket.
C. TEST FACILITY '
, 1 i 'Tha' tests were conducted on March 25, 1980 at The Kerite Company Fire Test Facility.
l An American Gas Furnace Company 10-inch wide ribbon burner was used to provide the fitme source. A direct readout.0mega pyrometer was used in conjunction with a thermo-couple to monitor flame temperature throughout the test. A laboratory timer was used to measure the duration of the test. The test cable was installed in a 12-inch wide,
- 3-inch deep, 8-foot high ladder type tray In a vertical configuration. !
l D. TEST PROCEDURE (IEEE 383-1974) l l ' A single layer of 10 8-foot lengths of test cable was mounted in the center six inches j 13f the tray, allowing a space of one-half cable diameter between cables.
Tha flame source was adjusted so that the temperature was approximately 1500 F and cpproximately 15 inches in length. Under dynamic conditions, the following manometer raadings were recorded for both air and fuel in centimeters of water.
Test No. Air Fuel (propane) i 1 I 4.4 2.4 I i 2 4.4 2.4 3 %.4 2.4 Thsse pressures were measured for both air and fuel at the inlet of the mixer.
Th2 flame source was placed 3 Inches away from the cables and allowes to burn for ~
20 minutes. At' the end of 20 minutes, the flame source was shut off and the cable silowed to burn until.it self-extinguished er was totally consumed. All pertinent j data was recorded. .The temperatures indicated in the next section were measured by i e thermov.cuple located 1/8" from the cable samples. The test was performed three times for reproducibility.
h
.s . '. .
't.h3 kerite conipany Test No. 80VP.10-P March 25, 1980 REPORT ON FLAME TEST CONDUCTED ON POWER CABLE E. TEST DATA Test No. 1 Test No. 2 Test No. 3
- 1. Time for cable to -
Ignite. 38 sec. 48 sec. 40 sec.
- 2. Time cable continued to burn after removal of flame source. -
0 sec. O sec. O sec.
3 Damage insulation 33" 36" 38" Jacket 37" 41" 40"
- 4. Mine es ~
Flame imoingement Temperature ( F)
Start 1500 1500 1500 1 1525 1200 1250 2 1550 1475 1050 3 1550 1475 1550 4 1575 1550 1575 5 1600 1550 1575 6 1625 1500 1500 7 1650 1300 1400 8 1675 1250 1475 9 1675 1350 1500 10 1650 1000 1600 11 1650 1200 1600 12 1650 1350 1400 13 1650 1275 1650 14 1675 1200 1550 15 1700 1000 1500 16 1650 1250 1600 17 1700 1425 1500 18 1725 1050 1525 19 1750 1250 1600 20 1675 1075 1575 F. CONCLUSION This c:ble shows no evi.'ence of propagating a fire. This type of cable thus qualifies as a- fire resistant cable in the context of the IEEE 383-1974 speci-fication.
4 Tcst No. 8"'G10-P t,ha kerite company March 25, 1980 REPORT ON FLAME TEST CONDUCTED ON POWER CABLE G. ATTESTATION i
The above test was personally witnessed by the undersigned and the test data presented cbove is accurate and complete to the best of my knowledge and belief. ,
I i
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wh 0 %w JV0:1dh // John V. Osborn V Technician APPROVED BY: ,b- ((USv S.F. Mauser Manager, Product Development l
l Subscribed ano sworn to befort .ne this 25th day of March,1980.
s 0??) l Yl
[ Notary Public t/ CSE: d
emp Narem couwury REPORT ON FLAME TEST CONDUCTED ON CONTROL CABLES February 3,1976 Test No. 76 VG 6-C Ref. No. 1G-2-3-76 2G-2-3-76 ;
3G-2-3-76 i A. OBJECTIVE 1
The objective of this flame test is to demonstrate that an FR insulated, FR l jacketed, control cable will not propagate a fire.
B. CABLE TESTED Seven conductor No.12 (19 strand), 600 volt, 40 mils FR (HI-70) insulation, 65 mils FR (HC-711) jacket.
C. TEST FACILrfY The tests were conducted on February 3,1976 at The Kerite Company Fire Test Facility. An American Gas Furnace Company 10 inch wide ribbon burner was used to provide the flame source. A direct readout Doric Multi-Point Temperature Recorder was u.ed in conjunction with the thermocouple to monitor flame temperature throughout the test. A laboratory timer was used to measure the duration of the test. The test specimen was installed in a 12 inch wide, 3 inch deep,11 foot high ladder type tray.
D. TEST PROCEDURE (IEEE 383-1974)
A single layer of six 8 foot lengths of test cable was mounted in the center six inches of the tray, allowing a space of one-half cable diameter between cables.
The flame source was adjusted so that the temperature was approximately 15000F. and approximately 15 inches in length. Under dynamic conditions the folicwing manometer readings were recorded for both air and fuel in centi-me.te. s of water.
Air Fuel Test No.1 4. 6 2. 6 Test No. 2 4. 7 2. 8 Test No. 3 4. 4 2. 4 e
____.-c~ ----.q ,._ .r e m .~:. _ . .*e-- ---
Tud N mxTm couramv Test No. 76 VG 6-C Pg. 2
. s These pressures were measured for both air and fuel at the inlet of the
. mixer. .
The flame source was placed three inches away from the cables and al-lowed to burn for twenty minutes. At the end of twenty minutes the flame source was shut off and the cable was allowed to burn until it self-extinguished or was totally consumed. All pertinent data was recorded. The temperatures indicated in the next section were measured by a thermocouple located 2 7A" from the burner face. The test was performed three times for reproducibility.
E. TEST DATA Test No.1 Test No. 2 Test No. 3
- 1. Time for specimen to ignite - 28 sec. 29 sec. 30 sec.
- 2. Time specimen continued to burn after removal of flame source - 25 sec. O sec. O sec.
- 3. Max. length of sample burned - 23" 29" 29"
- 4. Minutes Flame Impingement Temperature ( F.)
Start 1490 1457 1486 1 1324 1334 1333 2 -
1359 1283 1270 3 1275 1197 1180 4 1258 1139 1148 i 5 1226 1149 1192 6 1263 1207 1285 7 1253 1144 1434 8 1239 1207 1376 9 1302 1274 1253 10 1244 1249 ~1102 11 1306 1215 1143 12 1287 1195 1231 13 1257 1161 1271 14 1252 1130 1246 15 1224 1126 1258 16 1220 1126 1265 17 1225 1130 1241 18- 1223 1135 1189 19 1226 1146 1191
, 20 1233 1139 1201
.-.c - , -
- . . . . . . . . . s, - ... . - - - , -.
-wagjharrncewawwy ,
Test No. 76 VG 6-C Pg.3 F. CONCLUSIONS AND RECOMMENDATIONS This cable shows no evidence of propagating a fire. This type of cable, thus, qualifies as a fire resistant cable in the context of the test configuration.
G. ATTESTATION -
The above test was personally witnessed by the undersigned and the data presented above is accurate and complete to the best of my knowledge and be- ,
lief. l
- l
// ' John Osborn i
(/ Technician l APPROVED BY <
Paul D. Basconi, Mechanical Engineer ,
Subscribed and sworn to before me this 4th day of February,1976.
~
Gw MIL Notary Public g/
My Cc: .eien sp;res 14 arch 41.1979 JO/dm
n
-Stsne & Kabstrr Engin;sring Corporation October 14, 1980 ATTACHMENT B J.O. No. 13201 SUW.ARY OF CABLE FENETRATICN FIRE STOP TEST 2fG FCR FILCRIM 1
-The cable . penetration fire stops were tested by Franklin Institute. The results are reported in 7-C5159-1, F-C3159-2, F-C5159-3.
The different types of penetrations existing in the . station and which were repre-sented in the test are as follows:
A. Vertical penetration - 6" diaceter circular blockout.
B. Vertical penetration - E= bedded conduit projecting from both sides of floor.
C. Horizontal penetration - Ecbedded conduit projecting from both sides of wall.
D. Vertical / horizontal opening with tray projecting from both sides of floor / wall.
Table 1, attached, presents a checklist as to which penetrr. tion style is represented by the various test penetrations. A pass / fail indication is included in Table 1 The pass / fail criteria is as described in IEEE 634/1978.
DISCUSSICN OF VARIOUS PENETRATIO" STYLES 1 -Panatration Stvla A In Test 1 the original design of the penetration was tested with a ccating of 1/8" dry Flace=astic 77 on the outside of the cable bundles. Saeed on the code of failure of s1v. 5 in Test 1, a 1" wet coating of Flame-mastic 77 was applied to the surface of the Kaewcol and retested (siv.1 -
Tesg 2). This design passed with the maximum back-side te=perature of 585 F.
The test-results of s1v.1, 2, 4, 5 of Test 1, indicate that the worst case conditions are maxi =um cablo fill with the fire impinging in the direction as indicated in siv. 4 of Test 1 For the situations who-9 thermoset' ting cables are used, it is recommended that the cables on the Kaowool side be coatei en the outside with 1/8" dry Fla=emastic 77 for a length of three feet.
- 2. Penetration Stvle B '
This penetration design when tested vith thermo's etting cables passed.
See siv. 3, 6 - Test 1, and siv. 3, 6 -' Test
Siv. 2, . 4 - Test 2 (penetration style " A") and siv. 3, 6 - Test 2 (pene-tration style "B") both used thermosetting cablen with r.axinum cable fill.
Gince the penetratica style B passed but style A failed, we conclude style
I 1
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2 B is inherently superior to style A. For this reason if thermoplastic 1
I cables are used in style -B penetration, only a surface coating of 1/8" dry Fla=emastic 77 on the cables will be needed.
- 3. Penetration Style C
"*he penetration design was tested with Kaowool and a 1" wet coating of Flamemastic 77 on both surfaces. This design is ry==etrical and tested with raximu= c_able fill, and therefore did.not require additional testing.
If thermoplastic cables coated with Flace=astic 77 are used in lieu of the thermosetting type cable which m re in the test, the performance of the penetration is not expected to change significantly.
- 4. - Dr:etration Style D The tested penetration design incorporated a todification on the grout side only of a) 1" Flamenastic 77 on penetration surface and b) 1/8" Flanerastic 77 coating on cable surface. The design was asymmetrical and was tested in both directions (Tray 1 and Tray 2 - Test 3). Failure occurred on Tray-2 which had fire impinging on the grout side. The fail-ure occurred where the thermocouples were located 5" down from the top i of the concrete but still on the surface of the penetratien. The ther:o-l cougles reading temperatures at the concreto level were all less than i 300 F. If 4" of Kaowool and 1" vet Flacemastic 77 on penetration surface I i were added cpposite the greut side, the aximum backside te=rerature would be well below the failure criteria.
It should be noted that Tray 1 represents the actual position of plant l installation, i.e. grout side of penetration up.
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TABT2 1 BRIEF DESCRIPTIO!! OF TEST SL72VP.S/ TRAYS A!!D IIESTII,TS ORIGINAL DESIGi ORIGINAL DESIGN PMIETRATION- ORIGIt!AL WITI! P.0DIFICATIOri WITil NODIFICATION STYIE DESIG'I aAa a n's
'.A Slv. 2, Test 2 - Fail S1v.1, Test 1 - Pass 'S1v. 1, Test 2 - Pass Sly.. 4, Test 2 - Fall S1v. 2, Test 1 - Pass Slv. 4, Test 1 - Pass Sle. 5, Test 1 - Fail D Slv. 3, Test.1 - Pass Not Applicable Not' Applicable Slv. 6, Test 1 - Pass
-Sly. 3, Test 2 - Pass
. S1v. 6, Test 2 - Pass
-G Not Tested Not Applicable Slv. 5, Test 2 - Pass D Not Tested Not Applicable Tray 1, Test 3 - Pass Tray 2, Test 3 - Fail 9
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