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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20212F4481999-09-17017 September 1999 Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 ML20212F7051999-09-14014 September 1999 Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 ML20211N0681999-09-0202 September 1999 Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager ML20211H6291999-08-26026 August 1999 Forwards NPDES Discharge Monitoring Rept for July 1999 for Indian Point,Units 1,2 & 3. Rept of Noncompliance Is Attached for Noncompliance Which Occurred at Unit 3 ML20211E1531999-08-18018 August 1999 Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) ML20211H6051999-08-18018 August 1999 Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols ML20211A9241999-08-11011 August 1999 Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr ML20210M7251999-07-26026 July 1999 Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium ML20210G8911999-07-20020 July 1999 Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager ML20209B6611999-06-29029 June 1999 Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls ML20196A6371999-06-15015 June 1999 Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21 ML20207D1861999-05-27027 May 1999 Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl ML20205R1981999-04-15015 April 1999 Requests That Dept of Environ Conservation Modify SPDES Permit for IPS IAW Proposed Rev Attached & Described as Listed ML20205R2961999-04-15015 April 1999 Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl ML20196K8111999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231 ML20205F9711999-03-25025 March 1999 Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98 ML20204F7931999-03-17017 March 1999 Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2 ML20204J9971999-03-0909 March 1999 Forwards Insp Rept 50-003/98-19 on 981130-990222.No Violations Noted ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J6171999-02-0505 February 1999 Forwards Transcript from 990120 Public Meeting Held in Peekskill,Ny Re Decommissioning ML20199H3731999-01-11011 January 1999 Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named ML20198E9561998-12-21021 December 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities Re Deliberate Misconduct in Violation of Regulation When False Info Was Provided to Two NRC Licensees ML20198C2371998-12-15015 December 1998 Ltr Contract:Task Order 237, Review & Evaluation of Indian Point 3 Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026 ML20198C4911998-12-11011 December 1998 Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld ML20198C3251998-12-11011 December 1998 Responds to ,Responding to NRC Ltr Re Concerns Raised About Potential Chilling Effect from Temp Denial of Site Access to Employee Raising Safety Issues to Util Senior Mgt ML20155H2901998-11-0303 November 1998 Responds to to Lj Callan Expressing Concern About Continued Operation of Indian Point Nuclear Generating Station.Explanation Why NRC Do Not Think Revoking OLs for Indian Point Units 2 & 3 Justified,Provided ML20155F9181998-10-28028 October 1998 Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2 ML20155D2791998-10-23023 October 1998 Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997 ML20154Q1761998-10-21021 October 1998 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Withheld in Part (Ref FOIA Exemption 7) ML20154L8031998-10-16016 October 1998 Ack Receipt of & Payment in Amount of $55,000 in Electronic Funds for Civil Penalty Proposed by NRC in .Corrective Actions Will Be Examined During Future Insp ML20155H3021998-09-24024 September 1998 Urges NRC to Revoke Operating Licenses for Indian Point Nuclear Generating Station,Units 2 & 3 & Not Renew OL for Unit 1 ML20154A1391998-09-22022 September 1998 Informs That Effective 980724,AA Blind Assumed Position of Vice President,Nuclear Power & Ja Baumstark Assumed Position of Vice President,Nuclear Power Engineering,Effective 980813 ML20153F0661998-09-18018 September 1998 Provides Response to Violations Noted in Insp Rept 50-286/98-05 & Proposed Imposition of Civil Penalty Dtd 980819.Corrective Actions:Existing Drawings for Spare Switchgear Cubicles Have Been Revised ML20151W4871998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned as SRAs for Region I ML20151W9511998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs Duties for Region I ML20155F4391998-08-26026 August 1998 Forwards Demand for Info,Being Issued to Enable NRC to Fully Understand Recipient Views on Facts & Circumstances Surrounding Allegedly False Info Provided to Two NRC-licensed Activities ML20238F5151998-08-26026 August 1998 First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Entirety. Documents Listed in App B Being Withheld in Part (Ref FOIA Exemption 6) IR 05000286/19980051998-08-19019 August 1998 Discusses Insp Rept 50-286/98-05 on 980528-0612 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Most Significant Violation Involved Failure, Following Design Mod in Oct 1997 ML20237B1001998-08-0505 August 1998 Responds to NRC Re Violations Noted in Insp Repts 50-247/97-13,50-247/97-15,50-247/98-02 & Investigation Rept 1-97-038,respectively.Corrective Actions:Acted Promptly to Assure Conforming to Testing Requirements ML20236X8511998-07-31031 July 1998 Forwards Rept Re Projection of Ability to Pay Retrospective Premium Adjustment for Period 980801-990731,per 10CFR140.21 ML20236V4211998-07-13013 July 1998 Forwards SER Approving Topical Repts WCAP-14333P & WCAP-14334NP (Proprietary & non-propiretary, PRA of RPS & ESFAS Test Times & Completion Times ML20236Q1431998-07-0808 July 1998 Responds to Administrative Ltr 98-03 Re Operating Reactor Licensing Action Estimates IR 05000247/19970131998-07-0606 July 1998 Discusses Insp Repts 50-247/97-13,50-247/97-15 & 50-247/98-02 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 ML20238F5231998-06-29029 June 1998 FOIA Request for Documents Re NRC Office of Investigation Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20154Q1831998-06-29029 June 1998 FOIA Request for Documents Re NRC OI Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20248F2891998-05-26026 May 1998 Ltr Contract:Task Order 8, Indian Point 2,A/E Follow-up Insp, Under Contract NRC-03-98-021 ML20248L9861998-05-21021 May 1998 Forwards Rev 7 to Security Force Training & Qualification Plan.Review to Verify Receipt of Revised Plan & Sign & Return Receipt Ack Form Provided ML20247M6951998-05-20020 May 1998 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, for Plant,Unit 2 1999-09-02
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058N0621990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Encouraged to Start Similar Initiative to Provide for Sharing of Info & Experiences Involving Engineering & Solutions of Problems Common to All ML20059M9111990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20059M9151990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248C4321989-09-25025 September 1989 Forwards Amend 23 to Indemnity Agreement B-19,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Effective 890701.Util Requested to Submit Signed Amend to Signify Acceptance ML20247B9451989-09-0606 September 1989 Forwards Enforcement Conference Rept 50-286/89-15 on 890808 ML20247R0751989-07-28028 July 1989 Forwards Safeguards Insp Rept 50-286/89-15 on 890605-07. Enforcement Conference Scheduled on 890808 to Discuss Previous Concerns Re Implementation of Security Program & Weaknesses in Protected & Vital Area Barriers ML20247J8311989-07-19019 July 1989 Forwards Amend 142 to License DPR-26 & Safety Evaluation. Amend Adds Surveillance Requirement to Tech Spec 4.16 Requiring Periodic Leak Testing of Low Head Injection Line Check Valves 897A-D & RHR Check Valves 838A-D ML20247C1311989-07-14014 July 1989 Provides Emergency Exercise Objectives & Scenario Guidelines to Be Used During Emergency Exercise Scheduled for Wk of 891113 ML20248C0941989-06-0505 June 1989 Forwards Amend 141 to License DPR-26 & Safety Evaluation. Amend Adds Surveillance Requirement to Tech Specs Requiring Periodic Testing of Backup Nitrogen Supply Sys for Operating PORVs ML20246Q3101989-05-0303 May 1989 Advises That Seminar to Discuss Recent Changes to Format for Requalification & Initial Exams Scheduled on 890331 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20247A0301989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20244C3121989-04-10010 April 1989 Forwards Amend 137 to License DPR-26 & Safety Evaluation. Amend Revises Tech Spec Tables 3.5-2 & 4.1-1 Requiring Operability & Surveillance Testing of Reactor Trip Breakers Shunt Trip Attachment ML20154Q7111988-09-21021 September 1988 Discusses Insps During 860816-870925 Re Environ Qualification & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Advises That 25% Mitigation Warranted ML20153C6611988-08-25025 August 1988 Forwards Corrected Amend 135 to License DPR-26 & Safety Evaluation,Correcting Administrative Errors Listed & Replacing Amend Issued on 880819.Corrected Ltr Forwarding Attachments Also Encl ML20153D0261988-08-19019 August 1988 Forwards Amend 135 to License DPR-26 & Safety Evaluation. Amend Temporarily Modifies Tech Spec 5.2.C, Containment Sys, Tech Specs Basis 3.3-10 & Updated FSAR Table 9.6-1, Essential Svc Water Requirements at 75 F River Water Temp ML20151V1471988-08-17017 August 1988 Informs That Financial Info Submitted in Satisfies Requirements of Section 140.21 of 10CFR140.Rule Requires That Each Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor ML20154M1821988-05-25025 May 1988 Forwards Safeguards Insp Rept 50-247/88-12 on 880407.No Violations Noted ML20236M9451987-11-0505 November 1987 Ack Receipt of Util Transmitting Proposed Amend to Plant Physical Security Plan.Comments on Physical Security Plan Changes Re Miscellaneous Amends & Search Requirements Encl.Response Requested within 30 Days ML20236E4201987-10-22022 October 1987 Forwards Trip Repts from ORNL & Sandia Re 870914-16 Visit to Westinghouse Waltz Mill Facility Re Equipment Calibr for Equipment Used During Reactor Vessel Insp During Current Outage ML20235D8221987-09-22022 September 1987 Informs of Limited Reorganization in Region I.Operator Licensing Responsibility Reassigned from Div of Reactor Projects to Div of Reactor Safety,Operations Branch, Effective 870831.Gallo Appointed Chief of Operations Branch ML20235E5761987-09-22022 September 1987 Informs of Limited Reorganization in Region I.Effective 870831,operator Licensing Responsibility Reassigned from Div of Reactor Projects to Operations Branch,Div of Reactor Safety.Rm Gallo Appointed Chief,Operations Branch ML20238D9541987-09-0808 September 1987 Forwards Safety Sys Outage Mod Insp Rept 50-286/87-13 on 870422-0714.Weaknesses Noted in Areas of Design & Design Verification Process Associated W/Replacement of Svc Water Pumps.Action Mgt Should Take Listed ML20238A8771987-08-31031 August 1987 Recommends That Site Specific Info Sheets & Appropriate Training Re Use Be Developed & Provided to Emergency Notification Sys & Health Physics Network Communicators to Facilitate Responses to NRC Requests for Data.Samples Encl ML20237H5441987-08-12012 August 1987 Forwards Results of Nonradiological Chemistry Stds Insp Activities for All Region I Licensees During 1985-1986. Results of Measurements Made by BNL Also Included ML20236L3531987-07-31031 July 1987 Informs of Plans for Combined Dcrdr/Spds Audit at Facility on 870914-17.Requests Approval to Use Camera to Take Pictures in Control Room.Response to Encl Questions on Status of SPDS Requested by 870821.Tentative Agenda Encl ML20215E0111987-06-12012 June 1987 Forwards Safety Insp Rept 50-247/87-14 on 870512.No Violation Observed.Concerns Re Previously Identified Weakness Involving Ability to Promptly & Accurately Classify Accident Conditions Expressed ML20214S6811987-06-0404 June 1987 Forwards NRC Form-398, Personal Qualifications Statement- Licensee, for Operator Training Applicants & re-applicants to Complete,Per 870526 Rev to 10CFR55.Graduates of INPO & Approved Simulation Facility Do Not Have to Complete Form ML20214S5531987-06-0404 June 1987 Forwards Revised NRC Form 398, Personal Qualifications Statement - Licensee. Rev Reflects Changes to 10CFR55 Effective 870526.All Applications for Licenses to Be Submitted on Revised Form as of 870526 ML20214R9331987-05-28028 May 1987 Advises That Info Contained in Rev 8 & Subsequent Amended Rev 8 to Physical Security Plan,Rev 4 to Safeguards Contingency Plan & Rev 6 to Security Force Training & Qualification Plan Consistent w/10CFR50.54(p) & Acceptable ML20214G1061987-05-15015 May 1987 Forwards Safeguards Insp Rept 50-286/87-09 on 870402 & 03. No Violations Noted ML20214H9341987-05-15015 May 1987 Forwards Safety Insp Rept 50-286/87-11 on 870420-24. No Violations Noted ML20210A0921987-04-20020 April 1987 Forwards Exam Rept 50-286/87-03OL of Exam Administered During Wk of 870223 ML20207T2081987-03-18018 March 1987 Forwards Insp Rept 50-286/87-02 on 870127-29.No Violation or Deviation Noted ML20204F2371987-03-18018 March 1987 Forwards Insp Rept 50-247/87-04 on 870203-0302.No Violation Noted ML20207S5491987-03-11011 March 1987 Forwards Insp Rept 50-286/87-01 on 870105-0217 ML20207S3281987-03-11011 March 1987 Forwards Safety Insp Rept 50-247/87-02 on 870127-29 & Notice of Violation ML20212J3641987-03-0202 March 1987 Forwards Insp Rept 50-247/87-01 on 870106-0202 & Notice of Violation ML20211E7141987-02-12012 February 1987 Ack Receipt of Providing Info Requested at 861114 Meeting.Info Sufficient to Clarify Difference Between Unit 3 Main Control Room & Unit 2 Simulator ML20210V5661987-02-10010 February 1987 Forwards Safety Insp Rept 50-286/86-24 on 861215-19 & Notice of Violation IR 05000247/19860191987-02-10010 February 1987 Ack Receipt of 861024 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-247/86-19. Discussion During 861119 Site Visit Helpful in Evaluating Full Scope of Corrective Actions ML20210U8991987-02-0909 February 1987 Requests Confirmation of 870203 Telcon Re Alleged Use of Controlled Substance at Facility.Review of Matter,Including Determining Validity or Probability of Occurrence & Determining Whether Any Safety Issues Involved Required ML20210S8731987-02-0505 February 1987 Summarizes 870127 Meeting at Region I Ofc Re Planned Mods of Plant Simulator.No Licensing Recommendations Made for Approval.No NRC Approvals or Actions Taken ML20209B5101987-01-28028 January 1987 Discusses Review of 861212 State of Ny Disaster Preparedness Commission Submittal to FEMA Region II Re Evaluating Offsite Emergency Plans & Preparedness.Issues Which May Cause Concern Listed in Encl ML20210B2351987-01-28028 January 1987 Forwards Insp Rept 50-247/86-33 on 871215-19.No Violations or Deviations Noted ML20209B5871987-01-23023 January 1987 Forwards Meeting Rept 50-247/86-136 on 861209 Re Plans for Integrated Assessment of Auxiliary Feedwater Sys ML20213A2871987-01-22022 January 1987 Forwards Insp Rept 50-286/86-23 on 861118-870105 & Notice of Violation ML20212K8951987-01-21021 January 1987 Lists Guidelines to Be Used for Submittal & Review of Objectives & Scenario Packages Prior to Scheduled 870513 Emergency Exercise.Importance of Completeness & Timeliness Stressed ML20212K3191987-01-20020 January 1987 Discusses Insp on 860811-0922 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty.Violation Noted: Reactor Heated Up Above Cold Shutdown Condition When Both Recirculation & Containment Spray Pumps Inoperable IR 05000247/19860111987-01-15015 January 1987 Forwards Meeting Insp Rept 50-247/86-11 on 861125.Major Area Discussed:Potential Enforcement/Unresolved Items & Open Items Identified in Environ Qualification Insp Rept 50-247/86-11 ML20207P9581987-01-14014 January 1987 Forwards Insp Rept 50-247/86-32 on 861122-870105.No Violations Noted 1990-08-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20211N0681999-09-0202 September 1999 Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager ML20209B6611999-06-29029 June 1999 Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls ML20207D1861999-05-27027 May 1999 Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl ML20204J9971999-03-0909 March 1999 Forwards Insp Rept 50-003/98-19 on 981130-990222.No Violations Noted ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J6171999-02-0505 February 1999 Forwards Transcript from 990120 Public Meeting Held in Peekskill,Ny Re Decommissioning ML20198E9561998-12-21021 December 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities Re Deliberate Misconduct in Violation of Regulation When False Info Was Provided to Two NRC Licensees ML20198C2371998-12-15015 December 1998 Ltr Contract:Task Order 237, Review & Evaluation of Indian Point 3 Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026 ML20198C3251998-12-11011 December 1998 Responds to ,Responding to NRC Ltr Re Concerns Raised About Potential Chilling Effect from Temp Denial of Site Access to Employee Raising Safety Issues to Util Senior Mgt ML20155H2901998-11-0303 November 1998 Responds to to Lj Callan Expressing Concern About Continued Operation of Indian Point Nuclear Generating Station.Explanation Why NRC Do Not Think Revoking OLs for Indian Point Units 2 & 3 Justified,Provided ML20154Q1761998-10-21021 October 1998 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Withheld in Part (Ref FOIA Exemption 7) ML20154L8031998-10-16016 October 1998 Ack Receipt of & Payment in Amount of $55,000 in Electronic Funds for Civil Penalty Proposed by NRC in .Corrective Actions Will Be Examined During Future Insp ML20151W9511998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs Duties for Region I ML20151W4871998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned as SRAs for Region I ML20238F5151998-08-26026 August 1998 First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Entirety. Documents Listed in App B Being Withheld in Part (Ref FOIA Exemption 6) ML20155F4391998-08-26026 August 1998 Forwards Demand for Info,Being Issued to Enable NRC to Fully Understand Recipient Views on Facts & Circumstances Surrounding Allegedly False Info Provided to Two NRC-licensed Activities IR 05000286/19980051998-08-19019 August 1998 Discusses Insp Rept 50-286/98-05 on 980528-0612 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Most Significant Violation Involved Failure, Following Design Mod in Oct 1997 ML20236V4211998-07-13013 July 1998 Forwards SER Approving Topical Repts WCAP-14333P & WCAP-14334NP (Proprietary & non-propiretary, PRA of RPS & ESFAS Test Times & Completion Times IR 05000247/19970131998-07-0606 July 1998 Discusses Insp Repts 50-247/97-13,50-247/97-15 & 50-247/98-02 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20248F2891998-05-26026 May 1998 Ltr Contract:Task Order 8, Indian Point 2,A/E Follow-up Insp, Under Contract NRC-03-98-021 ML20247M6951998-05-20020 May 1998 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, for Plant,Unit 2 ML20247L1511998-05-15015 May 1998 Informs That Author Writing to Confirm Westinghouse Onwers Group Participation in Forthcoming 980612 Briefing to Commissioners of NRC in Rockville,Md & to Provide Background & Guidance for Briefing ML20203K5921998-02-26026 February 1998 Ack Receipt of Transmitting Changes to Physical Security Plan for Plant.Approval by NRC Is Not Required IAW 50.54(p) ML20199E0291997-11-19019 November 1997 Ack Receipt of & Wire Transfer for $110,000 in Payment for Civil Penalties Proposed by NRC in . Corrective Actions Will Be Examined During Future Insp IR 05000247/19970081997-10-0707 October 1997 Discusses Insp Rept 50-247/97-08 on 970616 & 0721 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 ML20217C0931997-09-30030 September 1997 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in .C/As Will Be Examined During Future Insps ML20211D3561997-09-23023 September 1997 First Partial Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App A.Addl Records Being Reviewed & Notification Will Be Provided Upon Completion IR 05000286/19970801997-08-19019 August 1997 Discusses Insp Rept 50-286/97-80 on 970407-0501 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000 ML20149K9711997-07-29029 July 1997 Ack Receipt of & Payment of $205,000 for Civil Penalty Proposed by NRC in .Violation Retracted Due to Licensee Disagreement ML20211D4191997-06-19019 June 1997 Discusses 930227 Shutdown of Plant,Unit 3.NRC Concluded That Sufficient Progress Has Been Made to Support Safe Plant Restart & Power operations.CAL-1-93-09 Issued on 930617, Which Documented Util Restart Commitments ML20140G3831997-06-0909 June 1997 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 970519-21 at Facility.Completed ES-501-2 Results Summary & Individual Results ES-303-1 & 303-2 Encl. W/O Encl ML20138C7461997-04-23023 April 1997 Forwards Amend 191 to License DPR-26 & Safety Evaluation. Amend Revises TS Sections 3.3 & 4.5 to Allow Deletion of Requirement to Utilize Sodium Hydroxide as Additive in Post Accident Containment Spray Sys ML20134N6141997-02-19019 February 1997 Responds to Re Proposed Corporate Reorganization of Consolidated Edison for Indian Point Units 1 & 2. Ltr Deemed Application for Consent Under 10CFR50.80 & Referred to NRC Staff for Consideration ML20134M8901997-02-19019 February 1997 Eighth Partial Response to FOIA Request for Documents. Records in App O Encl & Already Available in Pdr.App P Records Being Made Available in PDR ML20134H6271997-02-10010 February 1997 Fifth Partial Response to FOIA Request for Documents.Records in App I Encl & Available in Pdr.App J Records Withheld in Part (Ref FOIA Exemption 5) & App K Records Completely Withheld (Ref FOIA Exemption 5) ML20134N6451997-01-0909 January 1997 Responds to to Jm Taylor Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny for Indian Point Units 1 & 2.Ltr of 961224 Deemed Application for Consent Under 10CFR50.80 & Referred for Consideration ML20133F7541997-01-0808 January 1997 Final Response to FOIA Request for Documents.Records in App a Encl & Available in Pdr.App B Records Being Withheld in Part (Ref FOIA Exemption 6) ML20128P2631996-10-11011 October 1996 Ltr Contract:Task Order 105, Indian Point 2 Ipap, Under Contract NRC-03-93-036 ML20129G6121996-09-24024 September 1996 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App C,E,F & G.Documents Available in Pdr.App E,F & G Documents Partially Withheld Ref FOIA Exemptions 4 & 6.App D Record Listed as Copyright ML20134B7681996-06-10010 June 1996 Forwards Director'S Decision 96-06 Denying 960518 Requests Re Immediate Suspension of Operating Licenses for Indian Point Nuclear Generating Units 2 & 3 ML20211D9231995-11-0707 November 1995 Responds to 951020 Postcard,Requesting Transcript of 951018 Public Meeting in Buchanan,Ny.Meeting Was Not Transcribed. Copy of Presentation by NYPA at Meeting Encl ML20133F7781995-07-11011 July 1995 Ack Receipt of Re Restart of Plant NPP in Westchester County in New York ML20211F0161995-01-12012 January 1995 Forwards Copy of Rev & Status Update 3 of Plant,Unit 3 Restart Action Plan ML20134P2921994-12-22022 December 1994 Responds to Questions Presented in to G Gordon Re New York Regulatory Jurisdiction at Plant,Unit 1 ML20058E1321993-11-23023 November 1993 Forwards Insp Rept 50-247/93-26 on 931108-12.No Violations Noted ML20059M8261993-11-16016 November 1993 Discusses Proposed Rule for Protection Against Malevolent Use of Vehicles at Facility.Safeguards Info Encl.W/O Encl ML20059M8561993-11-16016 November 1993 Forwards Safeguards Info Ref in Preliminary Draft Guide Which Provides Proposed Characteristics of Design Basis Vehicle.W/O Encl ML20059K7361993-11-0505 November 1993 Forwards Util 931015 Response to NRC Request for Info Re Employee Safety Concerns at Unit 3 1999-09-02
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E f 631 PAR K AVENUE I KING OF PRUSSI A, PENNSYLVANI A 19406 November 6, 1978 Docket No. 50-286 Power Authority of the State of New York Indian Point 3 Nuclear Power Plant ATTN: Mr. J. P. Bayne '
Resident Manager !
P. O. Box 215 Buchanan, New York 10511 Gentlemen:
The enclosed IE Circular No. 78-18 is forwarded to you for informa-tion. No specific action is requested and no written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosures:
- 1. IE Circular No. 78-18
- 2. List of IE Circulars Issued in 1978 .
cc w/encls:
George T. Berry, General Manager and Chief Engineer .
L. R. Bennett, Assistant General Manager - General Counsel l G. M. Wilverding, Licensing Supervisor P. W. Lyon, Manager - Nuclear Operations A. Klausmann, Director, Quality Assurance D. Halama, Site Quality Assurance Engineer J. F. Davis, Chairman, Safety Review Committee J. M. Makepeace, Director, Technical Engineering (Con Ed) 7812 3 00 /5f
l UNfTED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT ,
WASHINGTON, D. C. 20555 {
IE Circular 78-18 Date: November 6, 1978 Page 1 of 3 UL FIRE TEST
Background
On September 15, 1978, a fire test of a full-scale vertical cable tray array was conducted at the Underwriters Laboratory (UL) near Chicago, Illinois. It was part of the fire protection research program managed by Sandia Laboratories under NRC contract. The purpose of the test was to demonstrate the effectiveness of area sprinklers and cable tray fire barriers constructed of ceramic fiber blankets in preventing damage to cables as a result of an exposure to a flammable liquid fire. The test j resulted in damage to some electrical cables.
l Discussion The configuration of the fire test was selected to simulate a section of a plant area with vertical cable trays containing redundant safety divisions arranged such that the redundant divisions could be simul-taneously exposed to a potential fire resulting from an inadvertent spill of flammable liquid in the area. The arrangement of the cable trays and the designation of the redundant tray divisions is shown in Figure 1. Figure 2 shows the location of the fire detectors and the three groups of sprinklers. Each of the five cable trays contained
,~ cable insulated with polyvinyl chloride and was enclosed in a separated ceramic fiber blanket fire barrier from floor to ceiling in accordance with the manufacturer's recommendations. The sprinkler and detector arrangement was as permitted by NFPA Code. However, no water was actually used at any time during this test due to the failure of some sprinkler heads to actuate, as explained below.
Each sprinkler location in the test arrangement contained three nominally identical temperature sensing sprinkler heads with fusible links adjacent to an open sprinkler head which was connected to a manual water supply valve. The temperature sensing heads were wired to signal when their links fused. After all three temperature sensing heads at a given loca-tion activated, then the water supply for the open head was to be manually admitted. The sprinklers were of a type which actuate at the slow end of acceptance for reaction time. The test procedure required that all three temperature sensing heads had to activate before water would be turned on. In this way, it was expected to get some data on variability in the response time of identical sprinklers.
l l
IE Circular 78-18 Date: November 6, 1978 Page 2 of 3
, Test Details The test was started by igniting the two gallons of heptane that was poured into the floor pan. A fully developed fire occurred almost immediately. The ceiling smoke detector alarmed in about 15 seconds. In about 50-60 seconds, two of the three temperature sensing sprinklers located between the wall and cable trays 1 and 2 activated. The fire between cable trays 1, 2, 3, and 4 appeared most intense, apparently because of a chimney effect between the four trays. The flames between cable trays 3 and 5 did not appear to be so intense. The ceramic fiber blanket absorbed some of the heptane so that after the heptane in the pan burned, most of the flame seemed to come from the bottom outside surface of the ceramic fiber blanket. No additional temperature sensing sprinkler heads at any location activated; thus, the sprinkler water supply was not turned on for any of the three sprinkler locations. The apparent slow response of the third temperature sensing sprinkler is being investigated, since this was not intended to be a slow response sprinkler.
At about 3 minutes into the test there was an indication of a short circuit in cable tray 3, which was probably caused by the fire. After 5-7 minutes the height of the ilames appeared to subside; however, residual flames continued for about 40 minutes.
Preliminary Results and Analyses Preliminary information indicates that the flammable liquid or flames penetrated the protective barriers at the bottom of the vertical trays and caused fire damage to the polyvinyl chloride insulation on cables in four of the five trays.
On subsequent 500-volt megger tests, it was found that another cable in tray 2 had also experienced some damage, as evidenced by a conductor to ground short.
The most probable cause of the fire damage in certain cable trays appears to be related to the absorption or seepage of heptane under the ceramic fiber blanket at the juncture with the floor. Once the heptane entered the interior regions of the cable tray, then ignition apparently occurred via the small opening at the floor or through a vapor / air path within the joints. There is some indication that some cable damage was caused by absorption of heptane on the inside of the barrier (wicking effect) and its ignition which heated a cable tray ladder rung, causing damage to a cable in contact with the rung. The ingress of the heptane into the ceramic fiber needs to be further evaluated since this appears to be the most significant failure mode.
IE Circular 78-18 Date: November 6, 1978 Page 3 of 3 Tentative Conclusions The test results are still being analyzed, and it would be premature to establish firm conclusions at this time; however, the results now available indicate that the following areas of the fire protection program need close consideration:
- 1. To protect against spills of flammable liquids, barriers or curbs may be needed to prevent entry of the flammeble liquid behind fire barriers. A wick effect may also need to be considered in the design of fire barriers.
- 2. Some small fires may not actuate sprinkler heads. To reduce this possibility in sprinkler systems to be installed, fast response sprinkler heads should be considered (less than approximately 3 minutes in the UL Standard 199 " Automatic Sprinklers for Fire ProtectionService").
- 3. The location of the fire detection devices and the sprinkler heads relative to the fire and components being protected is of great importance. The path of the air movement in the area influences the actuation of such devices and should be considered in the system layout.
The final results of this test will be issued when the analysis of the test is complete.
This Circular is being issued for information only. No specific action is requested and no written response is required. If you desire addi-tional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
Attachments:
- 1. Figure 1
- 2. Figure 2 1
i
IE Circular No. 78-18 Date: November 6, 1978 Page 1 of 2 ENCLOSURE 2 LIST OF IE CIRCULARS ISSUED IN 1978 Circular Subject First Date Issued To No. of Issue 78-01 Loss of Well Logging 4/14/78 All Holders of Source Well Logging Source Licenses 78-02 Proper Lubricating 011 4/20/78 All Power Reactor for Terry Turbines Facilities with an Operating License (OL)orConstruction Permit (CP) 78-03 Packaging Greater Than 5/12/78 All Power Reactor Type A Quantities of Facilities with an Low Specific Activity OL or CP; and all Radioactive Material Fuel Cycle, Priority I for Transport Materials and Waste Disposal Licensees 78-04 Installation Errors That 5/18/78 All Power Reactor Could Prevent Closing Facilities with an of Fire Doors OL or CP 75-05 Inadvertent Safety 5/26/78 All PWR Power Injection During Reactor Facilities Cooldown with an OL or CP 78-06 Potential Common Mode 5/31/78 All Power Reactor Flooding of ECCS Facilities with an Equipment Rooms at OL or CP BWR Facilities 78-07 Damaged Components on a 5/31/78 All Power Reactor Bergen-Paterson Series Facilities with an 25000 Hydraulic Test Stand OL or CP 78-08 Environmental Qualifica- 5/31/78 Ali Power Reactor tion of Safety-Related Facilities with an Electrical Equipment at OL or CP Nuclear Power Plants
IE Circular No. 78-18 Date: November 6, 1978 Page 2 of 2 ENCLOSURE 2 (Continued)
LIST OF IE CIRCULARS ISSUED IN 1978 Circular Subject First Date Issued To No. of Issue 78-09 Arcing of General Electric 6/8/78 All Power Reactor Company NEMA Size 2 Facilities with an Contactors OL or CP 78-10 Control of Sealed Sources 6/14/78 All Institutional Used in Radiation Therapy Medical Licensees 78-11 Recirulation M-G Set 6/15/78 All BWR Power Reactor Overspeed Stops Facilities with an OL or CP 78-12 HPCI Turbine Control 6/30/78 All Power Reactor Valve Lift Rod Facilities with an Bending OL or CP having a HPCI Terry Turbine 78-13 Inoperability of 7/10/78 All Power Reactor Multiple Service Facilities with an Water Pumps OL or CP 78-14 HPCI Turbine Re- 7/17/78 All Power Reactor versing Chamber Facilities with an Hold Down Bolting OL or CP having a HPCI Terry Turbine excepting Duane Arnold and Monticello 78-15 Tilting Disk Check 7/24/78 All Power Reactor Valves Fail to Close Facilities with an with Gravity in Vertical OL or CP Position 78-16 Limitorque Valve 7/26/78 All Power Reactor Actuators Facilities with an OL or CP 78-17 Inadequate Guard 10/13/78 All Power Reactor Training / Qualification Facilities with an and Falsified Training OL; Susquehanna 1 & 2, Records Shoreham, and Salem 2