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 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 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 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 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 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 A99016, 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 Time1999-06-15015 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 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 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 IR 05000295/19980021999-04-0909 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 ML17191B2671999-03-12012 March 1999 Forwards Revs to Dresden,Quad Cities,Zion,Lasalle,Byron & Braidwood Station Odcm,Current as of 981231.ODCM Manual & Summary of Changes,Included 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) ML17191B2331999-02-0909 February 1999 Discusses Ceco 950105 Request for Review & Approval of Four near-site Emergency Operations Facilities (Eofs) & Corporate EOF Into One Single,Central Eof.Concludes That Central EOF Meets All of Functional & Physical Requirements for EOFs ML20202J4381999-02-0303 February 1999 Forwards Zion Fuel Evaluation Info,Per Discussion 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 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 A99016, 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 Time1999-06-15015 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 ML17191B2671999-03-12012 March 1999 Forwards Revs to Dresden,Quad Cities,Zion,Lasalle,Byron & Braidwood Station Odcm,Current as of 981231.ODCM Manual & Summary of Changes,Included 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 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 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 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 05000295/LER-1997-022-01, Forwards LER 97-022-01,IAW 10CFR50.73(a)(2)(v).Commitments Made within Ltr,Encl1998-08-28028 August 1998 Forwards LER 97-022-01,IAW 10CFR50.73(a)(2)(v).Commitments Made within Ltr,Encl 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 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 ML20028G8741990-08-26026 August 1990 Forwards Supplemental Info to Support 900523 Application for Amends to Licenses DPR-39 & DPR-48 Re Generic Ltr 83-37 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 ML20044A9511990-07-10010 July 1990 Advises of Westinghouse Reassessment of Portion of Analysis to Address Issue of Rapidly Propagating Fatigue Cracks in Steam Generator Tubes Per Bulletin 88-002 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 ML20043H3591990-06-19019 June 1990 Provides Supplemental Response to NRC Bulletin 88-008 & Suppls 1 & 2.Repts Use Inconsistent Terminology When Describing Lines 1/2RC005,1/2RC038,1/2RC071 & 1/2RC079 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 ML20043D3171990-06-0101 June 1990 Forwards Rev 22 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043F0421990-05-29029 May 1990 Notifies of Change to 770527 Commitment Re 125 Volt Dc Mimic Panels for Plant ML20043C9161990-05-21021 May 1990 Forwards Response to 880828 Request for Addl Info Re Control Room Ventilation Sys.Appropriate Pages from Fire Protection Plan Encl.W/Four Oversize Drawings ML20043C2751990-05-14014 May 1990 Provides Supplemental Response to Bulletin 89-002 Re Insp of Anchor/Darling Check Valves.Insp of All Check Valves Completed.Five Failures Discovered During Insp.Approval of Proposed Schedule for Completion of Valve Insp Requested ML20043D2201990-05-10010 May 1990 Forwards Request for Addl Info Re Steam Generator Girth Welds.Results of Hardness Tests on Girth Welds & Surrounding Areas & Results of Boat Sample Analyses Will Be Submitted W/Outage Rept ML20043F0341990-05-0707 May 1990 Advises That Use of Incorrect Info on Operation of Plant Resulted in Core Damage Probability Higher than Actual. Requests New Info to Reevaluate Conclusions of Rept ML20042G9701990-05-0303 May 1990 Forwards Corrected Monthly Operating Rept for Mar 1990 for Zion Unit 1.Original Rept Did Not Reflect Correct Forced Outage Duration for Time Period ML20042F3321990-05-0101 May 1990 Forwards Detailed Description of Facility Steam Generator Girth Weld Insp Results.Licensee Concludes After Review of Flaw Evaluation That Indications Acceptable 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 ML20034A3431990-04-12012 April 1990 Responds to Violations Noted in Insp Repts 50-295/89-40 & 50-304/89-36.Corrective Actions:Importance of Adhering to Requirements of 10CFR55.53 Discussed W/Personnel Involved & Refueling Procedures Revised ML20034B6901990-04-12012 April 1990 Forwards Rev 58 to CE-1-A, QA Program for Nuclear Generating Stations. Rev Being Made to Reflect Correct Frequency of Cumulative Deviation Reporting & to Clarify Applicability of Other ANSI N45.2 Stds ML20034A3371990-04-11011 April 1990 Forwards Analysis of Capsule Y Commonwealth Edison Co,Zion Nuclear Plant Unit 1,Reactor Vessel Matl Surveillance Program. Analysis Summary Listed ML20033H1451990-04-0202 April 1990 Informs That Amend Request Identifying Recirculation Phase Action Requirements Will Be Submitted by 900501 ML20012D2291990-03-15015 March 1990 Forwards Graded Quizzes of Seventh Licensed Operator Retraining Program Administered in 1990,per Confirmatory Action Ltr CAL-RIII-89-21 ML20012C5931990-03-13013 March 1990 Forwards Response to Request for Addl Info Re Degraded Tube R1C55 in Steam Generator A.Athos 3-D T&H Analysis Used to Obtain Calculated Velocities for Same Test Conditions ML20012B0321990-03-0202 March 1990 Responds to 900131 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Corrective Actions: Task Force Initiated & Nuclear Engineering Dept Developed Training Course for Preparation of Evaluations for Mods ML20033E8461990-03-0202 March 1990 Documents Basis for Request for Temporary Waiver of Compliance W/Diesel Generator Operability Requirements. Results of Investigation Will Be Discussed W/Region III Personnel If Diesel Generator Returned to Operable Status ML20012A7241990-02-27027 February 1990 Withdraws 891031 & 881208 Tech Spec Amends.Util Will Be Making New Requests for Tech Spec Amends in Future Utilizing New Guidelines to Assure That Submittals Meet Improved Stds ML20012A2791990-02-27027 February 1990 Forwards Proprietary & Nonproprietary Rev 0 to NFSR-0069, Transient Analysis Envelope for Zion Units 1 & 2. Proprietary Rept Withheld (Ref 10CFR2.790) ML20055C2921990-02-21021 February 1990 Forwards Errata Data for Radioactive Effluent Rept for Jan- June 1989 & Solid Radwaste Rept for Jul-Dec 1988 ML20012A0181990-02-21021 February 1990 Forwards Corrected Monthly Operating Rept for Jan 1990 for Zion Unit 1,reflecting Correct Duration for Time Period ML20011E1801990-01-30030 January 1990 Requests Relief from 800229 Confirmatory Order for Facility to Extend Outage Time for 40 H in Order to Complete Repair Air Start Sys & Perform Operability Run on Diesel Generator 1B,per 900130 Telcon ML20006C0431990-01-29029 January 1990 Forwards Response to NRC Bulletin 89-003.Util Nuclear Fuels Dept Designs or Reviews & Approves Each Core Reload for Plants & Refueling Operations Recently Reviewed to Ensure Appropriate Procedural Controls in Place ML20006E7351990-01-25025 January 1990 Forwards Response to SALP 8 Rept for June 1988 - Sept 1989 ML19354E4931990-01-23023 January 1990 Requests Withdrawal of Proposed Tech Spec Re Operation of Containment Purge & Vent Sys.Withdrawal Requested to Permit Inclusion of Evaluation of Confirmatory Order in Significant Hazards Consideration ML19354E1761990-01-22022 January 1990 Provides Results of Unit 1 latching-type Relays & Informs That Electrical Maint Procedure E005-2 Revised to Ensure That All Future Relays Will Be Inspected for Proper Latch Engagement Prior to Installation ML20006B0141990-01-22022 January 1990 Requests Withdrawal of 860221 Proposed Tech Spec Amend Re Operation of Containment Purge & Vent Sys.Amend Request on Subj,Including Rev of Plant Confirmatory Order,Will Be Submitted in Future ML19354E1671990-01-22022 January 1990 Provides Results of Unit 1 Breaker Insp & Advises That Remaining Ds Breakers,Consisting of 28 DS-206 Breakers Also Inspected During Fall 1989 Refueling Outage & Pole Shafts Replaced on Breakers Not Meeting Weld Criteria 1990-09-06
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Text
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'Q.
' 14 -
Commonwealth Edison -
' Zion Generat Station :.
1i ShNoh Blvd. &
e Michigan
?
Zion. Rhnois 80099
- Telephone 708 / 746 2084
?
June 26, 1990 t -
'Mr. A..Bert Davis' 3
U.S. Nuclear Regulatory Commission Region III i
799 Roosevelt Road Glen Ellyn, IL 60137:
7
- w
-- Subj ec t :
Zion Station Units 1 & 2 i
. Motor Operated Valves J
Torque Switch Settings NRC Docket Nos. 50-295/304 r
Dear Mr. Davis:
-,7
'As'a result.of recent inconsistencies in MOV torque switch settings,.a
- review has been made.by Commonwealth Edison-personnel as to the operability of a
safety-related, valves at Zion' Station.
This-review was discussed:with members-
- of your staff on June 21 and 22,-1990.
Confirmatory Action Letter (CAL) RIII 90-011 describes actions required to confirm valve operability for Unit 1 t
i
-(currently l operating in Mode 1).
l
'InresponsetoCALRIII90-011,itema,ZionSt$tionhasconfirmed'that j
=all of the IEB 85-03 MOVs are operable per the following discussion:
- t N
11.
Per' CAL-RII'I-90-011 item b, valves listed under Category 1 (per' Attachment), have had their torque switch settings verified correct or-changed to correct' settings since the. concerns have been raised.
Appropriate LCO's were entered per Technical Specifications-during these maintenance' inspections.
\\
Per-CAL RIII 90-011, item c, MOVs in categories 2 thru 6 (per Attachment)~
have operability determinations based on a plant or' equipment configuration as described below.-
~
q I-
- 2. -_ Valves listed under Category 2 are' valves tha't do not need to change.
' position during accident conditions but are periodically stroked closed and would present a. problem if they,did not reopen. These valves are
- deenergized open per the Technical Specifications or have been caution i
' carded to not be' stroked closed for periodic tests until-their torque switch settings-are r.qfirmed.
These settings will be checked prior to
. the next periodic test of these valves.
9007090055 900626 PDR ADOCK 0500o293 M 2 7 1990 PDC c
-ZINZEST/109'
}
r 3.
The valve listed under Category 3 (which is stroked quarterly per PT-7B " Aux-
- Feedwater Pumps Service Hater Valves Operability Checks") does not need to i
stroke:against a differential pressure as discussed in our IEB 85-03 response, provided-it:is stroked prior to its-upstream valve.
This upstream valve has already been verified to have its torque switches set properly. A procedure change to A0P 4.3 " Inadequate Auxiliary Feedwater Supply" has been completed to require this valve stroking sequence.
4.
Valves listed under Category 4 are valves that are tested periodically at or near'their accident differential pressures.
If these valves fail the required tests, the appropriate Technical Specifications will be entered. MOVs VC 8110' and VC Bill are stroked monthly during PT-21 " Centrifugal Charging Pump Tests." MOVs VC 112B,C,D,E are stroked quarterly during PT-10." Safeguards Actuation Unit One."
5.
Valves listed under Category 5 have had their operators changed.
Prior to _
returning to service they were verified to stroke under accident differential pressure per TSSP 240-89 " Unit 1 Aux FH MOV Spring Pa'ck P.eplacement fest"..
6.
Valves listed under Category 6 are valves that are tested periodically at or..
near their accident differential pressure.
However,.the two valves are not independently tested.
The two valves are parallel valves that are tested one after the other where the SI8801A valve usually receives the full differential pressure and the SI8801B valve receives a lower differential pressure.
The following explanations describe the tests that are performed on these valves.
ISS 15.6.84 This is an ECCS full flow test that was performed during the last refueling outage on October 29, 1989 with satisfactory valve stroke results. This test subjected the valves to nearly full charging pressure upstream of-the closed valves.
The valves were stroked open and flow was discharged into a fully vented RCS.
These valves were not individually stroke tested against a full differential pressure as was accomplished during IEB 85-03 testing.
However, this test closely approximates the:
conditions which would exist during a large break LOCA.
PT-20 This periodic test is performed every month with full charging pump pressure upstream against closed valves.
The valves are then individually stroked during the test.
Isolation valves between the-SI8801 valves and the RCS are closed to prevent injection into the RCS. While full differential pressure is not obtained during this. test, successful valve strokes are accomplished on a monthly basis.
PT-10 This periodic test is performed each quarter to verify the j
safeguards actuation signal ~will actuate ~the valves to the safeguards position.
Approximate full charging pressure upstream of the valves is seen with the downstream SI8800 valves closed. While-there is no signift ant differential pressure across the' valves, the valves have satisfactorily stroked during these tests.
-ZINZEST/109 b
'x
.1
'o,
~-
The periodic tests described in Category 6 cannot be oerformed at this time due to new information regarding the individual cold leg injection isolation valves
.(SI8800A,B,C,D).- It has been determined during the racent investigation that the SI8800 valves are not on Zion's Environmental.0ualification list.- Although.
j there is an extremely low probability that a ria:;gn basis accident would occur.
q while the valves'are closed during the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> duration of these tests, the possibility exists that valves.SI8800A,B,C,D may not re-open under these conditions.
Commonwealth Edison is evaluating whether these valves should be i
on Zion Station's Environmental Qualification list.
l Considering the periodic tests that were performed on these valves, as discussed above, Commonwealth Edison considers these valves operable and 1
proposes to verify the torque switch settings during the next outage of 4
sufficient duration where conditions permit high head injection isolation.
- q In response to CAL RIII 90-011, item d, all Unit 2 IEB 85-03 valves will have their torque switch settings verified correct using VOTES testing or field Inspection prior to entering mode 2 (current estimated date' July 13, 1990).
Two valves which will not be verified at this time are SI8803A and S188038, which are out-of-service due to a modification that has eliminated their function. At this l
time only five of~ thirty five valves still need to be inspected.
These remaining _
valves will be inspected at plant conditions that are less susceptible to loss of Reactor Coolant Pump seal injection.
1 In response to CAL RIII 90-011, item e, Zion Station will provide an expected i
' completion date for IEB 85-03 re-evaluation by July 6, 1990.
As required by CAL RIII 90-Oll, Zion Station will provide our programs and schedules addressing potential discrepancies with all other! safety-related H0Vs by i
July.6, 1990.
j If any questions arise concerning this matter, please-direct them-to this l
office.
Very truly yours, [
,cfcfgnW R. A.jChrzanowski i
Nuclear Licensing Administrator i
RAC/es 1
cc:
C. Patel - NRR I
'i Zion Resident Inspector i
i i
i
.ZINZEST/109 J
- J
y 1
-Attachment Unit 1 IEB 85-01_Valygi Categorv #1 Valves that have been verified at, or reset to the proper torque switch setting Valves Descriotion 1
1 SH0101*
1H0V-SH0101 is the 18 Auxiliary feedwater Pump Service Hater supply Upstream Stop Valve.
This valve is normally closed and is remotely opened from the control room during auxiliary feedwater pump operation when the condensate storage tank reaches a low level. This valve is in series with 1H0V-SH0104.
SH0102 IMOV-SH0102 is the 1A Auxiliary Feedwater Pump Service Water Supply Stop Valve.
This valve is normally closed and is remotely opened 3
from the control room during auxiliary feedwater pump operation when-the condensate storage tank reaches a low level.
SH0103 1H0V-SH0103 is the 1C Auxiliary Fuedwater Pump Service-Hater Supply.
Upstream Stop Valve. This valve is normally closed and is remotely opened-from.the control room during auxiliary feedwater pump operation when the condensate storage tank reaches a low level.
This valve is in series with'lH0V-SH0105.
SW0104*
IMOV-SH0104 is the IB Auxiliary Feedwater Pump Service Water Supply.
Stop Valve.
This valve is normally closed and is remotely opened from the control' room during auxiliary feedwater pump operation when Lthe condensate' storage tank reaches a low level.
This valve is in series with 1HOV-SH0101.
(
VC8105*'
IMOV-VC8105 is the Charging Line Discharge Isolation Valve to the Regenerate Heat Exchanger.
This valve is'normally open, in series with VC-8106, and closes on a SI signal during an accident.
.VC8106 1H0V-VC8106 is the Charging Line Discharge Isolation Valve to the Regenerate Heat Exchanger.
This valve is normally open, in series with VC8105, and closes on a SI signal during an accident.
)
' caution carded to not be stroked closed for periodic surveillance untti torque l settings confirmed i
- de-energized open per Technical Specifications a
+ VOTES tested
.* torque switches were reset
.ZINZEST/109
gp *
's 3
5 Attachment Unit 1 IEB 85-03 Valves
.CaingaryJ2 Valves administrative 1y maintained in ESF actuated position
,f SI8800A',B',C',D' 1MOV-SIB 800A,B,C,L are the Loop A,B,C,D Charging Cold Leg E
Injections Valves.
These valves are normally open (safeguards position), and receive a wntirmatory open SI signal during an c
- accident.
t S18802*
IMOV-SI8802.is the Safety Injection Pump Discharge Common Cold
,v' Leg Isolation Valve.
This valve is normally open and deenergized F
per Technical Specifications; and it receives a confirmatory open SI signal during an accident.
This valve is stroked open:and
~ closed for surveillance testing during a refueling outage.per X
both Technical Specifications and Station Operating. department PT's.
SI8803A*,B*
IMOV-SI8803A,B are the Safety Injection Boron Injection-Tank-(BIT) Inlet Isolation. Valves.- These valves, have been i
administrative 1y removed from service (de-energized open) per a recent Technical Specification change that removed the requirement for maintaining a Boron Injection Tank with 20,000 ppm boric acid solution, c
SI8806*-
1MOV-SIB 806 is the Safety Injection Pumps Suction Isolation Valve-1 from the Refueling Hater Storage Tank (RHST)..This valve is.
.normally open and de-energized per Technical Specifications; and it receives a confirmatory open SI signal during an accident.
This valve is stroked open and closed for surveillance ~ testing-during a refueling outage per both Technical Specifications land Station Operating department PT's.
t SI8923A*
1MOV-SI8923A is the 1A Safety. Injection Pump Suction Isolation-Valve from.the Refueling Hater.-Storage Tank (RHST).
This valve is normally open (safeguards' position), and receives a confirmatory open SI signal during an accident.
SI8923B' IMOV-SI89238 is the IB Safety Injection Pump Suction Isolation Valve from the Refueling Hater Storage Tank-(RHST).
This valve
/F is normally open (safeguards pos'etion), and receives a l
confirmatory open SI signal during an accident.
SI9010A',B' 1MOV-SI9010A.B are the Safety Injection Pump's Cross-Tie Isolation Valves to the Cold Leg Discharge.
These valves are N
normally open (safeguards position), and receive a confirmatory open SI signal during an accident.
' caution carded to not be stroked closed for periodic surveillance until torque y
settings confirmed
- de-energized open per Technical Specifications
~
+ VOTES tested i
- torque switches were reset ZINZEST/.109 7
i
,, j ~
d
,1
I,..
i.
Unit 1 IEB 85-03 Valves
-l Cdagory 3 Valves governed by an operating procedure to ensure O differential pressure when stroked SH0105 1MOV-SH0105 is the 1C Auxiliary feedwater Pump Service Hater Supply Stop Valve.
This valve is normally closed and is remotely opened from the control room during auxiliary feedwater pump operation
.I when the condensate storage tank reaches a low level.
This valve is in series with IMOV-SH0103.
Cdegory_4._
Valves that are periodically tested at approximately the IEB 85-03 differential pressure, i
VC8110-1H0V-VC8110 is the Charging Pumps Recirculation Isolation' Valve in series with VC8111. This valve-is normally open,.and would be I
closed during a LOCA when RCS pressure decreases to 1250 psig upon i
loss of RCS subcooling.
VC8111-1MOV-VC8111 is the Charging Pumps Recirculation Valve in series with VC8110.
This valve is normally open, and would be-closed:
L during a LOCA when RCS pressure decreases to 1250 psig upon loss of j
RCS subcooling.
l q
VC1128.
1HOV-VC112B is the Charging' Pumps Suction Isolation Valve from the i
Volume Control Tank (VCT).
This valve is normally open in series:
with VC112C.and receives a close SI signal during an accident.
.j i
VC112C 1MOV-VC112C is the Charging Pumps Suction-Isolation Valve from'the' Volume control Tank (VCT).
This valve ~1s normally open, in series with VC112B and receives a close SI signal during an accident.
- j 1
l VC112D 1H0V-VC1120 is the Charging Pumps Suction Isolation Valve from the l
L Refueling Hater Storage Tank (RHST).
This valve is normally 1!
L' closed, in parallel with VC112E and receives an open-SI signal during~an accident.
L i
l' VC112E IM0V-VC112E is'the Charging Pumps Suction Isolation-Valve from the h
_ Refueling Hater Storage Tank (RHST).
This valve ~is normally closed in parallel with VC1120 and receives an open SI signal during an-i accident.
l 1
ZINZEST/109
Attachment Unit ! IEB 85-03 Valves 1
Category _.5_
New valves tested at IEB 85-03 differential pressure U
FH0050 AFH supply to IB SG throttle valves j
FH0051 AFH supply to IB SG throttle valves FH0052
'AFH supply to 1C SG throttle valves FH0053+
AFH supply to IC SG throttle valves FH0054 AFH supply to IA SG throttle valves FH0055 AFH supply to 1A SG throttle valves FH0056 AFW supply to ID SG throttle valves FH0057 AFH supply to ID SG throttle valves Category _6_
Valves that have_been periodically tested at or near accident differential pressure that are tested one after the other in a parallel alignment.
SI8801A,B 1H0V-SI8801A,B are the Safety Injection Boron Injection Tank (BIT)
Parallel / Discharge Isolation Valves.
These valves are normally closed, and receive an open SI signal during an accident.
' caution carded to not be-stroked closed for periodic surveillance until torque settings confirmed
- de-energized open per Technical Specifications j
+V0TES tested i
'l i
i ZINZEST/109