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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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I FEB 101987 Docket No: 50-247
. Consolidated Edison Company of
'New York, Inc.
ATTN: Mr. Murray Selman ,
Vice President, Nuclear Power Indian Point Station Broadway and Bleakley Avenue Buchanan, New York 10511
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Gentlemen:
Subject: Inspection 50-247/86-19 This refers to your letters dated October 24, 1986, and January 2,1987, in response to our letter dated July 24, 1986.
Thank you for informing us of the corrective and preventive actions documented in your letters. The discussions between Mr. J. Johnson of the NRC and Mr. M.
Lee and others of your staff during a site visit on November 19, 1986, (Inspection No. 50-247/86-31) were helpful to us in evaluating the full scope of your corrective actions. Your supplemental response dated January 2,1987, documents this additional information. These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely, p Stewart D. Ebnet , Director i Division of Reactor Safety Enclosures: Licensee letters October 24, 1986, & January 2, 1987.
cc w/ encl:
Robert Spring, Manager, Regulatory Affairs P. Kokolakis, Director, Nuclear Licensing i Brent L. Brandenburg, Assistant General Counsel nj Walter Stein, Secretary - NFSC
/U Public Document Room (PDR) 1 Local Public Document Room (LPDR) \ dg Nuclear Safety Information Center (NSIC) \
NRC Resident Inspector State of New York FICIAL RECORD COPY RL IP2 86-19 - 0001.0.0
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RI:DRS RI:DRS Johnson Bettenhausen 1/d/87 Mb/87 0FFICIAL RECORD COPY RL IP2 86-19 - 0002.0.0 01/27/87 -
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. Consohdated Edison Company of New York, Inc.
' Indian Point Station
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Broadway & B6eakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116 October 24, 1986.
Ret Indian Point Unit No. 2 Docket No. 50-247
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Mr. Stewart D. Ebneter, Director Division of Reactor Safety
- U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 j
Dear Mr. Ebneter:
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This refers to the special operational safety inspection conducted by a
! team of NRC personnel led by Mr. Jon Johnson of your office on July 21, 1986 through Augu st 1, 1986, at the Indian Point Nuclear Generating 4 '
Station Unit No. 2.
j Your September 24, 1986 letter, which transmitted Inspection Report No.
50-247/86-19, stated that it appeared that certain of our activities were i
not conducted in full compliance with NRC requirements, as set forth in
' the Notice of Violation, enclosed therewith as Appendix A. Pursuant to i the provisions of 10 CFR 2 201, our response to that Notice is presented
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in Attachment A to this letter.
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In addition, your letter reaue sted that we re spond to certain concerns
- related to our attention to detail. We have recognized the need for attention to detail at Indian Point and have ongoing activities in place
.I that address your concerns in this area.
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. We have recently initiated a systems engineer approach aimed at enhancing operational and system detail awa reness. We a re addressing plant trips
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! and equipment malfunctions by performing root cause analysis and equipment failure and reliability analysis with the goal of enhancing the effectiveness of our maintenance activities. In addition, housekeeping ha s been stepped-up in an effort to facilitate modifications and maintenance. In order to assure followup to required actions and details
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that reau' > action, we a re tracking more closely those open items that are generated by the ongoing licensing and regulatory process, as well as those generated by in-house activities.- In our operational and system a sse ssment s, inconsistencies that are found are either promptly corrected
' We or scheduled for correction, depending on their level of importance.
l a re awa re that supporting sof tware such as drawings, procedures and the c f l -,
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, simulator need to accurately reflect "as-built" plant conditions, and are routinely assessing our existing programs in these important areas to see where the revision process can be streamlined to facilitate changes. To better implement plant configuration control activities, training of our staff is being conducted in selected areas, such as the NRC unresolved safety issues program, backfitting controls, plant failure analysis and root cause determination, team building as well as operator qualificaton and recualifications. These actions, to mention a few, are geared towards enhancing the level of attention to detail.
We are integrating the above-mentioned activities into our routine daily ope ration s. We are confident that since we have recognized the need for increased attention to detail, over time we will routinely be focu sing our attention and appropriately more sensitive to details.
Should you or your staff have any questions, please contact us.
Very truly yours, D W Attachments cca Senior Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 38 Buchanan, New York 10511
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, October 24, 1986 Re Indian Point Unit No. 2 Docket No. 50-247 ATTACHMENT A Response to Notice of Violation 1. Violation At Technical Specification 6.8.1 reouires that procedures be established and maintained to combat emergencies and other significant events such as loss of coolant and loss of electrical power (and/or degraded power sou rce s) .
Contrary to the above, on July 31, 1986, certain procedures combating a loss of coolant emergency and another significant event such as a degraded power source were not properly established or maintained in that:
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Emergency Operating Procedure (EOP) ES 1.3, Transfer to Cold Leg Recirculation, does not provide for opening valve MOV-744, RHR Pumps Discharge Valve, which is reouired to be open in order to establish alternate recirculation flow.
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EOP E-1, Loss of Reactor or Secondary Coolant, in the procedural step for resetting containment isolation phases A and B, fails to reouire ope ra tion of personnel and eauipment hatch solenoid switches located on Control Room panel SM which must be operated in order to reset containment isolation pha se A. This deficiency is also applicable to several other EOPs.
-- EOPs, E-0, Reactor Trip or Safety Injection, and ECA-0 2, Loss of All AC Power Recovery with SI Recui red, align the boron injection tank (BIT) to the auction of the sa fety in jection pumps although the BIT has been removed from service by electrical modifications and retired from u se as a sa fety injection component.
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An abnormal operating procedure had not been established for a degraded or loss of the 138KV off aite power feeder sources.
This is a Severity Level IV Violation (Supplement I).
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Octobe r 24, 1986 Ret Indian Point Unit No. 2 Docket No. 50-247 Reaponse A The Emergency Operating Procedu res (EOPa) referenced in this violation have been revised. . In addition, other EOP discrepancies addressed during the inspection, although not part of the violation, have also been corrected.
The concerns raised by the inspection team with regard to the procedures referenced in the violation have been promptly acted upon. Howeve r, we believe the discrepancies noted are mitigated for the following reasons:
In the case of MOV 744 (RHR Pumps Discharge Valve) and the phase A reset ouestions, the procedure s contain contingency actions which address the conditions created by the procedure discrepancie s.
Therefore, the operator would not he rendered incapable of completing the procedures in question.
In the case of the retirement of the Boron Injection Tank (BIT), the need to change the EOPs to reflect BIT retirement was recognized by plant staff and was in fact underway at the time of the inspection.
In addition, Operations personnel were fully aware of the retirement of the BIT and actions had been taken to effectively isolate the BIT and deenergise the associated motor operated valves.
A procedu re addre ssing the loss of 138 KV offsite power will be issued by Decembe r 15, 1986. Technical Specification 6 8.1 references Regulatory Guide 1 33 and ANSI 18.7. In the case of R.G.
1.33, Appendix A state s "The following are typical activities that should be covered by written procedures". In the case of ANSI N18 7-1976, Section 5.3 9.2 etates "The following categories of events may, depending upon the design of the plant, be conaldered as examples of gotential eme rgencie s for which procedures are written
..." "I,oss or degradation of vital power sources" is one of the examples. Therefore, we believe that the lack - of such a procedure is not in noncompliance with Technical specification 6 8.1.
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. Octobe r 24, 1986 Re: Indian Point Unit No. 2 Docket No. 50-247 2. Violation B:
10 CFR 50, Appendix B, criterion V requires that activities affecting quality to be prescribed by and accomplished in accordance with documented instructions, procedures, or drowings.
Contrary to the above, on July 23, 1986 the as-found configuration of the recirculation sump grating and floor plate was not in accordance .
with the Indian Point Unit 2 Final Safety Analysis Beport, ' Section 6.2, and the Containment Building General Arrangement Drawing No.
9321-F-2503, Rev. 15. This sump, in the as-found configuration, may not have been able . to pe rform one of its safety functions of preventing large size objects from entering the sump and blocking the suction path for the recirculation mode of core cooling.
Fu rthe r, several other examples of as-found : plant conditions which did not match design configurations were identified and are noted in Section 9.1 of this report.
This is a Severity Level IV Violation (Supplement I).
Response B:
At the time of discovery, operability of the recirculation pumps was deemed unaffected by the se conditions. Nonethele ss, as a conservative measure, a decision was subsequently made to repair the floor grating and correct the gap in the floor plating. The se -
efforts were completed on July 25, 1986.
A written anfety assessment, based on a previous Bechtel study, was provided to the inspection team on July 31, 1986. That a sse ssment concluded that the floor gaps discovered on July . 23, 1986 did not impact recirculation pump operability.
An additional independent analytical a ssessment by Bechtel wa s subsequently performed and that assessment concluded that the recirculation sump in the "as-found" condition would not have created adverse effects on the recirculation system.
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, Octobe r 24, 1986 Re: Indian Point Unit No. 2 Docket No. 50-247 3. Violation C:
10 CFR 50, Appendix B, Criterion V requires that activities affecting quality be prescribed by and accomplished in accordance with documented instructions or procedures. Station Administrative Order No. 218 require s that all work a rea s be cleaned, all recoverable items (i.e., tools, ..., ra gs, cleaning fluid, ...) be removed and properly dispositioned at the completion of work shift as practical, and that gas cylinders be marked as to type, capped and secured if left unattended.
Contra ry to the above, several examples of inadeouate restoration or securing of eculpment were found
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On July 29, 1986, twelve Nitrogen bottles for Steam Generator Blowdown and two unmarked gas bottles were observed unsecured.
On July 31, 1986, two Hydrogen bottles near the Volume Control Tank Hydrogen cover gas supply area were observed unsecured.
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On July 29, 1986, pla stic bags, ra gs, tools and debris we re observed inside the Fuel Handling Building and out side of the Fan House.
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On July 21, 1986 and on July 28, 1986, oil spills were observed on the floors of the cable spreading room and the eme rgency diesel generator room.
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On July 23, 1986, two large plastic bags and a cuantity of soft plastic tubing were left on the floor of the containment in the vicinity of the recirculation sump.
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A two-ton gantry c ra ne and in strument table s with wheels we re observed in the cable spreading room un secu red; and four instrument tables with wheels were also found unsecured in the 480 V switchgear room.
This is a Severity Level IV Violation (Supplement I).
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Octobe r 24, 1986 Ret Indian Point Unit No. 2 Docket No. 50-247 Response C:
Housekeeping has always been and will continue to be an Jmportant priority with station pe rsonnel . Notwithstanding the particula r conditions cited in this violation, the general appearance of the station has markedly improved. The inspectors noted in the in spection report that hou sekeeping conditions and plant cleanliness were gene rally satisfactory. The report stated, in pe rtinent pa rt, that "..the inspectors concluded that, de spite recent improvements in housekeeping conditions and plant cleanliness, additional attention in implementing the provision s of Station Administra tive Orde r No. 218, Rev. O,
' Housekeeping Policy' was wa rranted."
Station Administrative Order No. 218 is being revised to give more detailed and improved control of a rea s of re sponsibility by redistribution of a rea s within normal work discipline s. Area s of responsibility for housekeeping are being redefined so as to involve all four General Managers and the Resident Const ruction Manager. In addition, a booklet on hou sekeeping, explaining Indian Point's housekeeping philosophy, will be distributed to Station personnel.
Hou sekeeping will be empha sized as part of Indian Point's Genera l Employee Training (GET).
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Ret Indian Point Unit No.
Docket No. 50-247 ATTACHMENT B Response to Inspector Concerns 1. Labeling Con Edison is currently. in the process of upgrading the identification of plant equipment. The valve labeling portion of the upgrade is planned to be completed by August 30, 1987. Following completion of the valve labeling portion, Con Edison will continue with system component labeling. Central Control Room labeling adjustments, if reauired, will be done as pa rt of Con Edison's Detailed Control Room Design Review (DCRDR) implementation process.
2. Procedures As stated in our response to violation A, the EOPs referenced in that violation and other EOP discrepancies addressed during the inspection have been corrected. In addition, as a result of discussions with the in spection team, certain other procedures have been or will be revised to incorporate in spector sugge stions. We feel that these suggestions are positive contributions to the cuality of our procedures. Review of procedures by . support personnel and comments f rom operators as a result of procedure usage facilitate a continuing upgrade of plant procedures.
3. Containment Clomeout To ensure that containment closeout activities are performed in an acceptable manner, a containment closecut check-off list will be developed by January 30, 1987. This check-off list should ensure that the containment is left in an acceptable condition with respect to " housekeeping".
4. Gaa Turbine No. 2 Following the unsuccessful black-start attempt during the inspection, a Westinghou se ga s turbine engineer wa s contracted to review the condition of Ga s Turbine No. 2. A thorough inspection was performed. As a result of the inspection, the component which resulted in the computer fault was identified. This component is on orde r. A black-start te st will be performed after the component is replaced.
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5. Plant Configuration Management As stated in the our cover letter, the establishment of a systems engineer program will enhance operational and system detail awareness.
This program requires the system engineer to develop an intimate level of knowledge, understanding and awareness of the operation and design of a ssigned plant systems. This would provide' the system engineer with the nece ssa ry skills and involvement to a ssist in maintaining a high level of system performance. The system engineer will also provide a channel, where reliable and detailed information is readily accessible to a ssist support groups in perf62 ming their functions. The system engineer will enhance the communication and coordination of efforts between support groups within the station organization.
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Individuals designated as system engineers may perform the following functions, for example:
1. Ve rify accu racy of drawings 'and initiate a drawing change if nece ssa ry.
2. Recommend procedure revisions to the Generation Support Manager, , -
Maintenance Manager or I&C Engineer, as appropriate. -
3. Identify and evaluate potentialities for the enhancement of system and equipment performance.
4. Assist in the inve stigation of opera tional events in order to determine the cause of the event or to a ssu re that the system functioned properly during the event. -
5. Identify and recommend to the Training Department any changes to the system design or operating procedures which may affect, the required training of plant personnel. J
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>. s, Murray Selman v(e Presusent Consotidated Edison Company of New York, Inc.
Indian Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 -
Telephone (914) 737 6116 January 2, 1987 Mr. Stewart D. Ebneter, Director Division of Reactor Safety U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pa. 19406 Ret Consolidated Edison Company of New York, Inc.
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Indian Point Unit No. 2 Docket No. 50-247 ,
Dear Mr. Ebneter:
This refers to the special operational safety inspection conducted by a team of NRC personnel led by Mr. Jon Johnson of your office on July 21, 1986 through August 1, 1986, at the Indian Point Nuclear Generating Station Unit No. 2, and the subsequent conversations between Mr. Johnson and Con Edison staff on November 19, 1986. Attachment A to this letter transmits additional information that Mr. Johnson requested.
If you or your staff have any questions, please contact us.
Very truly yours, M^ . n,,_ _
attachment cca Mr. Jon Johnson Division of Reactor Safety U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pa. 19406 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, NY 10511 nr}\%< ...
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January 2, 1987 Ret Indian Point Unit No. 2 Docket No. 50-247-ATTACHMENT A 1. In our response to violation A, we stated that we believed that the e lack of a procedure on the loss of 138 KV offsite power was not in noncompliance with Technical Specification 6.8.1. Based on further
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review we concur with you that if no procedure existed on the loss of 138 KV offsite power that would . be in noncompliance with Technical Specification 6.8.1.
We stated that such a procedure, addressing the loss of 138 KV offsite power, would be issued by December 15, 1986. Procedure A27.1.1 Rev.
O, titled " Loss of 138KV" was issued with an effective date of December 12, 1986.
As stated in our earlier response to Violation A, the concerns raised by the inspection team with regard to the procedures referenced in Violation A have been promptly acted upon. Con Edison previously committed to submit to the NRC a revised EOP Procedures Generation Package by February 15, 1987. This revision better defines the EOP generation and maintenance process to facilitate changes on a more routine basis. In addition, Con Edison has purchased a computerized ECP maintenance program to better facilitate the processing of required changes to the EOPs. This will reduce the manual effort involved in maintaining many of the controlling documents. This program is scheduled to be implemented during the first half of 1987.
2. To ensure that containment closecut activities are performed in an acceptable manner, a containment closeout check-off list has been.
developed and is under final review. This check-off list will be issued by January 30, 1987. This check-off list till ensure that the
' containment is Icft in an acceptable condition. This check-off list requires, among other things, that the individual inspect .the recirculation sump grating and floor plate to assure that the as-left configuration is in accordance with the Indian Point Unit 2 Final Safety Analysis Report, Section 6.2, and the Containment Building General Arrangement Drawing No. 9321-F-2503, Rev. 15, 3. In our response to Violation C, we stated that Station-Administrative Order (SAO) No. 218, entitled " Housekeeping", is being revised to give more detailed and improved control of areas of responsibility by redistribution of areas within normal work disciplines. That SAO revision is in final review and will be issued this month. A !
housekeeping guide was published in November, 1986. This. guide has l been prepared to assist all Indian . Point personnel in maintaining Indian Point Unit 2 cleanliness standards at the highest levels. The i J
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January 2, 1987 Ret Indian Point Unit No. 2 Docket No. 50-247 guide has been issued to' maintenance personnel and subsequent distributions will be made to other personnel.
The station has been divided into separate cleanliness areas and personnel have been assigned responsibility for these areas. Signs have been posted in these areas with the name of the individual who has the responsibility to ensure that housekeeping standards are maintained. These areas are routinely inspected by management personnel. If any housekeeping deficiencies arise, that individual is contacted to correct the deficiency. Weekly housekeeping meetings are held with section representatives to discuss- the housekeeping condition of those areas assigned to them.
In addition, Maintenance supervisors inspect maintenance work areas to ensure that post-maintenance restoration of the area and or equipment is acceptable.
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