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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety 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 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 ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
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PRXORXTY 1 (ACCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
I ACCESSION NB 9510170394 DOC. DATE: 95/10/06 NOTARIZED: NO DOCKET g FACIL:5 -397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 P AUTH.N E AUTHOR AFFILIATION PARRISH, Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION R Document Control Branch (Document Control Desk)
SUBJECT:
Requests review & approval of relief request for exam category C-G pump casing welds to support planning for Spring,1997 & Spring,1998 refueling outages. 0 DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE TITLE: OR Submittal: Inservice/Testing/Relief from ASM Code GL-89-04 NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CLIFFORD,J 1 1 INTERNAL 6 0 AEOD/SPD/RAB 1 1 EZLE CEN 1 1 NRR/DE/EMCB 1 1
~~EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DSIR/EIB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D 0
C M
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5DS (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 12
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,~
f l
P er
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 Docket No. 50-397 October 6, 1995 G02-95-208 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 SECOND 10-YEAR INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST FOR EXAMINATION CATEGORY C-G PUMP CASING WELDS
References:
Letter GO2-94-286, dated December 27, 1994, JV Parrish (SS) to NRC, "Second 10-Year Inservice Inspection Program Plan" This letter submits for NRC approval relief request 2ISI-15.
In accordance with 10CFR50,55a(g)(6)(i), the Supply System requests relief from performing a surface examination per ASME Section XI, 1989 Edition with no Addenda, Subarticle IWC-2400 of Examination Category C-G pumps'asing welds until the pumps are disassembled for maintenance. This relief request is based on the hardship it will cause the Supply System to disassemble the pumps for the sole purpose of performing the examinations. The relief request is provided as Attachment 1 and applies to the second 10-year Inservice Inspection Program Plan which was submitted with the referenced letter. Attachment 2 contains the ISI Program Plan Table 9.1.4 pages revised by this relief request.
Review and approval of this relief request is requested prior to October 1, 1996 to support planning for the Spring, 1997 and Spring, 1998 refueling outages.
Should you have any questions or desire additional information regarding this matter, please call me or D. A. Swank at (509) 377-4563.
Sincerely, J.. Parrish (Mail Drop 1023)
V President, Nuclear Operations DPR/dpr cc: LJ Callan - NRC RIV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston & Strawn JW Clifford - NRC
~. <'PC,Qg DL Williams - BPA/399 NRC Sr. Resident Insoector - 927N 9510170394 951006 PDR ADOCK 05000397 p PDR
.I ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-15 Welds for Which Relief is Requested'SME Section XI Examination Category C-G, Code item number C6.10, pressure retaining welds in pumps and valves.
I~den . No N D~~~cri >~in I~N ~ISI DI N .
RHR-P-2A RHR-P-2AC-1 PMP CAS/CIR WLD'MP C6.10 RHR-213 RHR-P-2AC-2 CAS/CIR WLD C6.10 RHR-213 RHR-P-2AC-3 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2AC-4 PMP CAS/CIR WLD C6, 10 RHR-213 RHR-P-2 AC-5 PMP CAS/CIR WLD C6,10 RHR-213 RHR-P-2AN-1 PMP NOZZLE WELD'MP C6.10 RHR-213 RHR-P-2 AN-2 NOZZLE WELD C6.10 RHR-213 RHR-P-2AN-3 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2AL-1 PMPCAS/LONG.WLD~ C6.10 RHR-213 RHR-P-2AL-2 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2B RHR-P-2BC-1 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2BC-2 PMP CAS/CIR WLD C6,10 RHR-213 RHR-P-2BC-3 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2BC-4 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2BC-5 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2BN-1 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2BN-2 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2BN-3 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2BL-1 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2BL-2 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2BL-3 PMPCAS/LONG. WLD C6.10 RHR-213 Pump casing circumferential weld Pump nozzle weld Pump casing longitudinal weld,,
Page 1
ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-15 RHR-P-2C RHR-P-2CC-1 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CC-2 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CC-3 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CC-4 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CC-5 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CN-1 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2CN-2 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2CN-3 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2CL-1 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2CL-2 PMPCAS/LONG.WLD C6,10 RHR-213 RHR-P-2CL-3 PMPCAS/LONG.WLD C6.10 RHR-213 HPCS-P-1 HPCS-P-1C-1 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-2 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-3 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-4 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-5 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-6 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-7 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1N-1 PMP NOZZLE WELD C6.10 HPCS-206-1 HPCS-P-1N-1 PMP NOZZLE WELD C6.10 HPCS-206-1 HPCS-P-1N-2 PMP NOZZLE WELD C6.10 HPCS-206-1 HPCS-P-1L-1 PMPCAS/LONG.WLD C6.10 HPCS-206-1 HPCS-P-1L-2 PMPCAS/LONG.WLD C6.10 HPCS-206-1 HPCS-P-1L-3 PMPCAS/LONG. WLD C6.10 HPCS-206-1 LPCS-P-1 LPCS-P-1C-1 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1C-2 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1C-3 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1C-4 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1C-5 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1N-1 PMP NOZZLE WELD C6.10 LPCS-208-1 LPCS-P-1N-2 PMP NOZZLE WELD C6.10 LPCS-208-1 Page 2
I ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-15 LPCS-P-1N-3 PMP NOZZLE WELD C6.10 LPCS-208-1 LPCS-P-1L-1 PMPCAS/LONG.WLD '6.10 LPCS-208-1 LPCS-P-1L-2 PMPCAS/LONG.WLD C6.10 LPCS-208-1 LPCS-P-1L-3 PMPCAS/LONG.WLD C6.10 LPCS-208-1 Section XI RequirementsSection XI, Table IWC-2500-1, Examination Category C-G, items C6.10 requires a surface examination of the weld and adjacent base metal, The examination can be performed from either the inside or outside of the pump casing. Per subarticle IWC-2400 "Inspection Schedule",
the required examinations in each Examination Category shall be completed each inspection interval in accordance with Table IWC-2412-1. This table requires that approximately one third of the items in each category be examined each inspection period (3 to 4 year intervals).
Code Requirement from Which Relief is Requested Relief is requested from the requirements of IWC-2400 for Examination Category C-G welds of pumps HPCS-P-1, LPCS-P-1, RHR-P-2A, RHR-P-2B, and RHR-P-2C. This requires approximately one third of the welds be examined each inspection period.
Basis for Relief Relief is requested on the basis that examination of these welds to the schedule required by IWC-2400 places a hardship on the plant. The subject pumps were designed prior to the requirement to perform Class 2 component examinations for inservice inspection. The upper flange for the pumps are located at floor level and the casings are embedded in a pump pit which does not allow access to the outside surface of the pumps. Due to the inaccessibility of the pumps it is impractical to perform the nondestructive examinations required by IWC-2400. The pump welds are accessible for examination from the pump internal surfaces. To meet the requirements of IWC-2400, the pump would require disassembly and removal of the pump impeller. At least one pump would be required to be disassembled each inspection period. A pump disassembly would result in a large expenditure of manhours and accompanying personnel exposure. This expenditure of manhours and personnel exposure for the sole purpose of performing nondestructive examination of the pump casings is considered a hardship. Figures 1, 2, and 3 illustrate the installation details for the pumps.
Page 3
ATI'ACHMENT 1 RELIEF REQUEST NO. 2ISI-15 Alternative Examinations When pumps HPCS-P-l, LPCS-P-1, RHR-P-2A, RHR-P-2B, and RHR-P-2C are disassembled for maintenance, to the degree that the welds are accessible for examination, the requirements of Code Examination Category C-G will be implemented for the disassembled pumps. The examination will be performed on accessible areas of the welds as defined in ASME Section XI Figure IWC-2500-8. Since pumps RHR-P-2A, RHR-P-2B, and RHR-P-2C are of the same design and perform similar functions only one of these pumps will be examined during the inspection interval (Section XI, Table IWC-2500-1, Examination Category C-G, note 1), ifthey are disassembled.
Justification for the Granting of Relief This relief request should be granted for the following reasons:
- 1. It is estimated to take at least 3 days to disassemble a pump and at least another 4 days to reassemble the pump. The general area dose on the inside of the pipe and pump is calculated to be 200 mrem/hr. This would result in a large expenditure of manhours and personnel dose to perform the nondestructive examination.
- 2. The accessible portions of the welds will be examined when the pumps are disassembled for maintenance. This examination of welds and base metal should detect generic degradation of the pump casing welds.
- 3. The pumps are routinely tested for operability per plant Technical Specifications and are subject to periodic system pressure tests per the requirements of ASME Section XI.
- 4. Pump operating conditions (i.e. flow, pressure) are available to the control room operators and coritrol room annunciators are provided to alert plant operators to abnormal operating conditions.
- 5. Plant procedures are in place for the operators to respond to abnormal pump conditions (i.e.
pump failure) and redundant safety systems exist if a pump were to become inoperable..
- 6. The casing welds for pumps RHR-P-2A, RHR-P-2B, and RHR-P-2C underwent a magnetic particle preservice inspection examination from the internal surface of the pumps prior to plant startup, The HPCS-P-1 and LPCS-P-1 pumps were not required to undergo a preservice inspection.
Page 4
0 ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-15 The measures taken by the alternative examinations and the routinely scheduled surveillances and testing identified above ensure plant safety is maintained.
Implementation Schedule This relief request will be implemented during the second inservice inspection interval.
Page 5
ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-15 NOTES:
- 1. THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE INSPECTION PROGRAMS ONLY.
- 2. CASING MATERIALS ARE SA516 GR.70 PLATE.
- 3. PREFIX HPCS-P-1 IS LEFT OFF EACH WELD NUMBER FOR CLARITY. HPCS-P-1 (E22-C001)
LEGEND:
C CIRCUMFERENTIAL WELD L LONGITUDINAL WELD N NOZZLE WELD REFERENCE ORAWINGS:
FABRICATION PACKAGE C-4 MPLiII E22-C001 N-3 C-5 GENERAL ARRANGEMENT CVliIi 02E22-06,7 C-6 DISCHARGE FLOOR EL. 422'-3 P \
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ORAWN OAtE CHECKED OAtE APPROVEO OAtE OWG NO. REV.
D.L EHR 9-1-95 ~~ > -~-'/ (MiA 'P/~~ HPCS-206-1 SH 1 OF 1 POS2-AV RO (8/94)
FIGURE 1<<LE ~E Page 6
ATTACHMENT I RELIEF REQUEST No. 2ISI-15 NOTES:
- 1. THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE PROGRAMS ONLY.
- 2. CASING MATERIALS ARE SA516 GR.70 PLATE. LPCS-P-1 (E21-C001)
- 3. PREFIX LPCS-P-1 IS LEFT OFF EACH WELD FOR CLARITY LEGEND C CIRCUMFERENTIAL WELD L LONGITUDINAL WELD N NOZZLE WELD REFERENCE DRAWINGS C-4 FABRICATION PACKAGE N-3 MPLg E21 -C001 GENERAL ARRANGEMENT CVIg 02E21-06,8 C-5 DISCHARGE FLOOR EL. 422'-3"
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' ' N-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM OWN DESCRIPTION CHK WELD AND COMPONENT IDENTIFICATION DIAGRAM 0 9-1 95 NEW ISSUE DRAWING LPCS-P-1 (E21-P001)
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ORAWN OATE CHECXEO BATE APPROYEO GATE O.L. EHR 9-1-95 i(lb~ '7- ~Vs ~ -,%>-. LPCS-208-1 SH 1 OF 1 0 PIIS2 AV RO (%94)
FIGURE 2 Page 7
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ATTACHMENT 2 Table 9.1.4 WHP-2 Washington Public Power Supply System Interval 2 ISI Program Plan and Schedule Revision 1 HPCS - High Pressure Core Spray (Grouped by Drawing No. and WalkdoHn Order)
Out. Rel.
Pg Identification No. Description Category Item No. Method Per. Out. Requnt. Code Freq. Req. Remarks Diagram No. HPCS-206 01 HPCS-P-1C-1 PHP CAS/CIR 'WLD C-G C6.10 SUR C 0 15 HPCS-P-1C-2 PMP CAS/CIR WLD C-G C6.10 SUR C 0 15 HPCS-P-1C-3 PMP CAS/CIR WLD C-G C6.10 C 0 15 HPCS-P-1C-4 PHP CAS/CIR WLD C-G C6.10 SUR c 0 15 HPCS-P-1C-5 PMP CAS/CIR WLD C-G C6.10 SUR C 0 15 HPCS-P-1C-6 PMP CAS/CIR WLD C-G C6.10 C 0 15 HPCS-P-1C-7 PMP CAS/CIR WLD C-G C6.10 C 0 15 HPCS-P.1N-1 PHP NOZZLE 'WELD C-G C6.10 C 0 15 HPCS-P-1H-2 PMP NOZZLE WELD C-G C6.10 C 0 15 HPCS-P-1N-3 PMP NOZZLE 'WELD C-G C6.10 SUR C 0 15 HPCS-P-1L-1 PMPCAS/LONG WLD C-G C6.10 SUR C 0 15 HPCS-P-1L-2 PMPCAS/LONG 'WLD C-G C6.10 C 0 15 HPCS-P-1L-3 PMPCAS/LONG WLD C-G C6.10 C 0 15 Page 48-1
ATTACHMENT 2 Table 9.1.4 WNP-2 Washington Public Power Supply System Interval 2 ISI Program Plan and Schedule Revision 1 LPCS - Low Pressure Core Spray (Grouped by Drawing No. and Walkdown Order)
Out. Rely Pg Identification No. Description Category Item No. Hethod Per. Out. Re@mt. Code Freq. Req. Remarks Diagram No. LPCS-208 01 LPCS-P-1C-1 PHP CAS/CIR WLD C-G C6.10 C 0 15 LPCS-P.1C-2 PHP CAS/CIR WLD C-G C6.10 SUR C 0 15 LPCS-P-1C-3 PHP CAS/CIR WLD C-G C6.10 SUR C 0 15 LPCS-P-1C-4 PHP CAS/CIR WLD C-G C6.10 SUR C 0 15 LPCS-P-1C-5 PHP CAS/CIR WLD C-G C6.10 SUR C 0 15 LPCS-P-1N-1 PHP NOZZLE WELD C-G C6.10 SUR C 0 15 LPCS-P-1N-2 PHP NOZZLE WELD C-G C6.10 C 0 15 LPCS-P-1N-3 PMP NOZZLE WELD C-G C6.10 C 0 15 LPCS-P-1L-1 PMPCAS/LONG 'WLD C-G C6.10 C 0 15 LPCS-P-1L-2 PMPCAS/LONG WLD C-G C6.10 C 0 15 LPCS-P-1L-3 PHPCAS/LONG WLD C-G C6.10 C 0 15 Page 62-i
ATTACHMENT 2 Table 9.1.4 WNP-2 Washington Public Power Supply System Interval 2 ISI Program Plan and Schedule Revision 1 RHR - Residual Heat Removal (Grouped by Drawing No. and Walkdown Order)
Out. Rely Pg Identification No. Description Category Item No. Method Per. Out. Requnt. Code Freq. Req. Remarks Diagram No. RHR-213 RHR-P-2AC-1 PMP CAS/CIR WLD C-G C6.10 SUR 2 C 0 15 RHR-P-2AC-2 PMP CAS/CIR WLD C-G C6.10 SUR 2 C 0 15 RHR-P-2AC-3 PMP CAS/CIR 'WLD C-G ~ C6.10 Z C 0 15 RHR-P-2AC-4 PMP CAS/CIR WLD C-G C6.10 2 C 0 15 RHR-P-2AC-5 PMP CAS/CIR WLD C-G C6.10 2 C 0 15 RHR-P-2AN-1 PMP NOZZLE WELD C-G C6.10 SUR Z C 0 15 RHR-P-2AN-2 PMP NOZZLE WELD C-G C6.10 SUR Z C 0 15 RHR-P-2AN-3 PMP NOZZLE WELD C-G C6.10 SUR 2 C 0 15 RHR-P-2AL-1 PMPCAS/LONG.WLD C-G C6.10 2 C 0 15 RHR-P-2AL-2 PMPCAS/LONG.WLD C-G C6.10 SUR Z C 0 15 RHR-P-2A(CS) RHR PUHP BASE F-A F1.40A VT-3 1 10 41 CE 10 RHR-P-2BC-1 PMP CAS/CIR WLD C-G C6.10 SUR 2 C 0 15 RHR-P-2BC-2 PMP CAS/CIR WLD C-G C6.10 SUR 2 C 0 15 RHR-P-2BC-3 PMP CAS/CIR WLD C-G C6.10 SUR Z C 0 15 RHR-P-2BC-4 PMP CAS/CIR WLD C-G C6.10 SUR Z C 0 15 RHR-P-2BC-5 PMP CAS/CIR 'WLD C G C6.10 SUR 2 C 0 15 Page 349
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ATTACHMENT 2 Table 9.1.4
'WNP-2 Washington Public Power Supply System Interval 2 ISI Program Plan and Schedule Revision 1 RHR - Residual Heat Removal (Grouped by Drawing No. and Walkdown Order)
Out. Rely Pg Identification No. Description Category Item No. Method Per. Out. Requnt. Code Freq. Req. Remarks Diagram No. RHR-213 RHR-P-2BN-1 PMP NOZZLE WELD C-G C6.10 SUR C 0 15 RHR-P-2BN-2 PMP NOZZLE WELD C-G C6.10 C 0 15 RHR-P-2BN-3 PMP NOZZLE WELD C-G C6.10 SUR C 0 15 RHR-P-2BL-1 PMPCAS/LONG.WLD C-G C6.10 SUR C 0 15 RHR-P-2BL-2 PMPCAS/LONG.WLD C-G C6.10 C 0 15 RHR-P-2BL-3 PMPCAS/LONG.WLD C-G C6.10 SUR C 0 15 RHR-P-28(CS) RHR PUMP BASE F-A F1.40A VT-3 1 10 41 CE 10 RHR-P-2CC-1 PMP CAS/CIR WLD C-G C6.10 SUR C 0 15 RHR-P-2CC-2 PMP CAS/CIR WLD C-G C6.10 SUR C 0 15 RHR-P-2CC-3 PMP CAS/CIR WLD C-G C6.10 SUR C 0 15 RHR-P-2CC-4 PMP CAS/CIR WLD C-G C6.10 C 0 15 RHR-P-2CC-5 PMP CAS/CIR WLD C-G C6.10 C 0 15 RHR-P-2CN-1 PMP NOZZLE WELD C-G C6.10 C 0 15 RHR-P-2CN-2 PMP NOZZLE WELD C-G C6.10 C 0 15 RHR-P-2CN-3 PMP NOZZLE WELD C-G C6.10 C 0 15 RHR-P-2CL-'I PMPCAS/LONG.WLD C-G C6.10 SUR C 0 15 RHR-P-2CL-2 PMPCAS/LONG.'WLD C-G C6.10 C 0 15 RHR-P-2CL-3 PMPCAS/LONG.WLD C-G C6.10 SUR = Z C 0 15 RHR-P-2C(CS) RHR PUMP BASE F-A F1.40A VT-3 1 10 41 CE 10 RHR-PB-213(L) LK PRES BNDRY C-H C7.50 VT-2 1 13 P CE 3 RHR-PB-213(H) HYDRO PRES BNDR C-H C7.60 VT-2 3 19 E CE 10 Page 350
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