Forwards Excerpts from Pressurizer Control Test Performed During Hot Functional Testing.Confirmation Is Basis for Request for Deferral of Pressurizer Test ApprovalML20215D016 |
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Braidwood |
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Issue date: |
10/03/1986 |
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From: |
Tomashek C COMMONWEALTH EDISON CO. |
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To: |
Hickman NRC |
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Shared Package |
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ML20215D019 |
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References |
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86-736, NUDOCS 8610100580 |
Download: ML20215D016 (13) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 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 ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 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) ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 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) BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl 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 ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999 Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5 ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 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 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed 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) BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl 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 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999 Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5 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 05000457/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed1999-05-21021 May 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed 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 ML20206T3351999-05-17017 May 1999 Provides Written follow-up of Request for NOED Re Extension of Shutdown Requirement of TS Limiting Condition for Operation 3.0.3.Page 9 of 9 of Incoming Submittal Not Included ML20206N7861999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Braidwood Station. Rept Contains Info Associated with Stations Radiological Environ & Meteorological Monitoring Programs ML20206Q8521999-05-13013 May 1999 Submits Rept on Numbers of Tubes Plugged or Repaired During SG Inservice Insp Activities Conducted During Plant Seventh Refueling outage,A2R07,per TS 5.6.9 ML20210C7221999-05-0303 May 1999 Forwards Initial License Exam Matls for Review & Approval. Exam Scheduled for Wk of 990607 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 ML20206E3991999-04-29029 April 1999 Forwards 1998 Annual Environ Operating Rept & Listed Attachments Included in Rept.Without Encls ML20206C7901999-04-23023 April 1999 Provides Suppl Info Re Use of W Dynamic Rod Worth Measurement Technique,As Requested During 990413 Telcon.Rev Bars in right-hand Margin Identify Changes from Info Submitted by ML20206B3941999-04-21021 April 1999 Forwards Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors, for Byron & Braidwood Stations.Updated Info Re PCT for Limiting Small Break & Large Break LOCA Analysis Evaluations & Detailed Description of Errors ML20205S9621999-04-20020 April 1999 Responds to 981203 RAI Telcon Re SG Tube Rupture Analysis for Byron Station,Unit 2 & Braidwood Station,Unit 2.Addl Info & Subsequent Resolution of Issues Discussed During 990211 Telcon Are Documented in Encl ML20206B0821999-04-20020 April 1999 Requests to Reschedule Breaker Maint Insp for Either Wk of 990607 or One of Last Two Wks in Jul 1999,in Order to Better Accommodate Insp Activity 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 ML20206B0251999-04-14014 April 1999 Forwards Reg Guide 1.16 Rept for Number of Personnel & Person-Rem by Work Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions ML20205K3581999-04-0606 April 1999 Submits Request to Reschedule Breaker Maint Insp for Braidwood Nuclear Power Station for Either Wk of 990607 or One of Last Two Wks in Jul 1999 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) ML20210C7181999-03-30030 March 1999 Forwards Integrated Exam Outline Which Plant Submitting for Review,Comment & Approval for Initial License Exam Scheduled for Wk of 990607 ML20205E6401999-03-26026 March 1999 Forwards Proprietary Ltr Re Notification of Corrected Dose Rept for One Individual,Per 1997 Annual Dose Repts for All Comed Nuclear Power Facilities,Submitted 970430.Proprietary Info Withheld 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 ML20207J4321999-03-0808 March 1999 Forwards Braidwood Station ISI Outage Rept for A1R07, Per Requirements of ASME Section Xi,Article IWA-6200 ML20205C6861999-03-0404 March 1999 Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6741990-09-17017 September 1990 Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided ML20059K5081990-09-14014 September 1990 Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990 ML20064A3681990-08-24024 August 1990 Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA ML20064A3751990-08-24024 August 1990 Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept ML20059A3991990-08-15015 August 1990 Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program ML20058N0551990-08-0707 August 1990 Provides Supplemental Response to NRC Bulletin 88-008, Suppls 1 & 2.Surveillance Testing Performed Revealed No Leakage,Therefore,Charging Pump to Cold Leg Injection Lines Would Not Be Subjected to Excessive Thermal Stresses ML20056A3351990-08-0202 August 1990 Responds to NRC Bulletin 88-009 Requesting That Addressees Establish & Implement Insp Program to Periodically Confirm in-core Neutron Power Reactors.All Timble Tubes Used at Plant Inspected & 18 Recorded Evidence of Degradation ML20055J1221990-07-25025 July 1990 Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary ML20055J1261990-07-25025 July 1990 Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H0291990-07-17017 July 1990 Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990 ML20044A9621990-07-13013 July 1990 Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc ML20055G4631990-07-13013 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-456/90-08 & 50-457/90-08.Corrective Actions:Discrepancy Record for Cable Generated & Cable That Had Been Previously Approved for Use on Solenoid Obtained & Installed ML20044B1411990-07-12012 July 1990 Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request ML20044B2141990-07-11011 July 1990 Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification ML20044B2871990-07-0909 July 1990 Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original Submittal ML20044A7991990-06-29029 June 1990 Forwards Description of Change Re Design of Containment Hydrogen Monitoring Sys,Per 900517 Request.Util Proposing Alternative Design Ensuring Containment & Hydrogen Monitoring Sys Operability in Event of Power Loss ML20058K3521990-06-22022 June 1990 Requests Withdrawal of 900315 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Specs 3.8.1.1 & 4.8.1.1.2 to Clarify How Gradual Loading of Diesel Generator Applied to Minimize Mechanical Stress on Diesel ML20056A0361990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-456/90-10 & 50-457/90-11.Corrective Action:Valve 2CS021b Returned & Locked in Throttle Position & Out of Svc Form Bwap 330-1T4 Modified ML20043G5851990-06-0808 June 1990 Forwards Repts Re Valid & Invalid Test Failures Experienced on Diesel Generator (DG) 1DG01KB,1 Valid Test Failure on DG 2DGO1KA & 2 Invalid Test Failures Experienced on DG 2AGO1KB ML20043D3141990-06-0101 June 1990 Forwards Rev 18 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043E3141990-05-31031 May 1990 Withdraws 880302 Application for Amend to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,changing Tech Spec 4.6.1.6.1.d to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin,Due to Insufficient Available Data ML20043F4731990-05-30030 May 1990 Forwards Suppl to 881130 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Changes Requested Per Generic Ltr 87-09,to Remove Unnecessary Restrictions on Operational Mode Changes & Prevent Plant Shutdowns ML20043B7771990-05-23023 May 1990 Forwards Endorsement 9 to Nelia & Maelu Certificates N-108 & M-108 & Endorsement 8 to Nelia & Maelu Certificates N-115 & M-115 ML20043A9161990-05-16016 May 1990 Provides Advanced Notification of Change That Will Be Made to Fire Protection Rept Pages 2.2-18 & 2.3-14 ML20043C2811990-05-15015 May 1990 Responds to NRC 900416 Ltr Re Violations Noted in Insp Repts 50-456/90-09 & 50-457/90-09.Corrective Actions:Gas Partitioners Tested Following Maint During Mar 1990 & Tailgate Training Session Will Be Held ML20042G7111990-05-0707 May 1990 Responds to NRC Questions Re leak-before-break Licensing Submittal for Stainless Steel Piping.Kerotest Valves in Rh Sys Will Be Replaced in Byron Unit 2 During Next Refueling Outage Scheduled to Begin on 900901 ML20042F6851990-05-0404 May 1990 Requests Resolution of Util 870429,880202 & 0921 & 890130 Submittals Re Containment Integrated Leak Rate Testing in Response to Insp Repts 50-454/86-35 & 50-455/86-22 by 900608 ML20042F6771990-05-0303 May 1990 Advises NRC of Util Plans Re Facility Cycle 2 Reload Core. Plant Cycle 2 Reload Design,Including Development of Core Operating Limits Has Been Generated by Util Using NRC Approved Methodology,Per WCAP-9272-P-A ML20042E9111990-04-25025 April 1990 Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. ML20042F2681990-04-18018 April 1990 Provides Supplemental Response to Violation Noted in Insp Repts 50-456/89-21 & 50-457/89-21 Re Safeguards Info.Util Request Extension of 891010 Commitment Re Reviews of Plants. List of Corrective Actions Will Be Submitted by 900601 ML20042F0241990-03-28028 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML20012D8671990-03-21021 March 1990 Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date ML20042G4641990-03-20020 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Repts 50-456/90-02 & 50-457/90-02.Corrective Actions:Existing safety-related Temporary Alterations Will Be Reviewed to Determine Which Alterations Include Installation of Parts ML20012D8711990-03-19019 March 1990 Forwards Corrected No Significant Hazards Consideration to 890814 Application for Amends to Licenses NPF-72 & NPF-77 ML20012C0861990-03-14014 March 1990 Forwards Response to Insp Repts 50-456/90-03 & 50-457/90-03 on 900122-26.Encl Withheld (Ref 10CFR73.21) ML20012E9221990-03-13013 March 1990 Forwards Final Version of Action Plan for post-accident Sample Sys QC Program,Per Insp Repts 50-456/90-05 & 50-457/90-05 ML20012C5471990-03-12012 March 1990 Provides Results of Completed Util Reviews & Addresses Addl Info Requested by NRC Re 890317 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Change Tech Spec 4.5.2,supplemented on 890825 & 890925-27 Meetings ML20012C5061990-03-12012 March 1990 Forwards Braidwood Nuclear Station Unit 1 Inservice Insp Summary Rept,Interval 1,Period 1,Outage 1. ML20011F6211990-02-21021 February 1990 Forwards Revised PHOENIX-P/ANC Benchmark Scope to Replace Existing Ark & 2D Codes Used to Perform Neutronic Analyses for PWR Reload Designs.Codes Expected to Be Used in Dec 1990 for Cycle 3 Design Calculations ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20055D4121990-01-29029 January 1990 Forwards Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,For Review ML19354E1741990-01-22022 January 1990 Provides Current Status of Ds Breaker Insps for Plant Following Completion of Recent Unit 1 Refueling Outage & Advises That Remaining Ds Breaker Insps Will Be Completed by End of Upcoming Unit 2 Refueling Outage ML20006D9621990-01-22022 January 1990 Forwards Info Re Invalid Test Failure Experienced on Diesel Generators 1DG01KA & 1DG01KB,per Reg Guide 1.108 ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20011E7391990-01-16016 January 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp Repts 50-456/89-28 & 50-457/89-27.Corrective Actions:Maint Work Request Procedure Will Be Revised to Clarify Testing Performed within Nuclear Work Request Package ML20006A1641990-01-11011 January 1990 Forwards Info Describing Initial Use of Rod Worth Measurement Using Rod Exchange Technique,Per Sser 2 (NUREG-1002) 1990-09-17
[Table view] |
Text
-
l pe ektY J)o: so) Se - Ask October 3, 1986 bb '
STUP: 86-736 i
Dear Mr. Hickman:
MO At D. Smith's request I am sending you excerpts from the pressurizer control test done during Hot Functional testing. In the packet are:
- 1. The applicable pages of the test (pp 30 through 32)
- 2. A Package consisting of the: '
- a. The test Review Board Minutes (May 20, 1986)-
- b. The Joint Test Review Meeting Minutes (June 16, 1986)
- c. An addendum to the above (June 20, 1986)
- d. A Post Joint Test Review Meeting Minutes
- 3. The final test evaluation (Section 12, pp 1 through 20)
- 4. Tnso attachments to that evaluation, A & C. ,
Engineering has not accepted the analysis without re-confirming the spray valve set points. This confirmation is the basis of our request for deferral of the Pressurizer test approval.
If you have any questions concerning this material, please contact me, at 815-458-2801, ext. 2371.
C. J. Tomadhek Startup Superintendent Braidwood Station 1
(1731s/1.2) 8610100580 861003 6 PDR ADOCK 0500 A
\
y9
SwPT-RY-17
, Rt. vision 1 9.3 Pressurizer Pressure Control, Alarm, & Setpoint i Verification
- 4 One or two backup pressurizer heater banks may
- be kept on the ON position, if necessary to
- maintain pressurizer pressure.
- 9.3.l* **'FY the RCS is in hot standby (5571 10F, 2235 1 30 psig). v.s /- 35fh 9.3.lb Ensure that the following Pressurizar controls are in AUTO.
Group A Contactor ' n / 3 3*!A Group B Contactor . r~ / . # '! 72 O Group D Contactor Fuw/3b3[$
1RY455A PORV b r / 3 ' ~~ N 1RY456 FORV P. t t /3[t"f! if ILK-459 Level Control Lir / 3 [3 '[ fI, IPK-455A Pressure Control va / M!hf, c
IPK-455B Spray Control 1 Lpt>/J/.7;/ft. ,
IPK-455C Spray control 2 L 'tr/ 7[F &
"?(,?,/ 9.3.lc Record all parameter indications and recorders
. G, on Data Sheet 11.3. h/ 3 6 MjC 9.3.2 CLOSE the Pressurizer PORV Blocking Valves:
1RY8000A /1m / 3he!IC 1RY8000B r tw /- 85 Ow/
30 1216u AUTHORIZED FOR TESTING
~
BwPT-RY-17 s
. . Rsvision 1 9.3.3 Manually ENERGIZE all the Pressurizer Back-up Heaters to increase System Pressure.
/ 3 3? SG CAUTION
- DO NOT EXCEED A MAXIMUM ALLOWABLE PRESSURIZER HEATUP RATE OF 50*F IN ONE HOUR OR A COOLDOWN *
- RATE OF 100*F IM ONE HOUR. *
- e*********************************************
9.3.4 ENSURE the PRESSURIZER PRESSURE CHANNEL CONT.
SELECT switch is in CH455/CH456.
($1r.n / 33 9.3.5 RECORD the Przr. pressuie and the GRP C Htr amperage at which the Heaters GRP C are at O g minimum output. (Above normal Hot Standby psig)
Y IPI-455A N I Dsig s.... ..,, y m ,
J 2$
(2250 psig nominal) b.u.- /N!"l4#
GRP C HTRS (^ amps (min)
$s / '/.t/a l
9.3.6 RECORD the pressure and Grp C Htrs amperage at {
which the pressurizer Spray Flow is initiated.
IPI 455A 127 [ psig (Above Group C Mtr 1
cutout) (2260 psig nominal) b /3/~/2#
GRP C HTRS O amps (mi)1)
& f n 5/n
- O 31 ,
216u l AUTHORIZED FOR TESTING
.. _=
BwPT-RY-l'1
, . Rsvision 1 9 . 3 . ~1a After spray is verified, CLOSE the PRZR Spray Valves Block Valves and continue pressurization.
\
dY "T 4 23 @3 q l
. 1RYO22 Closed un-/NhlA t b r.~ '
- q. F' t 1RYO24 Closed Cm. / E$3d M i
- 9. 3 . ~1b Record the pressure when the spray valves are fully open IPI455A 27 IN psig (Above spray initiation) (2310 psig nominal) b1w/ 5 U4, #
- The next two steps could occur in reverse order.*
9.3.8 RECORD the pressure at which the "PZR PRESS CONT DEV HIGH" alarms (window 06D02 on IPM05J).
.., T SI2dG IPI-455A c' M ps{iyg (Above Spray Full Open psig)
(2310 psig nominal) kn'W &l['- W 9.3.9 RECORD the pressure at which the "PZR PRESS HIGH" (wt,dow 06C.02 on IPM05J) alarms.
IPI-456 0 3 l l'> osig (2285-2335 psig) l ?1w- / . A !.$. t l 9.3.10 RECORD the pressure at which the Power Operated l Relief Valves open.
1RY455A, IPI-455A S 2 i osig (Above " Cont Dev. High Alarm" psig) (2335 psig nominal)
?n / 3, '? g I 1RY456, IPI-456 2 33 osig (2310-2360 p ig) k.,. / 3'h W v- .
O !
32 1216u AUTHORIZED FOR TESTI
Pcg31 of 4 l'
/
O TRST REVIEW BONtD POST-TRST FOR BWPT-RY-17 (May 20, 1986) i Members: R. Riessen - Staff supervisor l M. Hottel - Tech Specialist i J. Webb - ops specialist D. Stroh - STR
, l i
1.
Test Change Record, comment by N. Hottel: The steps recorded for TCE I as 5.2.1 through 5.2.7 are in error, step 5.2.4,5,6 are not included.
This has no impact on the test.
No Resolution Required s
O 2.
/ $ection 6.4, comment by R. Riessen: Steps 6.4.1,2,3 were not signed off prior to section 9.1 being entered on 3/27/86. This comment also applies to step 7.4.2. This has no impact on the test.
No Resolution Required.
- 3. -
Step 4.2 and 4.4, casament by TRE: TRB is not able to evaluate the acceptance criteria values that are listed as " nominal" in these steps. The nominal values described in 4.2 and 4.3 were at the request of Project Engineering and do not conform to the startup Manual since they do ret have a set point and a prescribed expected range.
Acceptability of the nominal values recorded in the test for these acceptance criteria will have to be further evaluated by PRD.
l Resolution: [ggMRN M O
(1383s-2.8.254) l
- Page 2 of 4 d 4.
f Step 9.4.14, comment by R. Riessen: The deficiency written against the pressurizer level control are in,this step. Deficiency I was closed out based on the statement that it was tested in section 9.6 of nWPT-CV-11.
This does not appear to be an adequate reason for closing
. out the deficiency, when the deficient condition existed in this test.
If the controller were not tested in the same configuration in CV-11 sind under the same circumstances that the test conducted in RY-11, it appears this step in RY-17 may have to be retested.
Resolution: 4. ev.,7 da W & M4 6
& . 2%)PT-CV-17 /4 YW
.w" M O.e.p, * % ), Q 5.
& s ess,,4 hf=~ 'z'A W .
/ Step 9.4.2[accamentbyR.Riessen: 459A did not open and a deficiency was written against the discrepancy. However, a TCR was not written to bypass completion of this portion of the step. This step was subsequently retested satisfactorily.
No Resolution Required.
~ l O
6.
'. Step 9.3.23, comment by R. Riessen: The value recorded for IPI458ew m Data Sheet 11.3 is a write over and needs to be lined out, initialed and dated, and rewritten legibly, i
Resolution: [h M 8EZ j
! 7. Step 9.5.24, comment by M. Hottel: Page 2 of the SRL. does not describe method of simulation used for this step.
No Resolution Required.
l 0 -
(1383s-2.8.254) i 1
1
. ; *, F ge 3 of 4
- 8. /eficiencyRY-173 D
O< , comment by M. Hottel: This deficiency was written against 9.5.25 because the high temperature annunciator in this step did not come in. This was not a deficient condition in reality since the annunciator was suppose to ccme in at a higher temperature. The STE should have a TCE to bypass the verification for the annunicator coming in.
TC$ W k !& ~ N & % x=e!- A Resolution: M MEk d(co(, 74 A s ,ngt; wr- xY-/o & K m.ae> H r./o.vg
- 9. Deficiency RY-17H, comment by N. Hottel: This deficiency was written against 9.3.32 because backup heaters did not de-energize, however, step 9.3.32 is signed off which indicates that the heaters did de-energize. This step should not have been signed off. This is a ,
deficient condition, however, the deficiency is closed out. The explanation indicates that the level setpoint was not reached. The TCR should have been weitten to delete that portion of the step if it was not within the setpoint range.
Resolution: 7gg arg g O
Comments accurate, input provided to scheduling.
.&- i slaal tc.
Project Startup Date TRB Staff Supervisor i
4 O (1383s-2.8.254)
___.-,--..-+-.,---.,.__---.-..-..,,r, -w--,., _.---.,,-.,-.------%.--,.-,e.-.--%.----&, , ---- - - .-- - -e
- i Pcg3 4 of 4 x
Comments resolved as noted.
h / / 7.7M By g Test Ehg % r Date Resolution satisfactory, procedure approved, input provided to scheduling, wim Ploject Startup
/Date l'9-86 TER Staff Supervisor w
O I
O (1383s-2.8.254) .
' ~
~
~~
. .i ..
15 June, 1986 O TO: C.J. Tomashek FRON: -J.E. Boardman
Subject:
BwPT RY-17 Post Test Joint Test Review Meeting A Joint Test Review Noeting was held on June 11, 1986, to review the results of the above mentioned test. The JTR was attended by the following:
R. Latko- S.T.E.
P. Fay- S.T.E.
J. Boardman- On-Site PED E. Nagu- S.T.E.
M. Asztalos Westinghouse S.E.T.
J. Webb- Startup TRB J. Leider- On-Site PED i 1
M. Inserra- Startup TRB I D. Head- S.T,.E.
S. Zapinski- Station Tech Staff
() The following items were commented upon, and require resolution:
- 1. Address stop S.5.12, its test / retest chronology in the Engineering Evaluation.
- 2. Correct typos on page 5 and page 6 of the Engineering Evaluation. ,
- 3. Data collected in section S.3 concerning 1PT-455A Pressure control loop is not explicit, and therefore does NOT prove what it set out to prove. It is agreed that either additional information will be provided Cie.
pressure / time strip charts from the control board from the time of the test), or that ratesting will be performed.
- a. Loop 1PT4E5A needs complete calibration, and data on each component and its out of cal tolerence must be provided.
- b. If it is determined that additional data as in #3 above CANNOT be supplied, an AIR to ratest S.3 will i
be provided.
- c. The test engineers who ran the test state that the Engineering Evaluation as written to explain section S.3 is INCORRECT. It must be rewritten to reflect reality. ,
l i
.. ,e ..
.i s
PED letter BwPT-RY-17, Page 2
- 4. Collected data indicates both PORVs seem to be leaking (
after lifting and ressating. These must be relapped, and an AIR must be written to retest PORU leakage. The i STE indicates that these will be ratested in RYD79 retest. 1 Please resolve the above comments and submit the corrected test 1 together with the appropriate GP form to Dnsite PED for approval, i
YM
.E. Boardman- OnSite PED c: J.P. Leider I
G.T. Klopp R.E. Querio i E.E. Fitzpatrick O C.J. Tomashek E.E. Falb W.P. Poirier M.S. Inserra D. St. Clair R. Letko P. Fay E. Nagy M. Asztalos D. Head S. Zapinski l
l 1
O f
(
O 20 June, 1986 TO: C.J. Tomashek FROM: J.E. Boardman
SUBJECT:
Addendum to JTR letter dated 15 June, 1985, re BwPT RY-17 Post Test Joint Test Review Meeting In my letter referenced above, I failed to mention an additional item discussed at the JTR of 11 June, 1986. The following additional item '
requires resolution:
- 1. An AIR is needed to ratest PORU 455A once permanent tubing is installed for hot stroke time Copen) of less than 2 seconds.
O Please resolve this additional item before final submission of the
, tqst resulte,,for ap roval.
/
' dln. h . t ,
J E. Boardman 7f ]//ffQ 1
c: K. Brown J.P. Leider G.T. Klopp R.E. Querio E.E. Fitzpatrick l C.J. Tomashek E.E. Falb W.P. Poirier M.S. Inserra D. St. Clair R. Letko O
J- -
t..:. .
I 6 ,
I
.e-July 7, 1986 -
('"T_ ,
Stup #86-581
.Q
, TO: C. J. Tomashek FROM: Gene Nagy 4
SUBJECT:
BwPT-RY-17 Post Joint Test Review Meeting, Resolution of Comments I.
Resolution to J. E. Boardman letter dated 16 June 86:
- 1. Test / retest chronology for step 9.5.12 has been addressed
'in the engineering evaluation.
4
- 2. Typo's on page 5 & 6 are corrected (Engineering Evaluation) 3a. Loop 1PT-455 functions per design (as explained in the updated Engineering Evaluation, section 12.2.3). A post
' test calibration was performed during the week of 5-12-86. The post test cal consisted of inputting a signal at the sensor (i.e. pressure at IPT45J) and then verifying the indication at the points where data was collected. Results showed the pressure transmitters 1PT-455 & 456 were out of tolerance. Loop power supplies, isolators and indicators were within spec. The transmitters have been recalibrated and the out of tolerance condition addressed in section 12.2.3 of the l engineering evaluation. This is in accordance with the Braidwood Startup Manual. Therefore, a complete re-calibration is not requited.
3b. Strip charts and additional data has been provided (section 12.2.3), therefore, an AIR to retest section 9.3 is not required.
3c. The Engineering Evaluation for section 9.3 has been rewritten.
i
- 4. The PORV valves 1PCV-455A & 456 have been lapped. An AIR has been written to insure retest of these valves with respect to leakage.
II. Boardman letter dated 20 June 86
- 1. An AIR has been issued to retest PORV 455A after perminate turbine has been installed. The valve will be " hot stroked" in less than 2 seconds (open).
l l
[
I b
4
.. e .
t III. Westinghouse Ccwents
- 1. Westinghouse concerns have been addressed in the updated l version of Engineering Evaluation section 12.2.3.
Westinghouse (SET) now concurs that the Master pressure Controller responds such that the Spray Valves should preclude tht opening of PORV 455 during step load decreases between 10-50*4 power.
IV. TRB Coment incorporation All TRB coments from the meeting held on May 20, 1986 have c been addressed. No further action required.
i l
L E. {} Nagy Test Director 8M O R. Letko System Test Engineer (2566u/1.2/2.8.254)
.