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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217C1051999-10-0808 October 1999 Forwards Amend 153 to License DPR-3 & Safety Evaluation. Amend Revises TS Section 6.0,Administrative Controls,By Deleting TS Sections 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20212J2231999-10-0101 October 1999 Forwards Copy of Environ Assessment & Fonsi Re 990317 Application for Amend to Revise TS Section 6.0 by Deleting TS Section 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20211J5001999-08-31031 August 1999 Forwards Proposed Rev 29 to Yankee Decomissioning QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation. Amend in Response to Application Dated 990324,deletes License Condition 2.C (10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20210S0621999-08-10010 August 1999 Forwards semi-annual fitness-for-duty Program Performance Data for six-month Period of 990101-990630,IAW 10CFR26.71(d) ML20210R1421999-08-0404 August 1999 Forwards Insp Rept 50-029/99-02 on 990411-0714.One Severity Level 4 Violation Occurred,Being Treated as NCV ML20210F3691999-07-21021 July 1999 Submits Response to NRC Request for Clarification of Certain Details of Yaec Proposed Mods to Yankee Nuclear Power Station Defueled TS ML20209D4881999-07-0909 July 1999 Forwards Rev 29 to Decommissioning QA Program, for Info & NRC Approval,Iaw 10CFR50.54(a)(3).Attachment a Provides Listing of Changes,But Does Not Discuss All Refomatting, Grammatical,Editorial or Typographical Changes ML20209C3271999-07-0101 July 1999 Forwards Rev 2 to Security Training & Qualification Plan.Rev Withheld ML20209C3151999-07-0101 July 1999 Forwards Rev 9 to Security Plan,Reflecting Plant Decommissioning Activities & Continues to Provide Protection Against Radiological Sabotage.Rev Withheld ML20209D1611999-06-28028 June 1999 Forwards UFSAR for Ynps.Updated Ynps FSAR Is Being Submitted Biennially,Iaw Commitment in Ltr Dtd 950614.Document Reflects Changes Made to Ynps as of 981231,unless Otherwise Noted ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195D6781999-06-0707 June 1999 Forwards Original & Two Copies of New England Coalition on Nuclear Pollution & Consolidated Intervenor Opposition to Yankee Atomic Electric Co Motion to Terminate,As Required by Rule for Filing ML20207E6301999-06-0101 June 1999 Informs of Relocation of Yaec Corporate Ofcs,Effective 990501.New Address Submitted.All Formal NRC Correspondence to Util Should Be Directed to Duke Engineering & Svcs, Marlborough,Ma ML20207D7991999-05-29029 May 1999 Forwards Original & Two Copies of Ltr to ASLB Chairman in Matter of Yankee Nuclear Power Station Proceeding.With Certificate of Svc ML20207D8181999-05-29029 May 1999 Requests That Board Convey to Panel That within Period of Time Authorized by NRC Regulations Author Intends to File, on Behalf of Intervenors,Responsive Pleading to Yaec Pending Motion to Withdraw in Ref Matter.With Certificate of Svc ML20207D8131999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328.Forwards Organizational Chart ML20195B3491999-05-25025 May 1999 Submits Withdrawal of Proposed License Amend to Approve Plant Termination Plan.New Application Will Be Submitted in Future ML20206Q1881999-05-17017 May 1999 Forwards for Filing,Necnp Request for Permission to File Contentions & Contentions on Inadequacy of NRC Staff 990412 Environ Assessment & Finding of No Significant Impact of Approval of Util Termination Plan.With Certificate of Svc ML20206H8701999-05-0505 May 1999 Informs That DB Katz Unable to Locate Copy of Attachments to Which Zobler Referred to in Response to Block Ltr.Requests Info on How Panel Will View Receipt of Ea.With Certificate of Svc ML20206R3221999-05-0505 May 1999 Forwards Insp Rept 50-029/99-01 on 990101-0411.No Violations Noted.Activities at Rowe Facility Generally Characterized by safety-conscious Operations to Maintain Spent Nuclear Fuel & Careful Radiological Controls to Workers ML20206D1801999-04-30030 April 1999 Forwards Citizens Awareness Network First Set of Interrogatories,Requests to Produce & Certificate of Svc. Requests Any Objections Be Submitted Withing Five Days of Filing Receipt.Without Encls.Related Correspondence BVY-99-031, Forwards Ynps Annual Radiological Environ Operating Rept for Jan-Dec 1998, IAW Plant Defueled TS 6.8.2.a1999-04-26026 April 1999 Forwards Ynps Annual Radiological Environ Operating Rept for Jan-Dec 1998, IAW Plant Defueled TS 6.8.2.a ML20206B6641999-04-24024 April 1999 Requests Board Take Action to Remedy NRC Failure to Comply with Board Request & NRC Counsel Representation to Board in Relation to That Request Re Serving EA Upon Petitioners Per Request of Board.With Certificate of Svc ML20206C0801999-04-23023 April 1999 Requests That Change Proposed in Request for Transfer of Administrative Requirements for Ynps Defueled TS to Plant Decommissioning QA Program Be Withdrawn ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205S0131999-04-17017 April 1999 Forwards Original & Two Conformed Copies of Necnp First Set of Interrogatories & Requests to Produce for Filing in Matter Re Yaec License Termination Plan.Related Correspondence ML20205L0701999-04-13013 April 1999 Grants Voluntary Extension to Allow CAN to Effectively Participate in Hearing Process (ASLBP 98-736-01-LA-R).With Certificate of Svc.Served on 990413 ML20205P9091999-04-13013 April 1999 Informs That Item Intended to Be Attached to 990412 Filing (Motion for Leave to Reply(Reconsideration of Portion of of Prehearing Conference Order)) Inadvertently Overlooked. Section 4, Final Radiation Survey Plan Encl ML20205P2191999-04-12012 April 1999 Informs That Mj Watkins Has Been Appointed to Position as Yankee Rowe Decommissioning Licensing Manager,Effective 990412.Individual Will Serve as Primary Point of Contact for All Info Flow Between NRC & Yaec ML20205K9361999-04-0808 April 1999 Informs That J Block,T Dignan & D Katz Came to Agreement to Extend Discovery in Yankee Rowe License Termination Plan Hearing Process (ASLBP 98-736-01-LA-R) by 1 Wk from 990611 Until 990618 ML20205G7791999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for Yankee Power Station,Per 10CFR50.75(f) ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee ML20205F6331999-03-29029 March 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept, for Third & Fourth Quarters of 1998.Rept Summarizes Quantities & Estimated Dose Commitments of Radioactive Liquid & Gaseous Effluents Released During 1998 ML20205N1531999-03-24024 March 1999 Submits Request to Elminate fitness-for-duty Requirement from Plant.Proposed Change Has Been Reviewed by PORC & Nuclear Safety Audit & Review Committee ML20204E5051999-03-17017 March 1999 Requests NRC Review & Approval of Listed Mods to App a of Plant Possession Only License DPR-3 ML20207F8791999-03-0505 March 1999 Forwards Amend 151 to License DPR-3 & Safety Evaluation. Amend Revises Pol by Changing Submittal Interval for Radioactive Effluent Repts from Semiannual to Annual ML20207H8981999-03-0303 March 1999 Responds to Concerns Raised in Petitions to Intervene Filed with NRC by Necnp on 980224 & Citizens Awareness Network on 980226.Petitioners Requested Hearing on NRC Staff Consideration of License Termination Plan for Yankee Plant ML20203G2391999-02-12012 February 1999 Forwards Corrected Index Page for Amend 150 Issued to License DPR-3 on 990203 ML20202H5741999-02-0303 February 1999 Forwards Amend 150 to License DPR-3 & Safety Evaluation. Amend Revises Possession Only License Through Three Changes to TS ML20202F1921999-01-28028 January 1999 Forwards Copy of EA & Fonsi Re Application for Amend to Yaec Pol for Ynps Dtd 980820.Proposed Amend Would Revise Pol Through Listed Changes to TS ML20202E9401999-01-25025 January 1999 Submits Correction to Encl Request for Leave to Make Oral Appearance Statement, .Date of Conference & Desire to Make Oral Appearance Were Inadvertently & Incorrectly Entered on 990127 Instead of 990126 ML20199L1811999-01-22022 January 1999 Requests Opportunity for Representative of EPA to Make Oral Limited Appearance Statement & Submit Written Comments During 990126 Prehearing Conference Re Licensee Termination Plan ML20199K9151999-01-21021 January 1999 Requests Leave to Make Oral Limited Appearance Statement at 990127 Prehearing Conference Re License Termination Plan,Per 981130 Order Concerning Change in Filing Schedules & Date of Prehearing Conference ML20198N1691998-12-30030 December 1998 Forwards Motion for Leave to Participate in Matter of Yankee Atomic Electric Co License Termination Plan ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) ML20154P9431998-10-16016 October 1998 Forwards Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program. Program Name Changed Due to Status of Plant.Plant in Final Stages of Decommissioning ML20154F0861998-10-0101 October 1998 Forwards Insp Rept 50-029/98-03 on 980601-0731.No Violations Noted ML20153D7271998-09-23023 September 1998 Informs of Changes Made in Personnel Staff at Yankee Nuclear Power Station 1999-08-04
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058G4961990-11-0808 November 1990 Advises That Maint Activity for Control Rod Relatch Witnessed by NRC on 901104.Activity Successful ML20197H6971990-11-0606 November 1990 Forwards Resident Safety Insp Rept 50-029/90-16 on 900821- 1001 & Notice of Violation ML20058F2151990-11-0202 November 1990 Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review - Data & Info Capability ML20058D3501990-10-30030 October 1990 Forwards Safety Insp Rept 50-029/90-17 on 900730-0803. Unresolved Items Noted ML20058D2411990-10-26026 October 1990 Requests Written Policies & Procedures Required by 10CFR26.20 Providing Background for fitness-for-duty Insp ML20058C3901990-10-22022 October 1990 Forwards Amend 137 to License DPR-3 & Safety Evaluation. Amend Modifies Surveillance Requirement 4.1.3.4 ML20062B8901990-10-19019 October 1990 Forwards one-time Exemption from 10CFR55.59(c)(3)(i)(A)-(L) Re Annual Operator Simulator Training ML20058D2811990-10-19019 October 1990 Discusses Violations Noted in Insp Rept 50-029/90-14 & Forwards Notice of Violation ML20062B8671990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant. Interest to Participate,Intent to Attend & Approx Number of Representatives to Attend Requested by 901115 ML20059P0161990-10-12012 October 1990 Advises That 900920 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20059N4801990-10-0303 October 1990 Forwards Maint Team Insp Rept 50-029/90-81 on 900709-20 & 0806-10.Weaknesses & Unresolved Item Noted ML20059M0511990-09-26026 September 1990 Forwards Corrected Pages to Amend 136 to License DPR-3 ML20059M5301990-09-25025 September 1990 Forwards Safety Insp Rept 50-029/90-12 on 900619-0820. Violations Noted But Not Cited ML20059J2411990-09-12012 September 1990 Advises That 900828 Revised Diesel Generator Test Plan for Qualification & Preoperational Testing Acceptable.Tech Spec Changes to Enable Util Achieve Credit for Increased Generator Capacity Will Be Considered When Proposed ML20059H5671990-09-12012 September 1990 Advises That NRC Terminated Review of YAEC-1710, Yankee Nuclear Power Station Pilot Evaluation Rept for Plant License Renewal, Per Util 900716 Request.Resolution of Issues Will Occur as Part of Review of Application ML20059K7111990-09-10010 September 1990 Forwards Insp Rept 50-029/90-14 on 900802-27.Enforcement Conference Scheduled for 900921 ML20059H0601990-09-0707 September 1990 Discusses Unescorted Access to Licensee Facilities & fitness-for-duty Program,Per .Nrc Regulations Do Not Prohibit Licensee from Accepting Access Authorization Program of Another Licensee,Contractor or Vendor ML20059G2231990-09-0606 September 1990 Forwards Amend 135 to License DPR-3 & Safety Evaluation. Amend Modifies Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly ML20059E3011990-08-31031 August 1990 Forwards Safety Assessment of Yae 1735, Reactor Pressure... Evaluation Rept for Yankee Nuclear Power Station, Submitted w/900705 Ltr.Nrc Calculations Recognizing Uncertainties Conclude That Plant May Operate Until Feb 1992 ML20058P0701990-08-0909 August 1990 Forwards Insp Rept 50-029/90-11 on 900619-22.No Violations Noted ML20058N0681990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Cooperative Effort Would Promote Efficiency & Enhance Effectiveness of Nuclear Power Plant Activities ML20056A9341990-08-0303 August 1990 Forwards Radiological Safety Insp Rept 50-029/90-13 on 900709-13.One Noncited Violation Noted ML20058L5981990-08-0202 August 1990 Forwards Amend 134 to License DPR-3 & Safety Evaluation. Amend Incorporates NRC Guidance in Generic Ltr 88-17 to Facility Tech Specs.Three New Tech Specs Added & Change Also Addresses Low Temp Overpressurization ML20058L5331990-08-0202 August 1990 Forwards Rept from NRC Consultant Gr Odette Re Yankee Rowe Reactor Vessel Integrity.Response Requested by 900806 ML20058L0241990-08-0202 August 1990 Forwards Amend 133 to License DPR-3 & Safety Evaluation. Amend Incorporates Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 ML20055J4861990-07-31031 July 1990 Requests Performance of PTS Probablistic Analysis Using Broad Range of Matl Properties Re Reactor Pressure Vessel Evaluation Rept ML20055J2651990-07-27027 July 1990 Forwards Request for Addl Info Re Yankee Rowe Severe Accident Closure Submittal.Questions Concern Individual Plant Exam,Containment Performance Improvement Program & Accident Mgt.Response Requested within 1 Month ML20058L4761990-07-25025 July 1990 Forwards Exam Rept 50-029/90-06OL on 900619-21 IR 05000029/19890801990-07-25025 July 1990 Ack Receipt of Re Violations Noted in Insp Rept 50-029/89-80 ML20055G7991990-07-16016 July 1990 Forwards Safety Insp Rept 50-029/90-09 on 900515-0618.No Violations Noted ML20055C8531990-06-18018 June 1990 Forwards Amend 132 to License DPR-3 & Safety Evaluation. Amend Changes Title of Technical Svc Supervisor & Establishes New Positions Entitled Maint Support Supervisor & Operations Support Supervisor ML20059M9131990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C2961990-02-19019 February 1990 Forwards Safeguards Insp Rept 50-029/90-05 on 900207-09.No Violations Noted ML20248H7331989-10-0303 October 1989 Forwards Safety Evaluation Re Procedures Generation Program for Plant.Program Incomplete in Some of Its Content & Should Be Revised.Revision Need Not Be Submitted to NRC But Retained for Subsequent Review ML20247H4021989-09-0909 September 1989 Formalizes Requests Made in Conversation Between M St Lauren,R Clark & G Maret Re Planned Insp of Plant Emergency Operating Procedures During 891106-17 ML20247F0841989-09-0707 September 1989 Forwards Amend 124 to License DPR-3 & Safety Evaluation. Amend Moves Onsite & Facility Organizational Charts from Section 6.0 of Tech Specs to Section 401 of FSAR ML20246P6861989-09-0101 September 1989 Forwards Notice of Withdrawal of 890321 & 0414 Applications for Amend to License DPR-3,revising Tech Specs Re Snubber Listing,Per Generic Ltr 88-12.List of Snubbers Should Be Included in FSAR or Other Document IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246L6361989-08-31031 August 1989 Forwards Safety Insp Rept 50-029/89-11 on 890626-0731.No Violations Noted.Tmi Action Plan Commitments Re Main Steam Line Radiation Monitor Should Have Received More Attention. Addl Info Re Four Unresolved Items Requested ML20247E6531989-08-31031 August 1989 Forwards Amend 123 to License DPR-3 & Safety Evaluation. Amend Removes Description of High Pressurizer Water Level in Section 2 Re Bases on Page B2-4 of Tech Specs ML20246L0551989-08-25025 August 1989 Forwards Safeguards Insp Rept 50-029/89-13 on 890724-28.No Violations Noted ML20246G1741989-08-23023 August 1989 Forwards Requalification Exam Rept 50-029/89-03OL.Licensee Requalification Program Assigned Overall Program Rating of Satisfactory ML20246H7301989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits.Request That Util Ensure Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20246C7181989-08-15015 August 1989 Forwards Safety Insp Rept 50-029/89-15 on 890731-0803.No Violations Noted ML20245H4521989-08-11011 August 1989 Responds to 890712 Application for Amend to License DPR-3, Revising Tech Specs Re Main Steam Line Monitors & Primary Vent Stack Noble Gas Monitor.Verification Requested That Util Withdraw 890712 Application,Per 890810 Meeting 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217C1051999-10-0808 October 1999 Forwards Amend 153 to License DPR-3 & Safety Evaluation. Amend Revises TS Section 6.0,Administrative Controls,By Deleting TS Sections 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20212J2231999-10-0101 October 1999 Forwards Copy of Environ Assessment & Fonsi Re 990317 Application for Amend to Revise TS Section 6.0 by Deleting TS Section 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation. Amend in Response to Application Dated 990324,deletes License Condition 2.C (10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20210R1421999-08-0404 August 1999 Forwards Insp Rept 50-029/99-02 on 990411-0714.One Severity Level 4 Violation Occurred,Being Treated as NCV ML20207D8131999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328.Forwards Organizational Chart ML20206R3221999-05-0505 May 1999 Forwards Insp Rept 50-029/99-01 on 990101-0411.No Violations Noted.Activities at Rowe Facility Generally Characterized by safety-conscious Operations to Maintain Spent Nuclear Fuel & Careful Radiological Controls to Workers ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205L0701999-04-13013 April 1999 Grants Voluntary Extension to Allow CAN to Effectively Participate in Hearing Process (ASLBP 98-736-01-LA-R).With Certificate of Svc.Served on 990413 ML20207F8791999-03-0505 March 1999 Forwards Amend 151 to License DPR-3 & Safety Evaluation. Amend Revises Pol by Changing Submittal Interval for Radioactive Effluent Repts from Semiannual to Annual ML20207H8981999-03-0303 March 1999 Responds to Concerns Raised in Petitions to Intervene Filed with NRC by Necnp on 980224 & Citizens Awareness Network on 980226.Petitioners Requested Hearing on NRC Staff Consideration of License Termination Plan for Yankee Plant ML20203G2391999-02-12012 February 1999 Forwards Corrected Index Page for Amend 150 Issued to License DPR-3 on 990203 ML20202H5741999-02-0303 February 1999 Forwards Amend 150 to License DPR-3 & Safety Evaluation. Amend Revises Possession Only License Through Three Changes to TS ML20202F1921999-01-28028 January 1999 Forwards Copy of EA & Fonsi Re Application for Amend to Yaec Pol for Ynps Dtd 980820.Proposed Amend Would Revise Pol Through Listed Changes to TS ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) ML20154F0861998-10-0101 October 1998 Forwards Insp Rept 50-029/98-03 on 980601-0731.No Violations Noted ML20237F1281998-08-27027 August 1998 First Partial Response to FOIA Request for Documents. Forwards App a Records Already Available in Pdr.App B Records Being Made Available in PDR ML20236F3391998-06-24024 June 1998 Forwards Combined Insp Repts 50-029/98-01 & 50-029/98-02 on 980101-0331.No Violations Noted ML20249A7841998-06-17017 June 1998 Forwards Amend 149 to License DPR-3 & Safety Evaluation. Amend Revises TS Sections Pertaining to Minimum Water Cover Over Sf,Crane Travel Over Sf & Related Bases ML20248M0111998-06-0909 June 1998 Informs That Review of QA Program (YOQAP-1-A),rev 28,has Been Terminated & TAC M99265 Closed,Per 980414 Withdrawal ML20217C2501998-03-18018 March 1998 Requests Info to Provide NRC W/Adequate Assurance That Ynps Operated IAW Provisions of Yaec QAP Description Following Sale of Yankee Nuclear Svcs Div to Duke Engineering & Svcs ML20216G1311998-03-17017 March 1998 Forwards NRC Staff Response to Requests for Hearing, Filed on 980316 Re Yankee Atomic Electric Co Proceeding Per 980317 Telcon.Name Inadvertently Omitted from Service List. Related Correspondence ML20217Q4251998-03-11011 March 1998 Responds to Addressed to Chairman SA Jackson Forwarding Hearing Request of Franklin Regional Planning Board (Frpb).Aslb Established to Consider Hearing Requests Including That of Frpb.Served on 980311 IA-98-175, Submits Request for Addl Info Re Spent Fuel Pit License Amend Request Concerning Defueled TSs of Plant1998-03-0202 March 1998 Submits Request for Addl Info Re Spent Fuel Pit License Amend Request Concerning Defueled TSs of Plant ML20237F2221998-03-0202 March 1998 Submits Request for Addl Info Re Spent Fuel Pit License Amend Request Concerning Defueled TSs of Plant ML20216F8551998-02-0505 February 1998 Forwards Copy of Transcript of 980113 Public Meeting in Shelburne,Ma.Meeting Sponsored by NRC in Order to Inform Public About Regulations Re License Termination Process for Permanently Shutdown Nuclear Power Plant ML20202E5031997-11-28028 November 1997 Ack Receipt of License Termination Plan,Dtd 970515.NRC Placed Notice of Receipt in Fr 62FR43559.Application for Amend That Complies W/Appropriate Sections of Commission Regulations Should Be Filed by Licensee ML20202F4041997-11-26026 November 1997 Responds to ,Supplemented by Facsimile Addressed to J Callan,Executive Director for Operations, Requesting Hearing on Proposed Action by NRC Licensee. Informs That Request Denied by NRC for Listed Reasons ML20217C4401997-09-23023 September 1997 Forwards Insp Rept 50-029/97-02 on 970401-0814.No Violations Noted ML20217B0511997-09-0909 September 1997 Requests Addl Info to Complete Review of Licensee License Termination Plan ML20217K7561997-08-0808 August 1997 Ack Receipt of License Termination Plan & Forwards Notice of Receipt of Availability for Comment ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141J4461997-05-16016 May 1997 Forwards Insp Rept 50-029/97-01 on 970301-31.No Violations Noted ML20138H2951997-05-0202 May 1997 Responds to Offering NRC Staff Opportunity to Participate in 970620 Meeting.Informs That NRC Staff Will Not Participate in Meeting ML20148B2201997-05-0101 May 1997 Discusses Expressing Concerns Re Security Program at Facility Being Maintained Under License from Nrc. NRC Will Conduct Evaluation of Program Including Security Risks Involved W/Configuration If License Requests Change ML20134B5141997-01-24024 January 1997 Forwards Insp Rept 50-029/96-04 on 961121.No Violations Noted ML20129G9121996-10-28028 October 1996 Forwards Notice of Completion of Hearing Process Re Approval of Decommissioning Plan.Commission Denied Petition for Review by Hearing Re Approval of Decommissioning Plan. Plan Is Considered PSDAR ML20129C9211996-10-16016 October 1996 Forwards Insp Rept 50-029/96-03 on 960829.No Violations Noted ML20237F1771995-08-10010 August 1995 Informs That NRC Would Like to Conduct Site Release Research at Yankee Rowe Reactor Site ML20149H0801994-11-0404 November 1994 Ack Receipt of Providing Comments on Plant Decommissioning Plan.Nrc Currently Reviewing Plan & Comments Will Be Addressed During Review CLI-94-03, Forwards Decision CLI-94-03 in Response to Formal Petition Re Decommissioning Activities at Plant.Commission Ruled That Component Removal Program Does Not Involve Any Activities Requiring Adjudicatory Hearing & Denies Request1994-03-31031 March 1994 Forwards Decision CLI-94-03 in Response to Formal Petition Re Decommissioning Activities at Plant.Commission Ruled That Component Removal Program Does Not Involve Any Activities Requiring Adjudicatory Hearing & Denies Request ML20059K1851994-01-26026 January 1994 Discusses 930804 Telcon & Subsequent Correspondence Phone Calls Re NRC Commitment to Respond to Concerns Raised by Citizens Awareness Network.Nrc Response Will Be Delayed Beyond Early January & Response Provided within Two Months ML20059C7701993-12-29029 December 1993 Discusses to J Taylor of Allegations Against NRC Re Early Component Removal Project.Informs Licensee of No Objection Re Removal of Four Sg,Pressurizer & Portions of Intervals from Plant & Site.W/Encl ML20059D6291993-12-29029 December 1993 Forwards Insp Rept 50-029/93-07 on 930826-27,0923 & 1115-18 & Notice of Violation ML20059A6911993-12-22022 December 1993 Forwards Which Requested Info Re Potential Radiation Doses from Plant Reactor Vessel Internals Proposed for Removal Under Util Component Removal Program ML20059J7591993-12-20020 December 1993 Responds to to Chairman Selin Re Component Removal Project at Plant & NRC Provisions to Obtain Public Comments on Project ML20058P2741993-12-0808 December 1993 Advises That Rev 2 to Defueled Security Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20058E3461993-11-19019 November 1993 Forwards Granted Exemption from Requirements of 10CFR50.54 to Util in Response to Licensee Request of 930924 ML20058D6241993-11-19019 November 1993 Forwards Approved Partial Exemption Request from Training rule,10CFR50.120,in Response to Util ML20059C8101993-11-18018 November 1993 Responds to Re Request for Hearing on Early Removal Project at Plant.Requests Specific Info Re Early Component Removal Project ML20058B6331993-11-15015 November 1993 Forwards Physical Security Insp Rept 50-029/93-08 on 931018-19.No Safety Concerns or Violations Noted 1999-08-04
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THIS DOCUMENT CONTA
[ UNITED STATES l 3
NUCLEAR REGULATORY COMMISslO WASHINGTON, D, C. 20S55 J
o ff YM%*e /' SEP 16 B77 I Docket No. 50-29 '
l Yankee Atomic Electric Company ATTN: Mr. Robert H. Groce !
Licensing Engineer i 20 Turnpike Road !
Westboro, Massachusetts 01581 l
Gentiemen:
f RE: YANKEE-ROWE ATOMIC POWER STATION l 5
The Nuclear Regulatory Commission has reviewed the. infomation that you !
are required by your tec;-ical specifications to submit as part of an l Annual Operating Report ;ad has concluded that much of the infomation !
now included in the An.ual Operating Report can be deleted and still meet i the desired NRC objectives. Therefore, we are planning to delete the l requirements for an Annual Operating Report provided that certain l infomation presently in the Annual Operating Report continues to '
be reported.
i The purpose of this letter is to request that you submit a proposal to ,
delete the ' requirement in your technical specifications for an Annual l Operating Report. There is, however, one portion of your Annual Operating ;
Report that must be retained in the Technical Specifications. The i tabulation of occupational exposure data is needed by NRC and must continue to be submitted on an annual basis. This tabulation may be j submitted along with any report of facility changes, tests or experiments I required pursuant to 10 CFR 50.59(b), or as a separate submittal if you wish. -
In addition, we request that you concurrently modify the content of your required Monthly Operating Report. You presently may be using three report fomats contained in " Reporting of Operating Information - Appendix A Technical Specifications" Regulatory Guide 1.16 as your monthly report.
The " Average Daily Unit Power Level" fomat remains the same and should continue to be used. The other two fomats, " Operating Data Report" and " Unit Shutdowns and Power Reductions", along with their associated instructions for completing the fomats, have been revised slightly.
These revised fomats should be used starting with your monthly report for January 1978. Twelve copies of each of the current fomats and the )
associated instructions are enclosed for your use. Additional copies may be obtained from our Office of Management Infomation and Program Control . Along with the three report fomats that provide much of the i
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[ Yankee Atomic Electric Company SEP 161977 needed monthly operating infomation, we request that you provide a
" Narrative Summary of Operating Experience" that describes the operation of the facility, including major safety-related maintenance, for. the monthly report period. The summary should be of the -style and detail similar to that previously prepared for inclusion 'into the Annual Operating Report. l This requested " Narrative Summary of Operating Experience" is to cover 'l
. each one-month period only and is part of the Monthly Operating Report' l which should be submitted by the tenth of the month.following the calendar month covered by the report to the Director, Office of Management Infomation and Program Control. You should state your intentions with respect to providing this revised Monthly Operating Report when you submit a proposal l to delote 'the Annual Operating Report. J In lieu of the 1977 Annual Operating Report, the NRC will compile, from previously submitted reports, that infomation now judged necessary.
This compilation of operating data will be transmitted to each licensee i for validation and addition of any missing data. Additionally, a separate, l one-time only, " Narrative Summary of Operating Experience" will be required to cover the transition period (calendar year 1977) because ,
the narrative of operating experience was not submitted with previous Monthly Operating Reports nor will there be an Annual Operating Report I which would have contained the narrative. !
We request that you (1) propose.a change to your technical specifications j that would delete the requirement for an Annual Operating Rep'rt, (2) 1 modify the content of your monthly report, (3) provide any missing data 1 in the summary compilation which will be prepared and transmitted to you !
by NRC, and (4) provide a narrative of operating experience for the year l 1977. We believe that this new reporting program will represent a significant i paperwork reduction, provide more timely infomation and eliminate unnecessary I infomation. We request that you make a submittal as soon as possible, but no later than November 1,1977, so we may delete the requirement for the f submittal of an Annual Operating Report by March 1,1978. '
7 Si nc erely, !
- p& dst. J
. S hw ncer, Chief -
Operating Reactors Branch #1 Division of Operating Reactors ,
Enclosures:
Monthly Re' port Formats and Instructions (12) cc: See next page
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-Yankee A,tomic Electric Company SEP 161977- t cc: Mr Donald G. Allen, President Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581 l Greenfield Public Library.
402 Main Street Greenfield, Massachusetts 01581 1
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. (y OPERATING DATA REPORT DOCKET NO.
DATE COMPLETED BY TELEPHONE OPERATING STATUS
- 1. Unit Name:
2.- Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
. 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe): , .
- 8. If Changes Occur in Capacity Ratings (!tems Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted,If Any (Net MWe):
- 10. Reasons For Restiictions,if Any:
This Month Yr. to Date Cumulative 11' Hours in Reporting Period .
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours ;
- 14. Hours Generator On.Line
- 15. Unit Reserve Shutdown Hours 1.
- 16. Gross Thermal Energy Generated (MWH) l
- 17. Gross Electrical Energy Generated (MWH) . . . l
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Eachh i
- 25. ,1f Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (0/77)
Wy
'- 1 * - INSTRbfl0NS FOR COMPLETING OPERAT!NG DA REPORT This. report should be fumis'hed each month by licensees. The narse and telephone number of the preparer should be provided in .
J the designated spaces.- The instructions below are provided to assist licensees in reporting the data consistently. The number of the
- in'struction corresponds to the item nurnber of the report format.
I c UNIT NAMEi Self. explanatory. or of commercial' operation; whichever comes last to the
. lo ,
end of the penod or decommissioning, whichever comes
- 2. REPORTING PERIOD. Designate the month for which first. Adjustments in clock hours should be made in the data are presented. '
which a. change from standard to daylight. savings time (or vice versa) occurs. 1
- 3. LICENSED THERMAL POWER (MWg )is the maximum thermal' power. expressed in megawatts, currently auth. 12. NUMBER OF . HOURS REACTOR WAS CRITICAL. ,
orized by the Nuelear Regulatory Commission. ' Show the total number of hours the reactor was entical i during the gross hours of the reporting period.
-4. NAMEPLATE RATING (GROSS MWf ). . The nameplate -
power designation of the turbine. generator in megavoit 13. REACTOR RESERVE SHUTDOWN 110URS. The ' total amperes (MVA) times 'the nameplate power factor of the number of hours dunng the gross hours of nportms turbine generator- penod that the reactor was removed from service for -
admimstrative or other reasons but was available for
- 5. DESIGN ELECTRICAL RATING INET MW,) is the operation.
nomina' net electrical output of the unit specified by the utility and used for the purpose of plant design. 14. HOURS GENERATOR ON.LINE. Also called Service Hours. The total number of hours expressed to the near.
- ec MAXIMUM DEPENDABLE CAPACITY (GROSS MW,) est tenth of an hour dunng the gross hours of the re.
Is the gross eleetncal output as measured at the output porting period ' that . the unit operated with breakers terminals of the . turbine. generator during the most re' closed to the station bus. These hours, plus those listed stnetive seasonal conditions. in Unit Shutdowns for the generator outage hours.should equal the gross hours in the reporting period.
- 7. MAXIMUM DEPENDADLE CAPACITY (NET MWi ).
Maximum dependable espacity (gross) less the normal
- 15. UNIT RESERVE SHUTDOWN HOURS. The total num.
- station service loads' ber of hours expressed to the nearest tenth of an hour l S. Self explanatory-dunng the ;ross hours of the reporttng period that the -1 unit was remosed from service for economic or simuar reas ns but was available for operation.
- 9. P0hER LEVEL TO WHICH RESTRICTED IF ANY INET MW, J. Note that tha item is applicable only if restnctions on the power level are m enect. Short. term 16. GROSS THfRMAL ENERGY GENERATED IMWil).
(less than one month) limitatior s on power level need The thermal output of the nuclear steam supply system ,
l not be presented m this item. durmg the gross huurs of the reporting penod, expressed in megawatt hours (no decimals).
S nee this informatien is used to develop figures on capa, etty lost due to restr cnons and because most users of the 17. GROSS ELECTRICAL ENERGY GENERATEDIMWH).
"Operatmg Plant Status Report" are pntnanly :nterested The electrical output of the unit measured at the cutput in energy actually fed to the ctstnbution system. it a terminals of the turbme. generator during the gross hours requested that the Qure be expressed m MWe. Net in of the reporting penod, expressed in megawatt hours (no spite of the fact that the figure must be derived from decimals).
MWt or percent power.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH).
- 10. REASONS FOR RESTRICTIONS, IF ANY. If item 9 The gross electrical output of the unit measured at the
. is used. item 10 should explain why. Bnef narrante is output termmals of the turbme. generator minus the not.
acceptable. Cite references as appropriate. Indicate mal stauon service loads during :he gross houn of the whether restnctions' are selfimposed or are regulatory reportmg penod, expressed in megawatt hours. Negative requirements. Be as speelne as possible within space limi- quantities should not be used if there ;s no net positive tations. Plants in startup and power ascension test phase value for the period, enter zero (no decimals).
should be identified here.
- 11. HOURS IN REPORTING PERIOD. For units in power . 19. For units still in the startup ai d power ascension test
. ascension at the end of the penod. he gross hours from 23. phase. items 10.:3 should not be eemputed. Instead, enter
'the begmning of the pened or the first vleetncal produe. N/A m the current month column. These five factors tion whichever .comes last. to the end of the period, should be computed starting at the time the unit is de.
elared to be m commercial operanon. The cumulative For units in commeraal operation at the end of the 'igures m the second and third columns snould be based pened, the gross hours fmm the begmnmg of the penod on commeraal operanon .a a stanmg date.
(0/77 )
- m. _ _ _ _ ___ _ _ __
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191 UNIT SERVICE FACTOR. Compute by dividing hou:s ' ;
the generator was on line (item 14) by the gross hours in -
' the reporting period (item 11).. Express as percent to the ;
. nearest. tenth of a percent. Do not include reserve shut. 1 down hours in the calculation. j
- 20. . UNIT AVAILABILITY FACTOR. Compute by dhiding ,
the' unit available' hours (item 14 plus item 15) by the i gross hours in the reporting period. (item 11). Express ' -
as percent to the nearest tenth of a percent.' i t
- 21. UNIT CAPACITY FACTOR (USING $1DC NET). Comi 'I pute by dividing net electrical energy generated (item 18) .
l by the product of maximum dependable capacity (item: k p 7) times the gross hours in the reporting period (item 11).. .
Express as. percent to the nearest tenth of a percent.
l
- 22. UNIT ' APACITY FACTOR (USING DER NET). Com- -
pute m ' item 21. substituting design electrical rating i (item 5) for maximum dependable capacity. !
23.. UNIT FORCED _ OUTAGE RATE. Compute by dividing the total forced outage hours (from the table in Unit .
I Shutdowns and Power Reductions) by the sum of hours generator on line (item 14) plus total forced outage hours i (from the table in Unit Shutdowns and Power Reductions). i Express as percent to the nearest tenth of a percent. >
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS ~
s (TYPE, DATE. AND DURATION OF.EACH). Include type (refueling. maintenance, other), proposed date of start of shutdown, and proposed length of shutdown.
It is recognized that shutdowns may be scheduled between .
reports and that this item may not be allinclusive. Be as ;
accurate as possible as of the date the report is prepared. <
This item is to be prepared each month and updr.ted if l
appropriate until the actual shutdown occurs, i
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. 25. Self explanatory. .
- 26. Self. explanatory. Note, however, that this information !
is requested for all units in startup and power ascension
- test status and is not required for units already in com- '
mercial operation.
l TEST STATUS is defined as that period following ini- ;
tial criticality during which the unit is tested at succes- .
sively higher outputs. culminating with operation at full [
pow:'r for a sustained period and completion of war-l ranty runs, Following this phase, the unit is pnerally {
eensidered by the utility to be available for commercial ;
operauon.
t Date of COSDIERCIAL OPERATION is detined as the !
date that the unit was declared by the utility owner to i be available for 'the regular production of electrieity. !
usually related ..to the satisfactory completion of quali-tication tests as specified in the purchase contraet and to [
a the accounting policies and practices of the utility, I i
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'; s.. y M UNIT SHUTDOWNS AND POWER REDUCTIUNS
- LNSTRUCTIONS This report sh'ould describi all plant shutdowns during the in accordance with the table appearing on the report form.
report period. In addition,it should be the source of explan- If category 4 must be used, supply brief comments.
ation of significant dips in average power levels. Each signi- ,
ficant reductic in power level (greater than 20"e reduction LICENSEE EVENT REPORT :t. Reference the' applicable i in average dab power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) ' reportable . occurrence pertaining to' the outage or power should be noted, even though the unit may not have been reduction. Enter the nrst four parts (event year, sequential- t shut down completely l. For such reductions in power level, fePort number, occurrence code and report type) of the flye ,
the duration should be listed as zero, the method of reduction part designation as described in item 17 of instructions for j should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report i
. Acuon to Prevent Recurrence column should explain. The (LER) File (NUREG 0161). This information may not be
' Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. since should be used te provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction. not a reportable occurrence was involved.) If the outage or ;
power reduction wiu not result in a reportable occurrence. ;
. NUMBER. Th!s column should indicate the sequential num- the positive mdication 'of this lack of correlation should be i
bet assigned to each shutdown or signincant reduction m power noted as not applicable (N/A); '
for that calendar year. When a shutdown or sign!0 cant power reduction begins in one report period and ends in another, SYSTEM CODE. The system in which the outage or power an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of },
21! shutdowns or sigmricant power reductions are reported. Exhibit G Instructions for Preparation of Data Entry S.nects Until a unit has achieved hs first power generation, no num- for Licensee Event Report (LER) File (NUREG.0161). ,
ber should be ass;gned to each entry. Systems that do not fit any existing code should be designa' ;
ted XX. The code ZZ should be used for those events where !
DATE. This column should indieste the date of the start a system is not applicable.
of each shutdown or significant power reduction. Report !
as year. month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropriate component as ~70814. When a shutdown or significant power reduction from Exhibit ! Instructions for Preparation of Data Entr>
beg:ns m one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG 0161). >
be made for both report penods to be sure all shutdowns using the fouowmg cntieria or s:gnificant power reduc: ions are reported. "
A. If a component failed,use the component directlyinvohed. l TYPE. Use "F" or "S" to mdicate either " Forced" or " Sche.
di,ed." respectively, for each shutdown or significant power .i B. If not a component failure, use the refated component; cedue:ic n. Forced shutdowns include those required to be ,
e.g.. wrong valve operated through error: list vahe as
- n
- ::s:ed oy no later than the weekend foUowmg discovery component. ;
of an eff normai condition. It is recogn: zed that some ,iudg- i mint is equired m ;stegontmg shutdowns in this way. In C. If a chain of failures occurs. the Srst component to mai. ;
- enerai. a forced shutdown is or.e that would not hase been function should be listed. The sequence of events. mclud-cct.p;e
- ed in the absence of the conditien for which correcove l
~ mg the other ecmponents which fail, should te descrfced ;
ac::en was :2 ken.
under the Cause and Corrective Action to Present Recur. i renec column.
DURATgN. Scicp;anatoryg When a shutdown ex: ends Comoonents that do not St any ex: sting code should te de. !'
ce>ong tne end or a report renod. count or yJ the t:m_e :o the s gnated XXXXXX. The code Z22222 should be used for er.d er y.e report penod and picx up :he ensumg down tune
- n :ne tudowing report penods. Report durauon of outages events where a component designation is not apphesole.
3 toanded :o me nearist tenth of an hour to facib:ste surnmation.
The sum af the total uutage hours plus the hours :he genera- CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.
ter was on line shou!d equal the poss hours m the reponmg RENCE. Use the column m a narrative fashion to amplify or !
penod. explam the circumstances of the shutdown or power reduction. I The column should include the spec:fic cause for each shut-RE ASO.\. Ca:egor:te n> ietter deugnanon in accordance down or significant power reduction and the immediate and '
w:th the me.e spearmg on the report form, it category H contemplated long term correcove acuon taken. if approrn- !
ate. This column should also be used for a description of the mat 'e sed suppy:ner comments.
major safety.related correctae maintenance performed durmg
' METHOD OF SHUTT!SG DowN THE REACTOR OR the outage or power reduct on including an identiScation of; REDUCING PO%ER. - Catepon;e by number designanon the enneal path setmty and a report of any smgle release er ,
~
radioactmt> ur sing!e radianen expcsure spee:nea!!y arsoe;. !
I%te : hat this Jifters f rom :he Edison E!cerne Institute .ited with the outage which aucunts for more than 10 per en: j
,EEli denninens of " Forced Parnai Outap" and " Sche. of the allowable annuai values.
- cj Puna! Outapr Fm these wrm EFl uses s hange .e l For long textual reports eentinue narrattve on separ;ne paper 30 M% as s.c creak pent, for iarge; smeFrese: ors. 30 M% and rererense the shu: dun or power reduonon f.o tna j
.3
- call J .r.any in w ha un: e\plJnahou. HJfrJuve.
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- AVERAGE DAILY UNIT POWER LEVLE '
., DOCKET NO.
i UNIT ;,
DATE l
' COMPLETED BY ,
i TELEFHONE i i
i 1
MONTH _
DAY $
AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL !
- (MWe Net) (MWe-Net )
1 I '17 ,
2 18 -
i
-3. 19 4 20 i t
. 5 21 ',
6 "
1 23 ,
8 24 l 9 25 10 26 I II 27 12 28 -
13 29 -
14 30 '
t 15 31 ;
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INSTRUCTIONS ,
On this forrnst. list the average daily unit power leselin MWe Net for each day in the reporting inonth. Compute to ;
thi nearest whole megawatt.
i (9 /77 ) .
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