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| | number = ML20138S098 | | | number = ML20138S098 |
| | issue date = 11/06/1985 | | | issue date = 11/06/1985 |
| | title = Requests Review of Encl 851012 Ltr Re Comments & Recommendations Concerning Indian Point Special Proceeding & Commission Decision Cli 85-06 | | | title = Requests Review of Encl Re Comments & Recommendations Concerning Indian Point Special Proceeding & Commission Decision Cli 85-06 |
| | author name = Palladino N | | | author name = Palladino N |
| | author affiliation = NRC COMMISSION (OCM) | | | author affiliation = NRC COMMISSION (OCM) |
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| | contact person = | | | contact person = |
| | document report number = CLI-85-06, CLI-85-6, NUDOCS 8511190521 | | | document report number = CLI-85-06, CLI-85-6, NUDOCS 8511190521 |
| | | title reference date = 10-12-1985 |
| | document type = CORRESPONDENCE-LETTERS, INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE, NRC TO ACRS | | | document type = CORRESPONDENCE-LETTERS, INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE, NRC TO ACRS |
| | page count = 1 | | | page count = 1 |
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| ==Dear Mr. Ward:== | | ==Dear Mr. Ward:== |
|
| |
|
| By letter dated October 12, 1985, (copy enclosed), five members of the Advisory Committee provided comments and recommendations related to the Indian Point Special Proceeding and the Commission Decision (CLI 85-06). | | By {{letter dated|date=October 12, 1985|text=letter dated October 12, 1985}}, (copy enclosed), five members of the Advisory Committee provided comments and recommendations related to the Indian Point Special Proceeding and the Commission Decision (CLI 85-06). |
| Since "relatively broad considerations" are discussed in the letter, it would be beneficial to the Commission to have the views of the ACRS as a whole. Therefore, we request that you review the enclosed letter with the entire Advisory Committee and provide a report to the Commission. | | Since "relatively broad considerations" are discussed in the letter, it would be beneficial to the Commission to have the views of the ACRS as a whole. Therefore, we request that you review the enclosed letter with the entire Advisory Committee and provide a report to the Commission. |
| Sincerely, y . f fdw &" | | Sincerely, y . f fdw &" |
|
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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:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20196J9371998-12-0808 December 1998 Notification of 990120 Meeting with Util in Peekskill,Ny to Inform Public of Licensee Plans for Decommissioning Indian Point Nuclear Generating Station Unit 1 ML20236X5861998-08-0505 August 1998 Summary of 980620 Meeting W/Members of W,Util & NRC in Rockville,Md Re best-estimate Small Break LOCA Model Issues. Attendees List & Nonproprietary Matl Presented at Meeting Encl ML20217E7381997-10-0202 October 1997 Forwards Operator Licensing Exam Administered on 970317-20 W/Outline & Initial Exam Submittal Designated for Distribution Under Rids Code A070 IR 05000247/19970021997-10-0202 October 1997 Forwards NRC Operator Licensing Exam Rept 50-247/97-02 (Including Completed & Graded Tests) for Tests Administered on 970317-20 ML20236N0661997-05-0202 May 1997 Responds to from Consolidated Edison Requesting Interpretation of TS as to Definition of Operable as It Applies to Afs Under Certain Scenarios ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134N6211997-02-19019 February 1997 Forwards Response to SB Bram to EDO Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny Approved W/Edit by Chairman for Dispatch ML20134N6371997-01-14014 January 1997 Requests Concurrence Re Proposed Response to SB Bram to EDO Concerning Proposed Corporate Reorganization of Consolidated Edison Co of Ny by Close of Business on 970117 ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20211E9921995-11-0808 November 1995 Informs of Plan to Augment Plant,Unit 3 Resident Staff & Provide around-the-clock Insp Coverage During Plant Restart from Current Unplanned Outage.Primary Objectives of Insp Listed ML20211D9061995-08-14014 August 1995 Forwards Final Rev to Plant,Unit 3 Restart Action Plan Based Upon Completion of Insp Activities & Util Oversight ML20203B9821995-06-29029 June 1995 Discusses OI Repts 1-95-011,1-95-012 & 5-93-014 Re Fitness for Duty Incident,Falsification of Chemistry Records Involving EDG Fuel Oil & Falsification of Fire Protection Records ML20211F0441994-12-21021 December 1994 Requests That Plant,Unit 3 Restart Action Plan Be Replaced W/Encl Rev to Plan ML20236L5841994-11-0909 November 1994 Submits Interpretation of TS Requirement Re Fire Protection for Indian Point Unit 2 Per 940719 Memo NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20211E9541994-05-12012 May 1994 Requests Approval of Process by Which Plant,Unit 3 Restart Issues,As Listed in Restart Action Plan,Will Be Closed. Restart Issue Closure Process Outlined in Encl to Memo ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057C5721993-09-24024 September 1993 Forwards New Page 20,rev 12 of Security Plan Due to Rev 12 Copy Spillover from Page Nineteen Rev 13 Additions.Page Withheld ML20057B2111993-09-16016 September 1993 Forwards Update to Security Plan,Including Table of Contents,Rev 13 to Pages 18,19,21 & 24 & Chapter 11.Encl Withheld ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000286/19900161990-10-25025 October 1990 Notification of Significant Licensee Meeting 90-127/ Enforcement Conference on 901105 in King of Prussia,Pa to Discuss Licensed Reactor Operator Inattentiveness to Duty Noted in Insp Rept 50-286/90-16 ML20059D1341990-08-30030 August 1990 Notification of 900913 Meeting W/Util in Rockville,Md to Discuss Util Proposal to Upgrade Emergency Diesel Generators at Facility ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20196C4751988-06-23023 June 1988 Notification of Licensee Requested Meeting 88-097 on 880629 in King of Prussia,Pa to Discuss Security Program Topics ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195H0201988-02-16016 February 1988 Forwards Proposed Updated SALP Evaluation for Plant. Evaluation Based on Insps & Examiner Reviews Conducted During SALP Period Form 860801-870207 ML20195H0081987-12-0101 December 1987 Forwards Input for SALP Rept for Aug 1986 - Nov 1987 ML20147F8761987-10-21021 October 1987 Discusses 871022 Meeting W/Staff to Discuss NRC Position Re Util Steam Generator Replacement Program.Brief Summary of Licensee Position on Why Replacement Can Be Accomplished Under 10CFR50.59 Listed in Encl 1 ML20204G2771987-03-23023 March 1987 Notification of 870326 Meeting W/Util in Bethesda,Md to Discuss Info Required to Support Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870324 ML20207R2151987-03-10010 March 1987 Notification of 870324 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Facility Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870310 ML20212F9321987-03-0303 March 1987 Notification of 870310 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Decommissioning Plan & Need for Environ Statement ML20211K9161987-02-19019 February 1987 Summary of Operating Reactor Events Meeting 87-04 on 870209. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Events Encl ML20209H0831986-12-22022 December 1986 Summarizes INPO 861210 Accreditation Meeting in Atlanta,Ga. Listed Plants Presented Training Programs for Nonlicensed Operators,Reactor Operators,Senior Reactor Operators & Shift Technical Advisors ML20214T3041986-09-17017 September 1986 Notification of Rev 1 to Board Meeting 86-104 on 860923 at Region I to Discuss Regional Evaluation Phase of SALP ML20203N1921986-09-0808 September 1986 Notification of Board Meeting 86-104 W/Util on 860919 in King of Prussia,Pa to Discuss SALP Regional Evaluation Phase ML20207S2141986-08-0707 August 1986 Forwards Commission Directive to Staff to Respond to Shearon Harris Licensing Board Re Emergency Nighttime Alerting.Staff Should Address Alertability During Stormy Winter in Response to Indian Point Board 860609 & 0710 Ltrs ML20215A5931986-07-30030 July 1986 Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltrs 85-09 & 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee NUREG/CR-2655, Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 8607111986-07-10010 July 1986 Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 860711 ML20198H9381986-05-16016 May 1986 Notifies of 1986 Indian Point 2 full-participation Exercise on 860604 (Insp Rept 50-247/86-13).Team Assignments, Schedule,Exercise Event & Time Line,Open Items,Objective Lists & Synopsis of State & County Matl Encl.W/O Encl ML20199K4421986-05-10010 May 1986 Comments on Indian Point Special Proceeding.Severe Accident Policy Statement Should Be Reexamined ML20198E7621986-05-0808 May 1986 Informs of Next NRR Operating Reactor Events Briefing Scheduled for 850716 in Bethesda,Md.Guidelines for Participants Encl.Tentative Agenda for Meeting Listed ML20214G3971986-05-0808 May 1986 Forwards Sser on Review of Design for Automatic Shunt Trip for Reactor Trip Breakers.Util Response for Seismic Qualification Issue Acceptable.Licensee Will Be Required to Submit Tech Spec Changes ML20198E7981986-05-0808 May 1986 Informs That 850716 NRR Operating Reactor Events Briefing 85-12 Rescheduled for 850723 in Bethesda,Md.Agenda Encl ML20205N1051986-04-24024 April 1986 Requests Assistance in Review of Fuel Handling,Health Physics,Accidents & Environ Areas Per Encl Schedule of Decommissioning Actions ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20140C9931986-01-17017 January 1986 Comments on Proposed Memo Re Draft Annual Rept to EDO Concerning Use of PRA in Insp Program.Memo Fails to Discuss Emergency Risk Projection (Erp) Initiative.Summary of Erp & Probabilistic risk-based Insp Guidance Encl ML20137B3601986-01-0303 January 1986 Notification of SALP Board Meeting 86-006 on 860121 W/Util in King of Prussia,Pa ML20138J8241985-12-10010 December 1985 Notification of Licensee Meeting 85-125 on 851213 W/Util in King of Prussia,Pa to Discuss Security Program 1998-08-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20196J9371998-12-0808 December 1998 Notification of 990120 Meeting with Util in Peekskill,Ny to Inform Public of Licensee Plans for Decommissioning Indian Point Nuclear Generating Station Unit 1 ML20236X5861998-08-0505 August 1998 Summary of 980620 Meeting W/Members of W,Util & NRC in Rockville,Md Re best-estimate Small Break LOCA Model Issues. Attendees List & Nonproprietary Matl Presented at Meeting Encl ML20217E7381997-10-0202 October 1997 Forwards Operator Licensing Exam Administered on 970317-20 W/Outline & Initial Exam Submittal Designated for Distribution Under Rids Code A070 IR 05000247/19970021997-10-0202 October 1997 Forwards NRC Operator Licensing Exam Rept 50-247/97-02 (Including Completed & Graded Tests) for Tests Administered on 970317-20 ML20236N0661997-05-0202 May 1997 Responds to from Consolidated Edison Requesting Interpretation of TS as to Definition of Operable as It Applies to Afs Under Certain Scenarios ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134N6211997-02-19019 February 1997 Forwards Response to SB Bram to EDO Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny Approved W/Edit by Chairman for Dispatch ML20134N6371997-01-14014 January 1997 Requests Concurrence Re Proposed Response to SB Bram to EDO Concerning Proposed Corporate Reorganization of Consolidated Edison Co of Ny by Close of Business on 970117 ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20211E9921995-11-0808 November 1995 Informs of Plan to Augment Plant,Unit 3 Resident Staff & Provide around-the-clock Insp Coverage During Plant Restart from Current Unplanned Outage.Primary Objectives of Insp Listed ML20211D9061995-08-14014 August 1995 Forwards Final Rev to Plant,Unit 3 Restart Action Plan Based Upon Completion of Insp Activities & Util Oversight ML20203B9821995-06-29029 June 1995 Discusses OI Repts 1-95-011,1-95-012 & 5-93-014 Re Fitness for Duty Incident,Falsification of Chemistry Records Involving EDG Fuel Oil & Falsification of Fire Protection Records ML20211F0441994-12-21021 December 1994 Requests That Plant,Unit 3 Restart Action Plan Be Replaced W/Encl Rev to Plan ML20236L5841994-11-0909 November 1994 Submits Interpretation of TS Requirement Re Fire Protection for Indian Point Unit 2 Per 940719 Memo NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20211E9541994-05-12012 May 1994 Requests Approval of Process by Which Plant,Unit 3 Restart Issues,As Listed in Restart Action Plan,Will Be Closed. Restart Issue Closure Process Outlined in Encl to Memo ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057C5721993-09-24024 September 1993 Forwards New Page 20,rev 12 of Security Plan Due to Rev 12 Copy Spillover from Page Nineteen Rev 13 Additions.Page Withheld ML20057B2111993-09-16016 September 1993 Forwards Update to Security Plan,Including Table of Contents,Rev 13 to Pages 18,19,21 & 24 & Chapter 11.Encl Withheld ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000286/19900161990-10-25025 October 1990 Notification of Significant Licensee Meeting 90-127/ Enforcement Conference on 901105 in King of Prussia,Pa to Discuss Licensed Reactor Operator Inattentiveness to Duty Noted in Insp Rept 50-286/90-16 ML20059D1341990-08-30030 August 1990 Notification of 900913 Meeting W/Util in Rockville,Md to Discuss Util Proposal to Upgrade Emergency Diesel Generators at Facility ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20196C4751988-06-23023 June 1988 Notification of Licensee Requested Meeting 88-097 on 880629 in King of Prussia,Pa to Discuss Security Program Topics ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195H0201988-02-16016 February 1988 Forwards Proposed Updated SALP Evaluation for Plant. Evaluation Based on Insps & Examiner Reviews Conducted During SALP Period Form 860801-870207 ML20195H0081987-12-0101 December 1987 Forwards Input for SALP Rept for Aug 1986 - Nov 1987 ML20147F8761987-10-21021 October 1987 Discusses 871022 Meeting W/Staff to Discuss NRC Position Re Util Steam Generator Replacement Program.Brief Summary of Licensee Position on Why Replacement Can Be Accomplished Under 10CFR50.59 Listed in Encl 1 ML20204G2771987-03-23023 March 1987 Notification of 870326 Meeting W/Util in Bethesda,Md to Discuss Info Required to Support Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870324 ML20207R2151987-03-10010 March 1987 Notification of 870324 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Facility Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870310 ML20212F9321987-03-0303 March 1987 Notification of 870310 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Decommissioning Plan & Need for Environ Statement ML20211K9161987-02-19019 February 1987 Summary of Operating Reactor Events Meeting 87-04 on 870209. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Events Encl ML20209H0831986-12-22022 December 1986 Summarizes INPO 861210 Accreditation Meeting in Atlanta,Ga. Listed Plants Presented Training Programs for Nonlicensed Operators,Reactor Operators,Senior Reactor Operators & Shift Technical Advisors ML20214T3041986-09-17017 September 1986 Notification of Rev 1 to Board Meeting 86-104 on 860923 at Region I to Discuss Regional Evaluation Phase of SALP ML20203N1921986-09-0808 September 1986 Notification of Board Meeting 86-104 W/Util on 860919 in King of Prussia,Pa to Discuss SALP Regional Evaluation Phase ML20207S2141986-08-0707 August 1986 Forwards Commission Directive to Staff to Respond to Shearon Harris Licensing Board Re Emergency Nighttime Alerting.Staff Should Address Alertability During Stormy Winter in Response to Indian Point Board 860609 & 0710 Ltrs ML20207Q7071986-08-0707 August 1986 Staff Requirements Memo Requesting Provision of point-by- Point Response of Generic Safety Concerns Outlined in ASLB .Response to 860609 & 0710 Requests Re Adequacy of Alert Sys During Stormy Winter Nights Also Requested ML20215A5931986-07-30030 July 1986 Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltrs 85-09 & 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee NUREG/CR-2655, Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 8607111986-07-10010 July 1986 Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 860711 ML20198H9381986-05-16016 May 1986 Notifies of 1986 Indian Point 2 full-participation Exercise on 860604 (Insp Rept 50-247/86-13).Team Assignments, Schedule,Exercise Event & Time Line,Open Items,Objective Lists & Synopsis of State & County Matl Encl.W/O Encl ML20199K4421986-05-10010 May 1986 Comments on Indian Point Special Proceeding.Severe Accident Policy Statement Should Be Reexamined ML20198E7621986-05-0808 May 1986 Informs of Next NRR Operating Reactor Events Briefing Scheduled for 850716 in Bethesda,Md.Guidelines for Participants Encl.Tentative Agenda for Meeting Listed ML20214G3971986-05-0808 May 1986 Forwards Sser on Review of Design for Automatic Shunt Trip for Reactor Trip Breakers.Util Response for Seismic Qualification Issue Acceptable.Licensee Will Be Required to Submit Tech Spec Changes ML20198E7981986-05-0808 May 1986 Informs That 850716 NRR Operating Reactor Events Briefing 85-12 Rescheduled for 850723 in Bethesda,Md.Agenda Encl ML20205N1051986-04-24024 April 1986 Requests Assistance in Review of Fuel Handling,Health Physics,Accidents & Environ Areas Per Encl Schedule of Decommissioning Actions ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20140C9931986-01-17017 January 1986 Comments on Proposed Memo Re Draft Annual Rept to EDO Concerning Use of PRA in Insp Program.Memo Fails to Discuss Emergency Risk Projection (Erp) Initiative.Summary of Erp & Probabilistic risk-based Insp Guidance Encl ML20137B3601986-01-0303 January 1986 Notification of SALP Board Meeting 86-006 on 860121 W/Util in King of Prussia,Pa 1998-08-05
[Table view] Category:NRC TO ACRS
MONTHYEARML20138S0981985-11-0606 November 1985 Requests Review of Encl Re Comments & Recommendations Concerning Indian Point Special Proceeding & Commission Decision Cli 85-06 ML20235E9251972-12-21021 December 1972 Forwards to Applicants Re Consequences of Postulated Pipe Failures Outside Containment Structure 1985-11-06
[Table view] |
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8 tg g-
- UNITED STATES NUCLEAR REGULATORY COMMISSION
(
.E WASHWGTON, D. C. 20555 p*
/ November 6,1985 CHAIRMAN -
Mr. David A. Ward Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Ward:
By letter dated October 12, 1985, (copy enclosed), five members of the Advisory Committee provided comments and recommendations related to the Indian Point Special Proceeding and the Commission Decision (CLI 85-06).
Since "relatively broad considerations" are discussed in the letter, it would be beneficial to the Commission to have the views of the ACRS as a whole. Therefore, we request that you review the enclosed letter with the entire Advisory Committee and provide a report to the Commission.
Sincerely, y . f fdw &"
Nunzio J. Palladino
Enclosure:
As Stated 8511190521 R 851106 0 ADOCK 05000247 PDR L -
ENCLOSURE 1: ,
s October 12, 1985 l
lu
\
Honorable Nunzio J. Palladino Chairman \ '
U. S. Nuclear Regulatory Comission Washington, D. C. 20555
Dear Dr. Palladino:
I
Subject:
INDIAN POINT SPECIAL PROCEEDING We recognize that the Comission has acted on the Indian Point Special.
Proceeding but believe that it is worthwhile to provide some coments and recomendations for your further reflection. We shall not go into details of the proceeding but deal only with relatively broad consid-I
. erations, as follows:
- 1. Mr. Rowsnme of the NRC Staff testified that Inoian Pgint, Unit 2
' has a median frequency of core melt of roughly 4 x 10- per reactor l year for the "after fix" staff analysis described in the NRC testimony on Comission Question One, with a similar result for Indian Point, Unit 3. If this value were approximately represen-tative of the U. S. light water power reactors, it would suggest a chance of about one in two of a core melt accident by the year 2000 and a likelihood of essentially unity over the life of the current LWRs.
The uncertainties in the estimate for Indian Point are clearly large, with some factors pointing to possible overestimate and others to underestimate.
l We believe .that, especially for a high power nuclear power plant at one of the most highly populated sites in the U. S., the NRC should continue to strive for a substantial reduction in both the pre-dicted core melt frequency and the uncertainty therein.
Indian Point, Units 2 and 3, are evaluated by the Licensee and the NRC Staff as having a relatively effective containment in the presence of many, if not most, severe core accidents. However, these analyses res.t on incompletely understood phenomena, on generic rather than detailed examinations of containment (and plant) behavier, and on an incomplete set of accident scenarios.
Mr. Rowsome stated that he would be only mildly surprised if the consequences were a factor of 40 higher (or 200 lower) than the NRC Staff estimates.
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1 -
c . .- .
Honorable Nunzio J. Palladino 2. "The NRC Staff did not recomend design or operational improvements for the Indian Point units except- for a reliability assurance prog ram. However, they stated that, "it is the ensemble of evi-dence and ' the continued use of the PRA as a risk management tool (the sa fety assurance program) . . . that supported the staff recomenda tions." The majority of the ASLB recomended in favor of a filtered venting ' concept in view of the large uncertainties in
-the risk assessment and the high surrounding population density.
The Comission itself took a position less conservative than either the Staff or the majority of the ASLB.
- 3. Since the Staf f testimony at the Indian Point hearings, senior members of the NRC Staff have written coments in connection with ~
consideration of the NRC Safety Goals which are possibly at odds with the Indian Point decision. The Safety Goal Task Force, which includes Messrs. Murley, Rowsome, and Ernst, among others, raised the core melt frequency objective to first line status. Mr. Ernst and Mr. Minogue, in memoranda of May 10, 1985 and May 21, bdth support working toward the cora melt safety goal of 10 j985, per reactor year for existing nuclear power plants. Mr. Denton, in his memorandum of June 12, 1985, recomends a still more stringent core melt goal for existing plants.
- 4. In its report to you of July 17, 1985, the ACRS expressed its belief, "that the Comission frequency of not more than 10-ghould state that per reactor yeara is mean-core-melt an NRC objec-tive for all but a few, small, existing nuclear plants, and that, keeping in mind the considerable uncertainties, prudence and judgment will tend to take priority over benefit-cost analysis in working toward this goal."
- 5. We strongly support this ACRS position, and that a median estimate core melt frequency of 4 x 10 ge believeper rea'ctor year
_ (with very large uncertainties), for a high power plant at one of the most densely populated sites in the U. S., is too large for the
-long term and represents a situation requiring specific attention.
While we agree that it is acceptable for Indian Point, Units 2 and
. 3, to continue to operate, we recomend that the Comission require that both the Licensee and the NRC Staff develop, on some reason-able schedule, a plan for work intended to reduce both the esti-mated core melt frequency and the uncertainty therein. In addi-tion, we believe that detailed containment performance evaluation should be given particular emphasis at sites like Indian Point. It is our , belief that Comission policy should reflect prudence and
! come down on the side of safety, where the uncertainties remain t
large, giving appropriate consideration to both prevention and
Honorable Nunzio J. Palladino mitigation. We believb that, particularly if innovative approaches are used, significant 'mprovements in safety are achievable for Indian Point, Units 2 and 3, at reasonable costs.
Sincerely,
[Tavid Okrent, University of California Los Angeles, Califorrita 3se C. Ebersole, Tennessee Valley Authority, retired, Knoxville, Tennessee Dade W. Moeller, Harv~ard University Boston, Massachusetts
& s. Al Glenn A. Reed, Wisconsin Electric Power Company, Retired, Two Rivers, Wisconsin L
Charles J.~ vy ie, Duke r Company, Retired, Char te, a rolina cc: Comissioner Roberts Comissioner Asselstine Comissioner Bernthal Comissioner Zech Other Members of the Advisory Comittee on Reactor Safeguards
.