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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7111999-10-26026 October 1999 Informs That Licensee 990330 Response to GL 97-06 Provides Reasonable Assurance That Condition of Licensee Steam Generator Internals Is in Compliance with Current Licensing Bases for Plant ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217J8631999-10-15015 October 1999 Forwards Insp Repts 50-361/99-12 & 50-362/99-12 on 990808- 0918.One Violation Identified Involving Inoperability of Emergency Diesel Generator in Excess of Allowed Outage Time ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20217B5981999-10-0606 October 1999 Informs That Staff Concluded That All Requested Info for GL 98-01, Year 2000 Readiness in Us Nuclear Power Plants, Provided for San Onofre Nuclear Generating Station,Units 2 & 3 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20216J2631999-09-28028 September 1999 Forwards Copy of Final Accident Sequence Precursor (ASP) Analysis of Operational Event at Songs,Unit 2,reported in LER 361/98-003 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212D9921999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of San Onofre.Nrc Plan to Conduct Core Insps & One Safety Issues Evaluation of MOVs at Facility Over Next 7 Months. Details of Insp Plan Through March 2000 Encl ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 ML20217B9011999-09-10010 September 1999 Responds to Which Addressed Concerns Re Y2K Issue & Stockpiling of Potassium Iodide (Ki) Tablets by Informing That San Onofre Nuclear Station Already Completed All Work Required to Be Ready for Y2K Transition ML20211K4191999-09-0303 September 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20211N0261999-09-0303 September 1999 Forwards Exemption from Certain Requirements of 10CFR50.44 & 10CFR50,app A,General Design Criterion 41 in Response to Util Request of 980910,as Supplemented 990719 & SER 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20211H3321999-08-30030 August 1999 Discusses 1999 Emergency Preparedness Exercise Extent of Play & Objectives.Based on Review,Nrc Has Determined That Exercise Extent of Play & Objectives Are Appropriate to Meet Emergency Plan Requirements ML20211J7151999-08-27027 August 1999 Forwards Insp Repts 50-361/99-09 & 50-362/99-09 on 990627- 0807.Two Violations Being Treated as non-cited Violations ML20211H8561999-08-23023 August 1999 Forwards SE Accepting Licensee 970625 Requests for Relief RR-E-2-03 - RR-E-2-04 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211J5821999-08-23023 August 1999 Corrected Copy of ,Changing Application Date from 970625 to 990625.Ltr Forwarded SE Accepting Licensee 990625 Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section XI as Listed ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N9721999-08-10010 August 1999 Responds to Appeal of FOIA Request for Documents Re Osre Issue.No Osre Visit Scheduled for Sept 1996 at Plant,Per 990722 Telcon.V Dricks,In Ofc of Public Affairs Should Be Contacted Re Osre Issue ML20210N0901999-08-0909 August 1999 Informs That 990312 Application Requested Amends to Licenses DPR-13,NPF-10 & NPF-15,respectively,being Treated as Withdrawn.Proposed Change Would Have Modified Facility TSs Pertaining to SONGS Physical Security Plan ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210B9891999-07-20020 July 1999 Ack Receipt of Transmitting Plant Emergency Plan Implementing Procedure SO123-VIII-1, Recognition & Classification of Emergencies ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209D8051999-07-12012 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, Issue on 950519 to Plant. NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20209F5681999-07-0909 July 1999 Forwards Insp Repts 50-361/99-08 & 50-362/99-08 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20196K6721999-07-0202 July 1999 Discusses 990628 Meeting Conducted in Region IV Office Re Status of San Onofre Nuclear Generating Station Emergency Preparedness Program.List of Attendees & Licensee Presentation Encl 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20210N9871999-07-0101 July 1999 Appeals Denial of Documents Re Sept 1996 Osre for San Onofre Nuclear Generating Station.Requests Copies of Sept 1996 Osre Rept & Any More Recent Osre Repts ML20209B3571999-06-28028 June 1999 Submits Response to GL 98-01,Suppl 1 Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701. Disclosure Encl ML20209B4831999-06-25025 June 1999 Requests NRC Approval of Six Relief Requests from ASME Code Requirement for Containment ISI Exams.Six Relief Requests, Provided as Enclosures 1-6,are as Listed ML20196A9801999-06-17017 June 1999 Responds to NRC 990420 RAI Re Proposed risk-informed Inservice Testing & GL 96-05 Programs at Songs,Units 2 & 3. Revised Pages to risk-informed Inservice Testing Program, Encl ML20195G8091999-06-14014 June 1999 Forwards Response to RAI Made During 990511 Telcon Re LARs 184 & 170 for SONGS Units 2 & 3.Amend Applications Proposed Restriction on Operation with Channel of RAS or Efas in Tripped Condition ML20195K4201999-06-11011 June 1999 Forwards LERs 99-003-00 & 99-004-00 Re Manual Esfas (Reactor Trips) Due to Problems with Main Feedwater Control.Two Events Are Being Reported Separately Because Actual Causes Are Considered Different & Independent of Each Other ML20195H1561999-06-10010 June 1999 Forwards MORs for May 1999 for Songs,Units 2 & 3.There Were No Challenges to Pressurizer Safety Valves for Either Unit 2 & 3 ML20195E4981999-06-0808 June 1999 Forwards Application for Amends 188 & 173 to Licenses NPF-10 & NPF-15 for SONGS Units 2 & 3,respectively.Amends Would Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 Re Small Break LOCA Charging Flow & Main Steam Safety Valve Setpoints ML20196L3191999-05-24024 May 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements for Songs,Unit 2.Rept Covers Period of 970916-990226 ML20207A3831999-05-24024 May 1999 Responds to NRC 990326 RAI on DG Srs.Proposed to Add Listed Sentence to TS Bases for SRs 3.8.1.7,3.8.1.12 & 3.8.1.15,as Result of Discussion with NRC During 990427 Telcon ML20211K4261999-05-18018 May 1999 FOIA Request for Documents Re San Onofre OI Repts 4-98-041, 4-98-043 & 4-98-045 ML20206S7161999-05-17017 May 1999 Forwards MORs for Apr 1999 for Songs,Units 2 & 3.There Were No Challenges to Pressurizer Safety Valves for Either Unit 2 or 3 ML20206N4711999-05-13013 May 1999 Provides Info Requested by NRC Re Reduced Pressurizer Water Vol Change Amends Application 172 & 158 for Songs,Units 2 & 3,respectively.Proposed Change Will Reduce Pressurizer Water Level Required for Operability ML20206M7791999-05-13013 May 1999 Informs NRC of Changes Being Made to Emergency Response Data Sys (ERDS) at SONGS Unit 3.Revised Page to ERDS Data Point Library Is Provided in Encl ML20206K6891999-05-11011 May 1999 Forwards Approved Amends to NPDES Permits CA0108073,Order 94-49 & CA0108181,Order 94-50 & State Water Resources Board Resolution ML20206M0681999-05-10010 May 1999 Submits Correction to Info Contained in Licensee to NRC Re Proposed TS Change Number NPF-10/15-475.Stated Info Was Incorrect in That Overtime Provisions Were Not Contained in TR at Time of Was Submitted ML20206H0451999-05-0404 May 1999 Forwards Annual Financial Repts for Listed Licensees of Songs,Units 1,2 & 3.Each Rept Includes Appropriate Certified Financial Statement Required by 10CFR50.71(b) ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML20206C5151999-04-29029 April 1999 Forwards 1998 Radiological Environ Operating Rept for Songs,Units 1,2 & 3. Annual Radiological Environ Operating Rept Covers Operation of Songs,Units 1,2 & 3 During CY98 & Includes Summaries Interpretations & Analysis of Trends ML20206E5851999-04-29029 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for SONGS Units 1,2 & 3. Also Encl Are Rev 13 to Unit 1 ODCM & Rev 31 to Units 2 & 3 Odcm 1999-09-29
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- Company March 11, 1999 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Docket Nos. 50-361 and 50-362 Deviation Request from the Southern California Edison Company's Commitment to 10 CFR 50 Appendix R, Section III.0 San Onofre Nuclear Generating Station Units 2 and 3.
Gentlemen:
J 1he Southern California Edison Company (SCE) requests a deviation from SCE's approved fire protection program as delineated in License Conditions 2.C (14) l for Unit 2 and 2.C (12) for Unit 3. The approved fire protection program i includes a commitment to the requirements of Section III.0 of 10 CFR 50 l Appendix R to the extent that it requires oil collection systems for reactor j coolant pumps (RCPs) to be capable of collecting lube oil from all potential unpressurized leakage sites, including oil fill lines. The request is for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. The description below and in the Enclosure is of the Unit 2 RCP remote oil fill line configurations. Unit 3 is similar in all material aspects.
Remote oil fill lines to the SONGS Unit 2 RCP lub3 oil systems were connected during the Cycle 10 refueling outage, which ended February 26, 1999. However, the covers are currnntly shut to prevent their use pending NRC approval of the enclosed deviation yequest. SCE plans to connect the Unit 3 remote oil fill lines during the upcoming Cycle 10 refueling outage. These lines, which extend from the 45 foot elevation walkway adjacent to the RCP motor to the oil f/
fill line connections on the RCPs, were installed to reduce radiation exposure /[
and personnel safety hazards to workers who periodicclly add oil to the RCP lube oil systems during power operation.
It is noted that these remote oil fill lines were connected and used prior to 1997. In 1997 these lines were disconnected following interactions with the NRC staff and an SCE evaluation. Since that time, however, the NRC staff has approved the use of similar remote oil fill lines for other nuclear plants.
9903170330 990311 ~
PDR ADOCK 05000361 F PDR P. O. Box 128 San Clememe, CA 92674 0128 949-368-7101 Fn 949-3684575
1
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Document Control Desk '
Therefo're, based upon recent interpretations of the NRC Staff, SCE has concluded that this deviation request for the remote oil fill lines is appropriate. The enclosed request provides justification for such a deviation. In. addition, the enclosed request shows that the configuration of the remote oil fill lines, as designed, does not adversely affect the ability l to achieve and maintain safe shutdown of the plant in the event of a single fire, as required by 10 CFR 50 Appendix R.
4 The fire protection rule (10 CFR 50.48 and 10 CFR 50 Appendix R) became effective on February 19, 1981. Appendix R was only directly applicable to nuclear plants that had operating licenses on or before January 1,1979.
However, prior to the granting of a low power license for Unit 3 and a full power license to operate Unit 2, the NRC determined that all future licensees (for licenses issued after January 1,1979) would also have to commit to meet specific portiens of Appendix R requirements. The SONGS commitment to the specific portions of Appendix R was incorporated into the fire protection program as delineated in License Conditions 2.C (14) for Unit 2 and 2.C (12) for Unit 3. Because Appendix R did not apply to SONGS Units 2 and 3 based on the date of the license, SCE's compliance with Appendix R is by a commitment to specific portions of Appendix R. Therefore, SCE is requesting a deviation from the approved fire protection progr 3m as delineated in License Conditions 2.C (14) for Unit 2 and 2.C (12)for Unit 3 rather than requesting an exemption from the rule.
SCE is requesting expedited approval of this deviation request because of oil leakage currently observed on RCP 2P004. The existing oil collection system is fully compliant with Appendix R Section III.0 requirements for all ,
ootential leakage points during normal operation, and therefore, is designed '
to capture and channel this leakage to the oil collection tanks. Also, pu t operational inspections have confirmed the effectiveness of the lube oil collectica system.
However, since the 2P004 leakage rate is different from previous experience, SCE will perform a pre-planned inspection of potential oil leakage points !
prior to any addition of oil. This inspection will take into account ALARA practices. Since the accumulated leakage to date is lest than three gallons, subsequent inspections may be necessary to fully ensure that no unacceptable leakage exists.
Oi. drain tank level accuracy is insufficient to verify the estimated three gallons leaked to date; however, it may be included in subsequent inspections.
The tank that 2P002 and 2P004 drain into will hold an excess capacity of greater than 90 gallons more than the contents of two RCP lube oil systems.
j
c e
Document Control Desk .
The enclosed request for deviation is based on a December 23, 1996, request from Arkansas Nuclear One. At the current rate of leakage from RCP 2P004 SCE will need to add oil on or before March 18, 1999. Therefore, NRC approval of this request is needed prior to that date to reduce personnel radiation exposure and eliminate a personnel safety fall hazard during this oil addition.
If you have any questions or would like additional information on this subject, please feel free to contact me or Jack Rainsberry at (949) 368-7420.
Sincerely, "W
Enclosure l cc: E. W. Merschoff, Regional Administrator, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 J. W. Clifford, NRC Project Manager, San Onofre Units 2 and 3
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ENCLOSURE REACTOR COOLANT PUMP REMOTE OIL FILL SYSTEM
RCP FILL Page 1 of 5 REACTOR COOLANT PUMP REMOTE OIL FILL SYSTEM Remote Oil Fill System Description As a result of oil consumption during power operations, the need arises to periodically add oil to the reactor coolant pump (RCP) motor lube oil lower reservoir. Previously, this was accomplished by transporting oil into the containment building cavities (inside the bic-shield) and adding the oil using ,
the oil fill connection on the motor. This resulted in bcth ALARA (an estimated I 600 mR per entry) and personnel safety concerns (e.g., heat stress, climbing unguarded structures, and stepping out onto a beam, while carrying and pouring thecontainersofoil).
In an effort to minimize radiation exposure to maintenance personnel and resolve the personnel safety concerns, a gravity feed, remote oil fill system was installed on each RCP motor. The system ccnsists of a covered hopper and stainless steel tubing at the 45' elevation adjacent to each RCP. The oil hopper is designed to accommodate up to a five gallon container of oil inserted upside down. After the container is inserted, the lid of the hopper will be closed. The oil container completely empties out while inside the hopper. So, there is no potential of spillage during filling. These fill hoppers are connected to each RCP motor lower reservoir fill connection - stainless steel tubing (3/8" Unit 2and1/2" Unit 3)andhighpressurecompressionfittings.
It is estimated that oil fill efforts using these hoppers will result in a reduced radiation exposure (from 600mR to n estimated 50 mR per entry) and reduced risk of physical injury.
These remote oil fill lines and hoppers are seismically mounted to remove any SeismicCategoryII/Iconcerns. The Stainless Steel (SS) tubing, the hopper, and the oil fill connection are all mounted on the motor to minimize the effect of any translated vibration and thermal movement. Not all of the SS tubing nce all of the hoppers are protected by an oil collection system. The connections to the motor lower reservoirs are protected by installed oil collection system pans. The maximum oil level in the reservoirs is lower than the oil fill connection.
These remote oil fill tubing runs are connected with high pressure compression fittings. Only one fitting per pg is not protected by an oil collection system. This type of fitting is hi aly 9 reliable, especially when used in low pressure or ventea applications, and not typically subject to leakage. The minimum slope of the installed tubing is 1/8" per 12" run. This ensures the system drains following each use and remains a dry system. (Twosketches depicting a typical remote oil fill line to a RCP are attached.)
The remote oil fill lines do not extend beyond the fire zone boundary where the RCP is located.
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Page 2 of 5 01l Fill Process With the above described remote oil fill system, oil can be safely added to the
! RCP motor lower oil reservoirs. During each oil fill, the appropriate increase )
in reservoir level will be observed using a. level indication system. In each case, the resultant indicated change in level will verify that the oil reaches j the reservoir. Other administrative controls, as discussed under Compensatory l l Measures, will be in place to ensure any potential leakage is identified and I eliminated.
Consequences of Remote Oil Fill Potential Leakage !
The routing of the remote oil fill lines, as described above, is from the side l of the RCP motor, under the grating, to the motor lower oil reservoir fill port.
The oil fill tubing is routed such that no leakage from the system could reach any fibrous blanket insulation located in the containment building. All insulation that potential leakage from the system could come into contact with is a stainless steel reflective type pipe insulation. The expected maximum temperature on this type of insulation is less than 200*F under worst case design conditions, and therefore, would not be an ignition source.
l The Unit 2 Containment Building is a reinforced concrete structure that houses the reactor, steam generators, reactor coolant pumps, reactor coolant system,
- and other required support systems. The building is divided into three (3) principal fire areas, two of which do not contain any safe shutdown equipment.
The fire area containing safe shutdown equipment and cables is comprised of fire zones 2-CO-15-1A, 2-C0-15-18, 2-CO-15-1C, and 2-C0-63-10. Fire zones 2-C0-15-1A and 2-C0-15-1B are the steam generator rooms. Fire zone 2-C0-15-1C is the area
! outside the steam generator on elevations 15, 30, and 45 feet. Fire zone
[ 2-CO-63-1D is the operating floor at elevation 63 feet six inches. All four
- fire zones are considered one fire area because of a number of unsealed floor l penetrations and the use of open metal grating as floors.
l Fire zones 2-CO-15-1A and 2-00-15-18, which contain RCPs, are the primary concern of this deviation request. The major in-situ combustibles located in fire zonas 2-CO-15-1A :Ind 18 are cable insulation and Reactor Coolant Pump (RCP) motor. lube oil located an the 45 foot elevation. Introduction of transient combustibles to the area is controlled by plant administrative procedures, and access is limited to the area during normal plant operation. Although these fire zones do not have zone wide fire detection, fixed temperature rate-of-rise heat detectors and a semi-automatic water spray system are located above the RCPs. In the unlikely event of a fire, the detectors will provide an alarm to the Control Rcom as well as the site Fire Department office to alert Operations to open the containment firewater isolation valve. In addition, manual fire suppression capability, consisting of portable extinguishers and hose stations, is available in adjacent fire zone 2-C0-15-1C.
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RCP FILL Page 3 of 5 The containment building is divided into fire areas for the purposes of evaluating the effects of fires. The zones were divided on the basis of clear space without intervening combustibles. The north half of the containment building outside the generator rooms contains cabling and equipment associated with safe shutdown that is separated from cabling and equipment ir, the south half of the containment building. The oil fill lines for thi. RCP motors are located in the steam generator rooms: fire zones 2-CO-15-1A (north) and 2-C0-15-1B (south). There are two RCPs in each steam generator room. The RCP remote fill tubing does not communicate outside the respective steam generator room. The effects of postulated oil loss inside the generator rooms during the oil fill evolution were specifically evaluated for each zone. Due to the separation of redundant components, the oil fill lines pose no threat to the safe shutdown capability.
Safe Shutdown Equipment Separation Safe shutdown equipment located in these fire areas includes the following:
- Pressurizer pressure and level instrumentation and associated cables i
The separatio: of these instruments and associated cables was previously I analyzed. The analysis demonstrated that for a fire in a Steam Generator I compartment, redundant instruments will not be affected and at least one I required channel will remain available for safe shutdown. The steam generator comparti ants block a direct path of fire between redundant cables as the cables J 1 eave the steam generator compartment. This separation, combined with the l physical barrier of the steam generator rooms during most of the cables' routing, makes it highly unlikely that a single fire will affect instrumentation j to both steam generators. !
Pressurizer pressure and level instr ents are mounted on the outside of the steam generator compartment:;. Cables from the pressurizer pressure and pressurizer level instrurentation are all routed independently inside containment. It is highly unlikely that a fire of sufficient magnitude will I occur that will affect all channels of pressurizer pressure and level l instrumentation; therefore, at least ora channel of pressurizer pressure and l
, level indication will remain available for safe shutdown.
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RCP FILL Page 4 of 5 Below, the effects of a potential fire from a leak occurring during oil fill are {
analyzed. Oil leaks, if not captured by the lube oil collection system, would tend to migrate to the containment floor where it would flow to the equipment drains under the RCPs. The temperature of the equipment in the area will remain
-significantly below the auto-ignition temperature. Currently, Mobil, SHC 626 (synthetic) oil, which has an auto-ignition temperature of 720*F and a flash point of 440'F is used. Fixed temperature rate-of-rise type heat detectors are installed over each RCP in the steam generator rooms. The detection system l alarms 'are in the Control Room and the Fire Department office. The I semi-automatic suppression system is designed to control the spread of fire, if it did occur. Additionally, manual fire suppression equipment is readily available for responding to a fire. I Administrative limits will be set at a maximum of three (3) gallons of oil per oil fill. This will limit the amount of oil that is not contained in the onlikely event of an' oil leak. Given the RCP oil remote fill system is not l pressurized, the size of the generator room, and the limited size of the i postulated fire (three gallons of oil), the potential for fire is minimized, and the occurrence of damage to redundant instrumentation channels outside the ,
generator room is not credible. ;
Due to system design (sloping lines that do not retain oil) and the process for j adding oil, the likelihood of an oil leak of three gallons is very remote.
Further, should a leak occur during filling, the amount of the oil leaked would l be much less than the contents from one RCP motor, which has been analyzed from a safe shutdown perspective and found to be acceptable. Therefore, in the unlikely event of a fire involving the maximum postulated lube oil leak from one RCP, the ability to achieve and' maintain safe shutdown is assured.
Compensatory Measures E
In order to minimize the potential for an oil fire due to a leak from the lines of the remote oil fill system that do not have an oil collection system, the following actions will be taken each time oil is added through this system:
Prior to each fill the remote oil fill lines will be visually inspected.
- Each remote oil fill will be limited to three gallons.
A level indicator (e.g., PMS computer) will be utilized to verify that the three gallons has reached the reservoir of the correct RCP motor (the oil level can be determined to within % qallon).
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. Subsequent to each fill the remote oil fill lines will be visually inspected for leakage.
. The total oil volume to be added will be limited to less than the amount calculated to result in an indicated reservoir level of 95*t.
- Should any oil leak, it will be removed prior to exiting the containment building.
- The remote oil fill lines will be inspected each outage in conjunction with the RCP lube oil system inspection.
If at any point during a remote fill operation it is determined that added oil is not reaching the desired location, the activity will be terminated, and the situation will be assessed. Personnel responsible for adding oil to the system also inspect for evidence of smoke following the oil fill. If smoke is detected, a fire brigade will be dispatched to the area. Fire suppression equipment is readily available for use in responding to such an event.
Conclusions The system is dry when not in use. When utilized, the Lapressurized system is limited to three gallons of oil per fill.
Although highly unlikely, oil that may leak from this system could fall onto metal reflective insulation protecting RCS piping. There is no fibrous material located in any postulated leak affected area. The maximum temperature of the surface of the SS insulation is well below the auto-ignition temperature of the oil. Therefore, no credible ignition source is present.
The design of the existing oil collection system and the RCP lube oil system, including the remote fill lines, ensure that oil leaking from the lube oil system is minimized and that any oil leakage is diverted to a safe location to prevent it from becoming a fire hazard.
Should a fire occur, no redundant trains of safe shutdown equipment will be affected due to the limited amount of oil available (three gallons) and the configuration of safe shutdown equipment.
Based on the above, the intent of 10 CFR 50 Appendix R (the ability to achieve and maintain safe shutdown of the plant in the event of a single fire) is accomplished without having a full oil collection system on the RCP remote oil fill system, l
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