Forwards Supplemental Response to Technical Evaluation Rept Re Items 3.3.5, Containment Isolation Valve Position & 3.3.11, Accumulator Tank Level & Pressure, Concerning Application of Reg Guide 1.97 at PlantML20237A568 |
Person / Time |
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Site: |
Zion File:ZionSolutions icon.png |
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Issue date: |
12/08/1987 |
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From: |
Leblond P COMMONWEALTH EDISON CO. |
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To: |
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
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References |
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RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 3916K, GL-82-33, TAC-51367, TAC-51368, NUDOCS 8712150101 |
Download: ML20237A568 (16) |
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Similar Documents at Zion |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217J4411999-10-18018 October 1999 Forwards Exemption from Certain Requirements of 10CFR73.55 for Zion Nuclear Power Station,Units 1 & 2 in Response to Application Dtd 990730,to Allow Util to Discontinue Specific Aspects of Security Plan & SER ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20216G9541999-09-27027 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990730 Application for Exemption.Exemption Would Allow Zion Nuclear Power Station to Discontinue Specific Aspects of Security Plan A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999 Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station ML20211L1551999-09-0101 September 1999 Forwards Insp Repts 50-295/99-03 & 50-304/99-03 on 990608-0812 at Zion 1 & 2 Reactor Facilities.No Violations Noted.Activities in Areas of Facility Mgt & Control, Decommissioning Support,Sf & Radiological Safety Examined ML20211J9701999-08-31031 August 1999 Discusses Request for Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans, for Plant,Units 1 & 2.Exemption & Safety Evaluation Encl ML20211J0311999-08-30030 August 1999 Agrees with Content in NRC 990810 Memo Re Plant Spent Fuel Pool.Memo Contains Accurate Summation of Info That Util Communicated to NRC During 990713 Telcon ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G8191999-08-26026 August 1999 Forwards Amend 6 to Fire Protection Rept for Zion Nuclear Power Station,Units 1 & 2, IAW 10CFR50.71(e).Attachment 1 Contains Summary of Changes ML20211F5971999-08-20020 August 1999 Submits Request for Addl Info Re Proposed Defueled TSs for Plant,Per NRC Bulletin 94-001, Potential Fuel Pool Draindown Caused by Inadequate Maint Practices at Dresden Unit 1 ML20211C7401999-08-19019 August 1999 Informs That NRC Plans to Stop Using Office Complex at Zion Nuclear Generating Station Which Commonwealth Edison Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1). NRC-owned Equipment to Be Moved on or About 991001 ML20211J4421999-08-13013 August 1999 Forwards, EA & Finding of No Significant Impact Re Application for Exemption ,as Suppl by 990708 & 19 Ltrs.Proposed Exemption Would Modify Emergency Response Plan Requirements as Listed ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210J0861999-07-30030 July 1999 Requests NRC Approval of Exemption from Certain Requirements of 10CFR73, Physical Protection of Plants & Matls, by 990921.Exemption Is Needed to Support Scheduled 991001 Implementation of Plant Sf Ni.Encl Withheld,Per 10CFR73.21 ML20210C3641999-07-20020 July 1999 Discusses OI Rept 3-98-017 Completed on 980224 Re Contract Security Officer That Inadvertently Brought Personal Handgun Into Search Area at Plant & Forward NOV ML20210C4201999-07-20020 July 1999 Discusses Investigation Rept 3-98-017 Into Info Reported to Comed on 980224,informing NRC That N Everson Brought Personal Handgun Into Personnel Search Area at Plant.Nrc Determined That Violation Occurred.Nov Encl ML20210C2561999-07-19019 July 1999 Forwards Rev 1 to Calculation 22S-B-110X-0068, Determination of Heat Load for Assemblies F50D & Z33A, as Replacement Pages to Rev 0.Calculation Submitted Re Request for Approval of Proposed Plant Defueled Station EP ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20209E7391999-07-0808 July 1999 Forwards Proposed Revised Znps Defueled Station Emergency Plan & Supporting Calculations.Revs to Proposed Defueled Station Emergency Plan Have Been Reviewed & Approved IAW Comed QA Program ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196D3301999-06-18018 June 1999 Forwards Insp Repts 50-295/99-02 & 50-304/99-02 on 990121-0608.No Violations or Deviations Were Identified. Weakness Noted in Self Assessment/Corrective Action Program in Which Series of Personnel Errors Not Recorded in PIF Sys ML20195H9391999-06-15015 June 1999 Forwards Revised Monthly Operating Rept for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.Data Was Revised to Reflect Change in Daylight Savings Time ML20207H6121999-06-10010 June 1999 Provides Synopsis of OI Rept 3-1998-012 & Summary of Relevant Facts Re Violation Involving Employment Discrimination Against SRO at Zion Station.Enforcement Conference Scheduled for 990707 ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs A99018, Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold1999-05-27027 May 1999 Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20207B5991999-05-14014 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created.Reorganization Chart Encl ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206D8041999-04-30030 April 1999 Forwards Zion Nuclear Power Station Annual Radiological Environ Operating Rept & Listing of Commitments ML20206B9371999-04-27027 April 1999 Discusses Investigation Rept 3-98-17 Re Info Reported by Licensee on 980224 That Firearm Detected During Routine Search of Contractor Employee & Failure to Rept Incident to Supervisor.Oi Rept Synopsis Encl ML20206B4051999-04-23023 April 1999 Ack Receipt of Encl FEMA Ltr,Transmitting FEMA Evaluation Rept for 980819 Annual Medical Drill for Zion Nuclear Power Station.No Deficiencies Noted.Two Areas Requiring Corrective Action Noted During Drill ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205S5811999-04-16016 April 1999 Responds to Which Urged Full Public Hearing to Held on Concerns Raised by R Robarge & E Dienethal Re Zion Npp.Commission Issued 990302 Memo & Order Affirming ASLB Decision to Deny Petition to Intervene A99014, Provides Description of Actions Comed Has Taken to Reinforce Safety Conscious Work Environ at Zion Nuclear Power Station1999-04-15015 April 1999 Provides Description of Actions Comed Has Taken to Reinforce Safety Conscious Work Environ at Zion Nuclear Power Station ML20205Q9971999-04-13013 April 1999 Requests NRC Approval of Plant Defueled Station Emergency Plan in Accordance with 10CFR50.54(q).Ltrs of Agreement Between Util & Offsite Agencies Who Have Agreed to Provide Assistance to Plant Encl.Calculations Also Encl ML20205P2071999-04-0909 April 1999 Discusses Insp Repts 50-295/98-02,50-304/98-02 & OI Rept 3-98-015 Completed on 981112 & Forwards Nov.Violation Involves Zion Supervisor Who Willingly Failed to Protect Unattended SGI from Unauthorized Disclosure ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20206B4331999-03-26026 March 1999 Forwards Rept for Annual Medical Drill Conducted for Zion Nuclear Power Station on 980819.Two Areas Requiring Corrective Action Identified During Drill ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util A99011, Responds to NRC Re Violations Noted Insp Repts 50-295/98-02 & 50-304/98-02.Corrective Actions:Uncontrolled Safeguards Documents Were Immediately Taken Into Possession & Controlled by Plant Security Supervisor1999-03-18018 March 1999 Responds to NRC Re Violations Noted Insp Repts 50-295/98-02 & 50-304/98-02.Corrective Actions:Uncontrolled Safeguards Documents Were Immediately Taken Into Possession & Controlled by Plant Security Supervisor ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) A99009, Forwards Znps Annual Occupational Exposure Rept, for Exposures Occurring in 1998.Listing of Commitments Contained in Ltr Provided as Attachment B1999-03-0101 March 1999 Forwards Znps Annual Occupational Exposure Rept, for Exposures Occurring in 1998.Listing of Commitments Contained in Ltr Provided as Attachment B ML20202J4381999-02-0303 February 1999 Forwards Zion Fuel Evaluation Info,Per Discussion ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List A99001, Forwards Zion 1998 Annual Rept of Revised Regulatory Commitments1999-01-19019 January 1999 Forwards Zion 1998 Annual Rept of Revised Regulatory Commitments 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999 Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station ML20211J0311999-08-30030 August 1999 Agrees with Content in NRC 990810 Memo Re Plant Spent Fuel Pool.Memo Contains Accurate Summation of Info That Util Communicated to NRC During 990713 Telcon ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G8191999-08-26026 August 1999 Forwards Amend 6 to Fire Protection Rept for Zion Nuclear Power Station,Units 1 & 2, IAW 10CFR50.71(e).Attachment 1 Contains Summary of Changes ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210J0861999-07-30030 July 1999 Requests NRC Approval of Exemption from Certain Requirements of 10CFR73, Physical Protection of Plants & Matls, by 990921.Exemption Is Needed to Support Scheduled 991001 Implementation of Plant Sf Ni.Encl Withheld,Per 10CFR73.21 ML20210C2561999-07-19019 July 1999 Forwards Rev 1 to Calculation 22S-B-110X-0068, Determination of Heat Load for Assemblies F50D & Z33A, as Replacement Pages to Rev 0.Calculation Submitted Re Request for Approval of Proposed Plant Defueled Station EP ML20209E7391999-07-0808 July 1999 Forwards Proposed Revised Znps Defueled Station Emergency Plan & Supporting Calculations.Revs to Proposed Defueled Station Emergency Plan Have Been Reviewed & Approved IAW Comed QA Program ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20195H9391999-06-15015 June 1999 Forwards Revised Monthly Operating Rept for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.Data Was Revised to Reflect Change in Daylight Savings Time ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs A99018, Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold1999-05-27027 May 1999 Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206D8041999-04-30030 April 1999 Forwards Zion Nuclear Power Station Annual Radiological Environ Operating Rept & Listing of Commitments ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 A99014, Provides Description of Actions Comed Has Taken to Reinforce Safety Conscious Work Environ at Zion Nuclear Power Station1999-04-15015 April 1999 Provides Description of Actions Comed Has Taken to Reinforce Safety Conscious Work Environ at Zion Nuclear Power Station ML20205Q9971999-04-13013 April 1999 Requests NRC Approval of Plant Defueled Station Emergency Plan in Accordance with 10CFR50.54(q).Ltrs of Agreement Between Util & Offsite Agencies Who Have Agreed to Provide Assistance to Plant Encl.Calculations Also Encl ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20206B4331999-03-26026 March 1999 Forwards Rept for Annual Medical Drill Conducted for Zion Nuclear Power Station on 980819.Two Areas Requiring Corrective Action Identified During Drill ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util A99011, Responds to NRC Re Violations Noted Insp Repts 50-295/98-02 & 50-304/98-02.Corrective Actions:Uncontrolled Safeguards Documents Were Immediately Taken Into Possession & Controlled by Plant Security Supervisor1999-03-18018 March 1999 Responds to NRC Re Violations Noted Insp Repts 50-295/98-02 & 50-304/98-02.Corrective Actions:Uncontrolled Safeguards Documents Were Immediately Taken Into Possession & Controlled by Plant Security Supervisor A99009, Forwards Znps Annual Occupational Exposure Rept, for Exposures Occurring in 1998.Listing of Commitments Contained in Ltr Provided as Attachment B1999-03-0101 March 1999 Forwards Znps Annual Occupational Exposure Rept, for Exposures Occurring in 1998.Listing of Commitments Contained in Ltr Provided as Attachment B ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20202J4381999-02-0303 February 1999 Forwards Zion Fuel Evaluation Info,Per Discussion ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List A99001, Forwards Zion 1998 Annual Rept of Revised Regulatory Commitments1999-01-19019 January 1999 Forwards Zion 1998 Annual Rept of Revised Regulatory Commitments A98056, Forwards List of Revised Various Commitments Originally Contained in Util to Nrc.Changes in Commitments Were Satisfactorily Evaluated Using NEI Commitment Change Methodology1998-12-11011 December 1998 Forwards List of Revised Various Commitments Originally Contained in Util to Nrc.Changes in Commitments Were Satisfactorily Evaluated Using NEI Commitment Change Methodology ML20198C2501998-12-11011 December 1998 Forwards Rev 45 to Zion Nuclear Power Station Security Plan, Per Requirements of 10CFR50.4(b)(4).Rev Includes Listed Changes.Licensee Has Concluded That Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed A98051, Forwards List of Revised Regulatory Commitments Which Were Evaluated as Satisfactory Using NEI Commitment Change Methodology1998-11-20020 November 1998 Forwards List of Revised Regulatory Commitments Which Were Evaluated as Satisfactory Using NEI Commitment Change Methodology A98055, Forwards List of Revised Regulatory Commitments Which Were Evaluated as Satisfactory Using NEC Commitment Change Methodology1998-11-20020 November 1998 Forwards List of Revised Regulatory Commitments Which Were Evaluated as Satisfactory Using NEC Commitment Change Methodology ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 A98059, Forwards Page Change Instruction for Aug 1998 DSAR for Zion Nuclear Power Station,Units 1 & 2.Instruction Was Omitted from 981110 DSAR Due to Administrative Error1998-11-11011 November 1998 Forwards Page Change Instruction for Aug 1998 DSAR for Zion Nuclear Power Station,Units 1 & 2.Instruction Was Omitted from 981110 DSAR Due to Administrative Error A98053, Forwards Change Instructions for Update to Zion UFSAR, Rewritten to Reflect Permanent Defueled Condition of Plant. & DSAR,1998-11-10010 November 1998 Forwards Change Instructions for Update to Zion UFSAR, Rewritten to Reflect Permanent Defueled Condition of Plant. & DSAR, ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20198C7401998-10-21021 October 1998 Informs That Encl Correspondence Was Received from Constituent,C Paxton Re Request for Investigation as to Documentation Also Encl.Without Encl ML20154J4951998-10-0707 October 1998 Forwards Revised Security Plans for CE Listed Nuclear Power Stations,Per 10CFR50.4(b)(4).Changes Do Not Decrease Effectiveness of Station Security Plans.Encl Withheld A98050, Forwards Zion Station Special Rept Number 30412398002SR.Rept for Reporting Period of Jan 1996-Dec 1997.Attachment B Provides Listing of Commitments Contained in Submittal1998-10-0505 October 1998 Forwards Zion Station Special Rept Number 30412398002SR.Rept for Reporting Period of Jan 1996-Dec 1997.Attachment B Provides Listing of Commitments Contained in Submittal ML20151Y5101998-09-11011 September 1998 Provides Results of drive-in-drill Conducted on 980804 & Augmentation Phone Drills Conducted Between 980601 & 0831 ML20238F7571998-08-28028 August 1998 Forwards fitness-for-duty Program Performance Data for Each of Util Nuclear Power Stations for Six Month Period Ending 980630 A98047, Forwards Revised Scope of One Commitment Contained in Response to NOV1998-08-28028 August 1998 Forwards Revised Scope of One Commitment Contained in Response to NOV ML20153F6811998-08-26026 August 1998 Informs of E Dienethal & R Robarge Concerns Re Safety of Areas in & Around City of Zion ML20237D9281998-08-24024 August 1998 Provides Description of Approach Being Taken by Comed to Develop Dsar.New Safety Classification Will Be Developed for Equipment Determined to Be Important to Defueled Condition 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0341990-09-20020 September 1990 Forwards Addl Station Blackout Info Re Diesel Loading & Alternate Ac Analysis,Per 900404 Meeting.Info Will Be Helpful When Evaluating Unit O Diesel Generator cross-tie Mod ML20059G1611990-09-0606 September 1990 Submits Supplemental Response to Generic Ltr 89-06, Certifying That SPDS Satisfies or Will Be Modified to Satisfy Requirements of Suppl 1 to NUREG-0737.Classroom Instruction on SPDS Incorporated Into Program ML20059G1751990-08-31031 August 1990 Provides Results of Util Reevaluation of Response to NRC Bulletin 85-003.Util Believes That Previous Testing Results & Subsequent Submittals Provide Assurance of Continued Operability of Sys motor-operated Valves ML20059D8271990-08-23023 August 1990 Provides Written Communication Re Util Intentions & Commitments,Per 900808 Telcon W/M Wallace.Standing Order 90-24 Issued to Provide Administrative Controls Beyond Tech Spec Requirements to Assure Svc Water Pump Availability ML20059C0781990-08-22022 August 1990 Submits Supplemental Info to Util 900412 Response to Notice of Violation in Insp Repts 50-295/89-40 & 50-304/89-36.Info Regards Requalification program,180 H of Required Training Through SAT Process & Policy for Remediation of Individual ML20056B4331990-08-20020 August 1990 Forwards Errata,To Radioactive Effluent Rept for Jan-June 1990 & Gaseous Effluent Errata Sheet ML20058P7791990-08-13013 August 1990 Provides Supplemental Response to NRC Bulletin 89-001 Re Mechanical Plugs Supplied by Westinghouse,Per .All Mechanical Plugs from Heats NX-3513 & NX-4523 Removed from Hot Legs of Plant Steam Generators ML20058N0651990-08-0707 August 1990 Responds to NRC Bulletin 88-009 Re Incore Neutron Monitoring Sys Thimble Tube Integrity.Thimble Tube Insps Will Be Performed at Every Refueling Outage Until Sufficient Data Accumulated on Thimble Tube Wear ML20056A0271990-07-30030 July 1990 Provides Addl Info Re Resolution of Number of Older Licensing Issues,Including Containment Isolation Valve Position Indication,Per NRC ML20056A0741990-07-27027 July 1990 Forwards Justification for Rev to Installation Schedules for Two Commitments Re Safeguards Inadequacies & Program Concerns.Encl Withheld ML20055J1191990-07-26026 July 1990 Responds to Generic Ltr 90-04, Request for Info Re Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. Current Status of Issues Encl ML20055J2231990-07-26026 July 1990 Requests Withdrawal of Proposed Amend Re Deletion of Confirmatory Order ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H0871990-07-20020 July 1990 Provides Status Rept on Molded Case Circuit Breakers Replacement,Per NRC Bulletin 88-010.Traceable Replacement Breakers for Units 1 & 2 Being Procured safety-related & Meet Criteria of Bulletin Action 7 ML20058N6821990-07-0606 July 1990 Suppls 900626 Response to CAL-RIII-90-011 Re Torque Switch Settings,Per NRC Bulletin 85-003.Program to Address Generic Ltr 89-10 Which Expands Scope of Bulletin 85-003 Testing to safety-related motor-operated Valves,Being Developed ML20055D5291990-06-27027 June 1990 Forwards Table Outlining Status of Significant Events Re PWR Reload Safety Analysis Methods for Plant Cycle 13.Requests That Transient Analysis Topical Rept Be Reviewed & SERs Issued Prior to 910830 ML20055D5231990-06-26026 June 1990 Responds to Confirmatory Action Ltr CAL-RIII-90-11 Re Actions Required to Confirm Valve Operability for Unit 1,per IE Bulletin 85-003 ML20055D8461990-06-24024 June 1990 Forwards WCAP-10962,Rev 1, Zion Units 1 & 2 Reactor Vessel Fluence & Ref Temp for PTS Evaluations ML20055D8391990-06-18018 June 1990 Provides Supplemental Info in Response to Generic Ltr 88-17, Loss of Dhr. Permanently Installed Level Transmitter, Independent from Refueling Vessel Level Recorder & Led Readout Will Be Utilized ML20055J4471990-04-26026 April 1990 Responds to NRC Re Violations Noted in Insp Repts 50-295/90-03 & 50-304/90-03.Corrective Actions:Training Rev Request Initiated & Personnel Counseled ML20055C2921990-02-21021 February 1990 Forwards Errata Data for Radioactive Effluent Rept for Jan- June 1989 & Solid Radwaste Rept for Jul-Dec 1988 ML20248G1171989-09-29029 September 1989 Forwards Revised Tech Spec Section 3/4.9,Page 210 to 890925 Application for Amends to Licenses DPR-39 & DPR-48 Re Containment Isolation,Per 890927 Request for Clarification ML20248D0881989-09-21021 September 1989 Forwards Rev 56 to QA Program Topical Rept CE-1-A ML20247N9031989-09-18018 September 1989 Forwards Revised Zion Station,Fire Hazard Analysis,App a of Branch Technical Position Apcsb 9.5-1 ML20247H5171989-09-15015 September 1989 Submits Supplemental Info Re Generic Ltr 88-17, Loss of Dhr. Evaluation of Rh Pump Motor Alarm Recommended That Inputs from Parameters Should Be Processed Through Computer W/Graphic Configuration Similar to SPDS Iconic ML20247F9641989-09-11011 September 1989 Documents 890711 Telcon Between CP Patel, J Bongarra & Author Re Deferral of Certain Dcrdr Commitments.Conversation Directed to Three Specific Issues & Related Human Engineering Deficiencies ML20247C4061989-09-0808 September 1989 Initiates Discussion Over Need to Reconsider Installation Date for Unit 1 Re Atws.Due to New Design,Implementation for Unit 1 Scheduled for Spring 1991 & Unit 2 for Spring 1990 ML20247M3201989-09-0101 September 1989 Forwards Corrected Operating Status Rept Re Unit Shutdowns & Power Reductions for Jul 1989 ML20246F5021989-08-24024 August 1989 Suggests Performance of Study to Determine Alternate Methods to Perform Preventative Maint of Diesel Generator O, Including Mod of Existing Plant Design or Operational Changes to Plant Evolutions ML20246Q1661989-08-23023 August 1989 Responds to NRC Re Violations Noted in Insp Repts 50-295/89-15 & 50-304/89-15.Corrective actions:nonsafety- Related Instrument Maint Procedures Reviewed & Error Evaluation Committee Meeting Held on 890517 ML20246E4761989-08-21021 August 1989 Forwards Errata Data to Effluent & Waste Disposal Semiannual Rept,1988, for Jul-Dec 1988 ML20245J2601989-08-10010 August 1989 Provides Addl Info Re Proposed Amend to Tech Specs Section 3.15, Auxiliary Electric Power Sys. Info Answers & Resolves Questions Raised by NRC Re Tech Spec Amend Request ML20245H3771989-08-0909 August 1989 Forwards Listed Policies,Including Endorsements 24 & 25 to Nelia Policy NF-294,Endorsements 19 & 20 to Maelu Policy MF-128,Endorsements 36 & 37 to Nelia Policy NF-277 & Endorsements 29 & 30 to Maelu Policy MF-114 ML20245J2501989-08-0404 August 1989 Provides Clarification Re Proposed Amend to Tech Specs Section 3.15, Auxiliary Electric Power Sys. Areas That Warrant Clarification Can Be Grouped Into Impact or Risk Assessment of Diesel Generator & Use of LOCA Events ML20247M5181989-07-28028 July 1989 Forwards Response to Safeguards Inadequacies Noted in Regulatory Effectiveness Review Insp on 890515-19.Encl Withheld (Ref 10CFR73.71) ML20247P4991989-07-27027 July 1989 Confirms 890725 Telcon Re Util Intention to Withdraw Pages 199a & 199b of 890613 Application for Amend to Tech Specs, Revising Guidance on RCS & Containment Isolation Valves Per Generic Ltr 87-09 ML20245F1701989-07-21021 July 1989 Responds to NRC 890526 & 0619 Ltrs Re Violations Noted in Insp Rept 50-295/89-19.Corrective Actions:Standing Order Issued on 890601 to Administratively Control Future Failures of 1(2)MOV-CS0049 or 1(2)MOV-CS00050 05000295/LER-1989-008, Forwards LER 89-008-00 Re Room Cooler Svc Water Supply Discrepancy Discovered on 8906091989-07-10010 July 1989 Forwards LER 89-008-00 Re Room Cooler Svc Water Supply Discrepancy Discovered on 890609 ML20247J0481989-07-0505 July 1989 Responds to 890622 Request for Addl Info Re Allegation RIII-88-A-0032,providing Info to Substantiate Allegations 1-4 & Corrective Actions Taken Re Allegation 5.Allegations Regard Unsatisfactory Performed Work ML20245K9321989-06-30030 June 1989 Suppls Util 880711 Response to NRC Bulletin 88-004.Util Confirmed That RHR Sys Could Experience pump-to-pump Interaction.Min Flow Rate of 50 Gpm for RHR Pump Would Prevent Cavitation & Pump Failure within 30 Minutes ML20245H1391989-06-20020 June 1989 Responds to NRC 890405 Request for Addl Info Re Design of Component Cooling Water Sys ML20245G2411989-06-19019 June 1989 Forwards Endorsements 55,28,205,179,55,37,117,100,108 & 97 to Nelia & Maelu Policies NF-227,MF-114,NF-43,MF-22,NF-253, MF-104,NF-187,MF-54,NF-201 & MF-64.respectively ML20244E5951989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Were Installed at Byron & Braidwood Stations.Remedial Actions Will Be Taken for Zion for Suspect Heats ML20247Q9321989-05-31031 May 1989 Provides Evaluation of Operation for NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Util Participating in Program for Partial Resolution of Issue Through Westinghouse Owners Group ML20245G9631989-05-26026 May 1989 Provides Response to Allegation RIII-88-A-0140 Forwarded to Licensee by for Investigation ML20244E2861989-05-25025 May 1989 Forwards Response to Allegation RIII-88-A-0176.Response Withheld (Ref 10CFR2.790) ML20247J7101989-05-18018 May 1989 Forwards Response to Allegation RIII-88-A-162.Encl Withheld (Ref 10CFR2.790(a)) ML20247C1451989-05-10010 May 1989 Forwards Appropriate Revs to Proposed Amends to Licenses DPR-39 & DPR-48 Re Reactor Protection Sys ML20247B4751989-05-0808 May 1989 Responds to NRC Re Violations Noted in Insp Repts 50-295/89-08 & 50-304/89-08.Corrective Actions:Change Made to Weld Map,Revising Weld Numbers to Agree W/Data Sheet & Discrepancy Rept Initiated to Document Error ML20246B2431989-05-0101 May 1989 Forwards Ltr Inadvertently Omitted from 1988 Radwaste & Environ Monitoring Annual Rept 1990-09-06
[Table view] |
Text
__-_ _________
e Ctmm:nwr.Ith Edison 2
V One First National Plaza. Chicago Ittinois Kddress Feply to: Post Offce Box 767 Chicago, Illinois 60690 0767 December 8, 1987 l
l U.S. Nuclear Regulatory Commission Attn: Document control Desk Washington, DC 20555
Subject:
Zion Nuclear Power Station Units 1 and 2 NUREG - 0737, Supplement 1 - Confirmatory Order Regulatory Guide 1.97 NRC Docket Nos. 50-295 and 50-304 TAC Nos. 51367/8 _
References (a): June 12, 1984 letter from S.A. Varga to D.L. Farrar (b): August 1, 1986 letter from P.C. LeBlond to H.R. Denton (c): May 15, 1987 letter from D.R. Muller to D.L. Farrar (d): August 24, 1987 letter from P.C. LeBlond to US NRC Gentlemen:
This transmittal is providing the NRC Staff with the results of additional review regarding the application o. Regulatory Guide 1.97 at Zion Station. Reference (a) transmitted an order confirming Commonwealth Edison company's commitment made in response to Generic Letter 82-33. Included among these items was a commitment to submit a preliminary report describing l how the requirements of Regulatory Guide 1.97 have been or will be met at Zion Station. That report was submitted in reference (b).
Reference (c) provided Commonwealth Edison Company with an interim Technical Evaluation Report (TER) and requested a response regarding the twenty-two open items identified in the TER. Commonwealth Edison Company's review of twenty of these open items was contained in reference (d).
Reference (d) stated that two items would require additional study. These items were:
3.3.5 - Containment Isolation Valve Position 3.3.11 - Accumulator Tank Level and Pressure commonwealth Edison Company has completed this additional study.
The results of this work are contained in the Attachment to this letter, go) 8712150101 871200 PDR ADOCK 05000295 \
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US NRC December 8, 1987 In addition, an internal Commonwealth Edison Company technical review has identified a concern regarding TER item 3.3.26. Reference (d) stated that "The existing flow instrumentation, FT-PR53, is capable of measuring flow in the range of 0 to 229,500 CFM".
This technical review has questioned the accuracy of the flow ]j instrumentation in the lower ranges (less than approximately 20,000 CFM).
l As a result, the adequacy of FT-PR53 is being reexamined. Commonwealth Edison expects to notify the NRC Staff of the results of this rereview by March 1, 1988. j
\
If any further questions arise regarding this matter, please direct l them to this office. l Very truly yours, Ph 4 P. C. LeBlond i Nuclear Licensing Administrator l 1
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Attachment cc: Resident Inspector - Zion l J. A. Norris - NRR i
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l ATTACHMENT SUPPLEMENTAL RESPCNSE TER ITEMS; l
3.3.5 and 3.3.11 !
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3.3.5 Containment Isolation Valve Position (Variable 29) !
l Regulatory Guide 1.97 recommends Category 1 valve position indication j for the purpose of verifying the accomplishment of isolation. The i licensee has provided a list of containment isolation valves and !
justification for exceptions (note 26) from the regulatory guide recommendations.
Based on the information provided, we are unable to determine that the recommendations for (a) redundancy, (b) single-failure criterion and )
(c) environmental qualification have been met. !
- a. The licensee has listed a group of valves that do not have position indication for series pairs. The licensee states that backup ,
indication is provided by various plant system variables. The I licensee should provide additional information for the valves listed i.e., why is there no indication of individual valves of the series pair? Why is a plant system variable adequate to determine the proper valve position?
- b. The licensee states that all air operated and solenoid operated valves fail in the safe direction (closed) on loss of power, thus, position status for these valves need only meet Category 3 criteria.
The fact that these valv(s are supposed to fail shut is not i sufficient justification for not meeting the single failure criterion. In an accident situation, the operator should be able to ascertain that the valves are in fact shut from the position j indication. The licensee should meet this single failure criterion. j
- c. We are unable to determine from the licensee's submittal which valve position switches are located in a mild environment and which l ones are not. The licensee should provide information that j verifies that all valve position switches requiring environmental !
qualification do in fact have the proper switch.
Ceco Response:
J Regulatory Guide 1.97 Rev. 2 indicates that Category 1 instrumentation I is recommended for those key variables >51ch monitor accident !
conditions. Containment isolation valva position indication is used by l the operator to detertine accomplishme it of a safety function, not to monitor accident conditions. The Catecary 1 variables required to monitor accident conditions which could cause a breach of containment were determined based on Section 1.2 of Regulatory Guide 1.97 which states in part:
"The sources of potential breach are limited to the energy sources within the cladding, coolant boundary, or containment."
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The key variables which are used to monitor accidents which may produce
" energy sources within ... containment" are:
- Containment pressure Containment Radiation j Because containment isolation valve position indication is not the i primary indication of the above variables, it was re-classified as a Category 2 variable. The following additional justification is l provided for the Category 2 classification:
- Containment isolation valve position indication does not provide !
the operator with information required to monitor containment conditions during or post-accident.
- Containment isolation valve position indication information is not used to prevent or mitigate adverse containment conditions. ;
The containment isolation function is a result of adverse containment conditions. Since the containment isolation function 1s interlocked to the key variables indicating accident and/or adverse containment conditions, it can be used as back-up indication of adverse containment conditions. Containment pressure and radiation monitoring instruments are designated as Category 1 instrumentation.
Containment isolation valve position indications are used to determine the status of each valve. Regulatory Guide 1.97 Rev. 2 page 3 states that Category 2 " generally applies to instrumentation designated for indicating system status". This is consistent with determination of valva status, i.e. open or closed.
A revised listing of conta!nment isolation valves is shown on Table 3, attached. With the except2on of manual valves, Table 3 shows each containment isolation valve listed in Section 3.9 of the Zion Station Technical Specification as updated by Amendments 95 and 105 effective June 23, 1987. Responses to NRC Technical Evaluation Report Item 3.3.5 were formulated to address this revised listing.
- a. Redundancy j Regulatory Guide 1.97 Rev. 2 does not require Category 2 variables to meet single-failure criteria. Since redundancy is used as a means of meeting single-failure criteria, redundant containment isolation valve position indication is not required. However, it should be noted that i most containment isolation valve position indications at Zion Station are redundant.
Table 3 shows the series pair valve associated with each containment isolation valve listed. Each containment isolation valve and its series pair valve are equipped with independent individual position indication except as noted. As noted on Table 3, a number of series pair valves are check valves. Table 2 of Regulatory Guide 1.97 Rev. 2 specifically excludes check valves from requiring position j '
indication. Therefore, all of the containment isolation valves listed
i
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f with series pair valves have redundant position indication and therefore meet single-failure criteria. For those valves which do not have a series pair valve, the following justification is provided:
A0V-CC9437 is a component cooling system containment isolation valve. The component cooling system piping isolated by AOV-CC9437 is a closed loop system. In order for a breach of containment to cause a release of radioactive materials, a simultaneous breach in ,
the component cooling pressure boundary and failure of the l containment isolation valve must occur. Also, A0V-CC9437 is a j normally closed, fail-closed valve allowing the operator to I ascertain the correct valve position in the event of a failure of the position indication. ;
i
- PCV-FP08 provides containment isolation for the fire protection I system. This valve is a normally closed, fail-closed valve, allowing the operator to ascertain the correct valve position.
- FCV-SS02, 3, 4 & 5 provide isolation of the steam generator blowdown sampling lines. Each of the four lines is a 3/8-inch diameter sample line routed to the steam generator sample panel and i sink. Failure of the isolation valves alone will not cause a breach of containment resulting in a radioactive release. Because blowdown sampling is a secondary system, a simultaneous failure of the primary system pressure boundary, (steam generator tubes), and the containment isolation valves must occur to initiate a radioactive release. Since these sample lines are equipped with radiation detection instrumentation, this instrumentation, RR-0001, j can be used as back-up instrumentation to determine if a breach of containment which could result in a release of radiation exists.
- Main steam isolation valves HOV-MS0001, 2, 3 and 4 and MSIV bypass valves FCV-MS82, 83, 84 and 85. Redundancy for these valves is provided by the flow, pressure, and radiatior. instrumentation associated with main steam flow. This additional instrumentation was previously identified as meeting Regulatory Guide 1.97 Rev. 2 recommendations for Category 2 variables. The pressure, flow and radiation instrumentation available for back-up indication of valve closure were listed in the original Zion Station Regulatory Guide 1.97 submittal as variable numbers 62, 63, and 86 respectively.
- MOV-SW0001, 2, 7, 8, 9, 10 & 11 are the service water isolation valves. The s<rtice water system in containment consists of a closed loop c Jing water system for the containment ventilation coolers. The discharge lines are equipped with radiation detection instrumentation. These instruments provide monitoring for radioactive materials which could be transported in the service water system following a breach in the closed loop system and failure of the containment isolation valves.
Since the purpose of the containment isolation function is to prevent the release of radioactive materials from containment, the existing valve position indication together with the radiation monitoring equipment (pR014 & RRPR19) provide sufficient redundancy to determine if a breach of containment exists.
l
- b. Single-Failure Criteria Category 2 variables are not required to meet single-failure l criteria. However, in order to address the NRC concerns the following response was prepared.
The containment isolation valves with series pair valves are redundant and therefore satisfy single-failure criteria. This is because the series pair containment isolation valves have physically separate individual position indications (excluding check valves).
With the exception of A0V-CC9437 and FCV-PP08, the A0V's and FCV's without series pair isolation valves are equipped with redundant separately powered control air solenoids. This ensures that a single-failure will not prevent accomplishment of containment isolation since these valves are fail-closed.
Single-failure criteria for the MSIV's, MSIV bypass, and service water ;
isolation valves is met by the back-up instrumentation discussed above.
- c. Environmental Qualification Table 3 shows the zone and environment for each containment isolation valve. Valves located in mild environments and qualified motor operated valves with internal limit switches, meet Regulatory Guide 1.97 environmental qualification recommendations. ;
i The majority of the remaining valves are in " radiation only" environments. The position switches for these valves as well as all other containment isolation valve position switches will be analyzed to confirm their suitability for their environments. Those position switches which do not meet the standards required for reliable ]
operation in their respective environments will be replaced on an j "as-fail" basis as part of normal maintenance activities. Replacement switches will be selected in accordance with Regulatory Guide 1.97 environmental qualification recommendations, i
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3.3.11 Accumulator Tank Level and Pressure Regulatory Guide 1.97 recommends environmentally qualified instrumentation for this variable with a range of 10 to 90 percent volume (for level) and 0 to 750 psig (pressure). The licensee has supplied instrumentation with no environmental qualification. The provided ranges are approximately 20 to 95 percent of the tank volume and 0 to 700 psig.
The licensee states that the primary function of both level and pressure instrumentation is to monitor the pre-accident status of the accumulator tanks to assure that this passive safety system is prepared to serve its safety function.
The accumulators are passive devices. Their discharge into the reactor coolant system (RCS) is actuated solely by a decrease in RCS pressure. We find that the ranges of the instrumentation supplied for this variable are adequate to determine that the accumulators have discharged.
Therefore, the ranges of this instrumentation are acceptable for this variable.
The existing non-qualified instrumentation is not acceptable. An environmentally qualified instrument is necessary to monitor the status of these tanks. The licensee should designate either level or pressure as the key variable to directly indicate accumulator discharge and provide instrumentation for that variable that meets the requirements of 10 CFR 50.49 and Regulatory Guide 1.97.
In response to reference (c) CECO has performed a detailed review of Emergency Operating procedures as they relate to the use of accumulator Tank Level and pressure Instrumentation, item 3.3.11 of the TER. We have determined that neither accumulator tank level nor pressure instrumentation is used anywhere in the EOp's. Based up.on this information, there is sufficient additional justification to tbclassify the subject instrumentation as Category 3. Listed below is the summary of that review.
- 1. E-O Reactor Trip or Safety Iniection This procedure verifies that the auto actions were performed and attempts to diagnose the accident. - No mention is made of accumulator tank level or pressure instrumentation.
- 2. .E- 1 Loss _.of Reactor __or Secondary Coolant This procedure continues to verify and diagnose the accident and confirm E-O diagnostics. If large LOCA exists, subprocedure ES-1,3 is utilized; subprocedure ES-1.2 for small LOCA. - Again, no mention is made of accumulator tank level or pressure l instrumentation.
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- 3. ECA-0.0 Loss of All AC Power With loss of all AC power the ability of supplying any cooling water is lost. RCP seals are postulated to leak, leading eventually to large LOCA. - No direction is given for the operator to verify the injection of the accumulators, or to check accumulator tank level or pressure.
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- 4. ECA-1.1 Loss of Emergency Coolant Recirculation j l
This procedure addresses the existence of a LOCA combined with an !
inability to go to cold leg recirculation. Actions are taken to maximize make-up and reduce the outflow. Core Exit T/C's and RVLIS are used to determine adequate core cooling. - Accumulator tank level or pressure instrumentation is not used here at all. l S. FR-C.1 Response to Inadequate Core Coolin_g FR-C.2 Response to Degraded Core Cooling l
Reactor coolant system pressure, temperature and RVLIS are {
primarily relied on in these procedures. - Again, the accumulator l tank level or pressure are not required.
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