Safety Evaluation of Topical Rept NEDC-32721P, Application Methodology for General Electric Stacked Disk ECCS Suction Strainer, Part 1.Concluded That Use of GE Hydraulics Design Method Acceptable for All Plants,With One Noted ExceptionML20203C184 |
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20217J0721999-10-18018 October 1999 Safety Evaluation of Topical Rept EMF-2158(P),Rev 0, Seimens Power Corp Methodology for Boiling Water Reactors, Evaluation & Validation of Casmo-4/Microburn-B2. Rept Acceptable for Licensing Evaluations of BWR Neutronics ML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary ML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217G0931999-10-15015 October 1999 Safety Evaluation of Topical Rept BAW-10179P,Rev 3, Safety Criteria & Methodology for Acceptable Cycle Reload Analysis. Rev 3 Found Acceptable & Accurately Include Conditions & Limitations for Applicability of References ML20217K0651999-10-15015 October 1999 Safety Evaluation of Topical Rept BAW-10193P, RELAPS5/MOD2-B&W for Safety Analysis of B&W-Designed Pressurized-Water Reactors. Rept Acceptable for Referencing in Licensing Applications ML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair ML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 ML20217J1101999-10-13013 October 1999 Safety Evaluation of Topical Rept TR-108727, BWRVIP Vessel & Internals Project,Bwr Lower Plenum Insp & Flaw Evaluation Guideline (BWRVIP-47). Rept Will Provide Acceptable Level of Quality for Exam of safety-related Components ML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217C1311999-10-0808 October 1999 Safety Evaluation Supporting Amend 153 to License DPR-3 ML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217B1641999-10-0505 October 1999 Safety Evaluation of Topical Rept BAW-10228P. Science. Rept Acceptable for Licensing Applications,Subject to Listed Conditions in Accordance with Fcf Agreement (Reference 4) ML20212M2141999-10-0505 October 1999 Safety Evaluation Concluding That Topical Rept EMF-2158(P), Rev 0,acceptable for Licensing Evaluations of BWR Neutronics Designs & Applications,As Per SPC Agreement (Ref 9) Subj to Stated Conditions ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20212J1301999-09-30030 September 1999 Safety Evaluation Concluding That Topical Rept WCAP-12472-P-A,Addendum 1, Beacon-Core Monitoring & Operations Support System, Acceptable for Licensing Applications Subj to Pertinent Restrictions ML20212J9141999-09-29029 September 1999 Safety Evaluation of Topical Rept TR-108724, BWRVIP Vessel & Internals Project,Vessel Id Attachment Weld Insp & Flow Evaluation Guidelines (BWRVIP-48) ML20212J9661999-09-29029 September 1999 Safety Evaluation of Topical Rept TR-107285, BWRVIP Vessel & Internals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dated Dec 1996.Rept Acceptable ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216F9831999-09-20020 September 1999 Safety Evaluation Supporting Amend 11 to License R-115 ML20216H9901999-09-20020 September 1999 Proposed Final Rept Impep Review of South Carolina Agree- Ment State Program 990712-16 ML20212D4471999-09-20020 September 1999 Safety Evaluation Supporting Amend 31 to License R-103 ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 1999-09-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:TOPICAL REPORT EVALUATION
MONTHYEARML20217J0721999-10-18018 October 1999 Safety Evaluation of Topical Rept EMF-2158(P),Rev 0, Seimens Power Corp Methodology for Boiling Water Reactors, Evaluation & Validation of Casmo-4/Microburn-B2. Rept Acceptable for Licensing Evaluations of BWR Neutronics ML20217G0931999-10-15015 October 1999 Safety Evaluation of Topical Rept BAW-10179P,Rev 3, Safety Criteria & Methodology for Acceptable Cycle Reload Analysis. Rev 3 Found Acceptable & Accurately Include Conditions & Limitations for Applicability of References ML20217K0651999-10-15015 October 1999 Safety Evaluation of Topical Rept BAW-10193P, RELAPS5/MOD2-B&W for Safety Analysis of B&W-Designed Pressurized-Water Reactors. Rept Acceptable for Referencing in Licensing Applications ML20217J1101999-10-13013 October 1999 Safety Evaluation of Topical Rept TR-108727, BWRVIP Vessel & Internals Project,Bwr Lower Plenum Insp & Flaw Evaluation Guideline (BWRVIP-47). Rept Will Provide Acceptable Level of Quality for Exam of safety-related Components ML20212M2141999-10-0505 October 1999 Safety Evaluation Concluding That Topical Rept EMF-2158(P), Rev 0,acceptable for Licensing Evaluations of BWR Neutronics Designs & Applications,As Per SPC Agreement (Ref 9) Subj to Stated Conditions ML20217B1641999-10-0505 October 1999 Safety Evaluation of Topical Rept BAW-10228P. Science. Rept Acceptable for Licensing Applications,Subject to Listed Conditions in Accordance with Fcf Agreement (Reference 4) ML20212J1301999-09-30030 September 1999 Safety Evaluation Concluding That Topical Rept WCAP-12472-P-A,Addendum 1, Beacon-Core Monitoring & Operations Support System, Acceptable for Licensing Applications Subj to Pertinent Restrictions ML20212J9661999-09-29029 September 1999 Safety Evaluation of Topical Rept TR-107285, BWRVIP Vessel & Internals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dated Dec 1996.Rept Acceptable ML20212J9141999-09-29029 September 1999 Safety Evaluation of Topical Rept TR-108724, BWRVIP Vessel & Internals Project,Vessel Id Attachment Weld Insp & Flow Evaluation Guidelines (BWRVIP-48) ML20216F4771999-09-16016 September 1999 Safety Evaluation of Topical Rept TR-108823, BWR Vessel & Internals Project,Bwr Shroud Support Insp & Flaw Evaluation Guidelines (BWRVIP-38).Requests That BWRVIP Be Reviewed & Resolve Issues & Incorporate Concerns in Revised BWRVIP-38 ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20212B2501999-09-0202 September 1999 Safety Evaluation of TR WCAP-14696, WOG Core Damage Assessment Guidance, Rev 1.Rept Acceptable ML20211K5711999-09-0101 September 1999 FSER by NRR Re BWR Vessel & Internals Project,Instrument Penetration Insp & Flaw Evaluation Guidelines (BWRVIP-49), for Compliance with License Renewal Rule (10CFR54).TR Acceptable ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20209H9571999-07-15015 July 1999 Safety Evaluation Accepting EPRI Rept TR-105696-R1, BWR Vessel & Intervals Project:Reactor Pressure Vessel & Internals Examination Guidelines (BWRVIP-03) Rev 1, ML20209F1571999-07-0808 July 1999 Safety Evaluation of Topical Rept TR-108695, BWR Vessel & Internals Project,Instrument Penetration Inspection & Flaw Evaluation Guidelines (BWRVIP-49). Rept Acceptable.Rept Demonstrates That Aging Effects of Rv Components Adequate ML20209F1261999-07-0808 July 1999 Safety Evaluation of Topical Rept TR-108709, BWRVIP Vessel & Internals Project Low Alloy Steel Vessel Materials in BWR Environment (BWRVIP-60). Rept Acceptable for Assessment of SCC Growth in BWR Low Alloy Steel Pressure Vessels ML20209D9651999-07-0707 July 1999 Safety Evaluation of Topical Rept WCAP-14750, RCS Flow Verification Using Elbow Taps at Wesstinghouse 3-Loop Pressurized Water Reactors. Changes to TS Bases Acceptable ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20196G6321999-06-15015 June 1999 Safety Evaluation of Topical Rept EMF-2087(P),Rev 0, SEM/PWR-98:ECCS Evaluation Model for PWR LBLOCA Application, Rept Acceptable ML20195J2681999-06-14014 June 1999 Safety Evaluation of Topical Rept TR-108726, BWR Vessel & Internals Project,Lpci Coupling Insp & Flaw Evaluation Guidelines (BWRVIP-42). Rept Acceptable for Insp of safety- Related LPCI Coupling Assemblies,Except Where Staff Differ ML20207H1521999-06-0909 June 1999 Safety Evaluation of Topical Rept TR-108708, BWRVIP Vessel & Internals Project,Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals (BWRVIP-44), Sept,1997.Rept Acceptable ML20207G4971999-06-0808 June 1999 Safety Evaluation Re Mods to TR CENPD-266-P-A, Application of Dit Cross Section Library Based on ENDF/B-VI. Rept Acceptable ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20207C7321999-05-26026 May 1999 Safety Evaluation of Topical Rept BAW-2248, Demonstration of Mgt of Aging Effects for Reactor Vessel Internals. Rept Provides Individual B&W Nuclear Power Plant Utility Owner with Technical Details for for License Application Renewal ML20195J2271999-05-25025 May 1999 Safety Evaluation of CE Owner Group Topical Rept CE NPSD-951 Rev 1,justifying, Reactor Trip Circuit Breakers Surveillance Frequency Extension ML20207A6251999-05-21021 May 1999 Safety Evaluation of TR WCAP-14449(P), Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection. Rept Acceptable ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206K7691999-05-0808 May 1999 Topical Rept Evaluation of CENPD-389-P, 10x10 Svea Fuel Critical Power Experiments & CPR Correlations:SVEA-96+. Rept Acceptable ML20206D5441999-04-28028 April 1999 Safety Evaluation of Topical Rept TR-107284, BWRVIP Vessel & Internals Project,Bwr Core Plate Insp & Flaw Evaluation Guideline (BWRVIP-25). Rept Acceptable for Insp & Flaw Evaluation of Subject safety-related Core Interal ML20206D4951999-04-26026 April 1999 Safety Evaluation Supporting Topical Rept BAW-2251, Demonstration of Mgt of Aging Effects for Rv ML20205L9441999-04-0808 April 1999 Safety Evaluation of Topical Rept CENPD-289-P, Use of Inert Replacement Rods in Abb C-E Fuel Assemblies. Rept Acceptable ML20205L9671999-04-0707 April 1999 Safety Evaluation of Topical Rept TR-108727, BWRVIP Vessel & Internals Project,Bwr Lower Plenum Insp & Flaw Evaluation Guideline (BWRVIP-47). Rept Found Acceptable Except Where Staff Conclusions Differ from BWRVIP ML20205F0251999-03-21021 March 1999 Safety Evaluation of Topical Rept TR-108727, BWRVIP Vessel & Internals Project Vessel Id Attachmant Weld Insp & Flaw Evaluation Guidelines. Rept Acceptable ML20207E3821999-03-0202 March 1999 Topical Rept Evaluation of SL-5159(P), Methodology & Verification of Gapp Program for Analysis of Piping Systems with E-Bar Supports. Staff Finds Topical Rept Acceptable for Referencing in Licensing Applications ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20203A2581999-02-0505 February 1999 Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE ML20203C1841999-02-0303 February 1999 Safety Evaluation of Topical Rept NEDC-32721P, Application Methodology for General Electric Stacked Disk ECCS Suction Strainer, Part 1.Concluded That Use of GE Hydraulics Design Method Acceptable for All Plants,With One Noted Exception ML20203A7461999-02-0202 February 1999 Safety Evaluation of Siemens Power Corp Topical Rept EMF-92-116(P), Generic Mechanical Design Criteria for PWR Fuel Design. Rept Acceptable ML20199L6651999-01-25025 January 1999 Topical Rept/Ser of BAW-10186P, Extended Burnup Evaluation. Rept Acceptable.Staff Finds That Improved Methodology Adequate & Acceptable for Fuel Reload Licensing Applications Subject to Listed Conditions ML20198G1851998-12-15015 December 1998 Safety Evaluation for Topical Rept WCAP-14572,rev 1, WOG Application of Risk-Informed Methods to Piping ISI Topical Rept ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195F7041998-11-17017 November 1998 Safety Evaluation Accepting Topical Rept NEDC-24154P, Supplement 1,for Referencing in Licensing Applications to Extent Specified & Under Limitations Delineated in Rept ML20195F7941998-11-17017 November 1998 Safety Evaluation of EPRI TR-106708 & TR-106893.Repts Found to Be Acceptable for Replacement &/Or Repair of BWRVIP Vessel & Internals Project,Internal Core Spray Components ML20195C6721998-11-10010 November 1998 Safety Evaluation of Topical Rept WCAP-15029, Westinghouse Methodology for Evaluating Acceptability of Baffle-Former- Bolting Distribution Under Faulted Load Conditions ML20155G3901998-11-0505 November 1998 Safety Evaluation of TR GENE-770-06-2, Addendum to Bases for Changes to Surveillance Test Intervals & Allowed Out-of- Svc Times for Selected Instrumentation Tss. Rept Acceptable ML20155G3031998-11-0505 November 1998 Safety Evaluation of TRs NEDC-30844, BWR Owners Group Response to NRC GL 83-28, & NEDC-30851P, TSs Improvement Analysis for BWR Rps. Rept Acceptable ML20155B6121998-10-28028 October 1998 Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable ML20154F0711998-10-0606 October 1998 SE of TR WCAP-14036,Rev 1, Elimination of Periodic Protection Channel Response Time Tests. Rept Acceptable ML20155G2611998-10-0505 October 1998 Corrective Page 9 of Safety Evaluation of TR WCAP-14036,Rev 1, Elimination of Periodic Protection Channel Response Time Tests. Typos Made in Original Rept Re Components Covered by Solid State Protection Sys Were Corrected 1999-09-09
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Attachment SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO TOPICAL REPORT NEDC-32721P, ENTITLED
" APPLICATION METHODOLOGY FOR THE GENERAL ELECTRIC STACKED DISK ECCS SUCTION STRAINER" GENERAL ELECTRIC COMPANY PARTl EVALUATION OF GENERAL ELECTRIC'S METHODOLOGY TO DETERMINE STRAINER HYDRAULIC PERFORMANCE
1.0 INTRODUCTION
By letters dated April 3,1997, and November 21,1997, the General Electric Company (GE) ;
submitted topical report NEDC-32721P, " Application Methodology for the General Electric l Stacked Disk ECCS Suction Strainer," to the Nuclear Regulatory Commission (NRC, the staff) for review. The methodologies described in this report are being used by multiple boiling-water reactor (BWR) licensees (i.e.,12 plants) as part of their resolution of concerns identified in NRC Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors." By facsimile dated August 18,1997, and letter dated March 10,1998, i the staff transmitted requests for additional information (RAls) to GE. GE responded to the staff RAls in a letters dated November 21,1997, and April 29,1998.
The GE topical report encompasses methodologies for two different types of analyses. The i first methodology is used to determine the head loss across the strainer for estimated debris i loadings. The second methodology is used to determine the structuralloads on the ECCS l penetrations, piping and strainers caused by hydrodynamic forces during an accident. These two methodologies are separate and distinct. Therefore, the staff has broken its review into two parts. This safety evaluation (SE) is Part I of the staff's evaluation of topical report NEDC-32721P. Part I provides the staff's evaluation of the methodology used to determine strainer performance (e.g., head loss across the strainer with assumed debris loadings) only.
Part ll of this safety evaluation will address the methodology to determine the structural loadings due to hydrodynamic forces during a accident. The hydrodynamic load methodology is still undergoing staff review.
2.0 DISCUSSION l
GE's topical report and RAI responses were evaluated by the staff's contractor, Los Alamos National Laboratory (LANL) and LANL's findings relative to GE's methodology for determining the head loss across GE stacked disk strainers are documented in a proprietary Technical Evaluation Report (TER) entitled " Technical Review of GE LTR NEDC-32721P: Application Methodology for GE Stacked-Disk ECCS Suction Strainer," dated December 23,1998. This SE does not contain proprietary information; however, LANL's TER (attached) does. LANL's TER is accordingly being withheld from the public document room.
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3.0 CONCLUSION
S Based on the staff's review of all relevant information including LANL's TER and GE's submittals, the staff has concluded that the testing program used by GE for verifying the hydraulic performance of the prototype GE strainer and validating GE's head loss correlation is acceptable. The staff notes that some of the test procedures are not considered to be prototypical because they do not exactly replicate post-LOCA conditions; however, the overall l- impact of these procedures on the measured head loss is considered to be insignificant. The l staff concludes that GE has taken adequate measures to ensure that test results are conservative. The test program provided valuable data that can be used to correlate the effect of flow velocity, strainer shape, debris loading and particulate-to-fiber ratio on head loss. The i only drawback of the GE test program noted by the staff is that it did not envelope the l parametric range that covers all the plant applications. In particular, much of the test data were obtained for low fiber loadings where the gaps between the strainer disks were not completely filled. This comment is applicable to all insulation types, especially when tested in conjunction l with sludge debris. This, in itself, is not a deficiency, and in fact, is often the case for many test ;
l programs where practical considerations influence the parametric range selected for testing. j Extending the test results over a narrow parametric range outside the test range is reasonable.
However, the staff believes that for one case (a plant with a sludge-to-fiber mass ratio in excess of those tested), the application of GE test data (or the correlation) would be inappropriate without additional testing. GE is conducting an additional test to address this concern.
GE adopted an empirical means for correlating the test data. GE's choice was to correlate l head loss in terms of superficial parameters (such as circumscribed velocity) that are easy to determine in plant applications. This approach raised questions regarding the generic applicability of the GE correlation, especit.by application of the correlation beyond the test l range. However, the staff believes that GE introduced margin which is sufficient to compensate for any deficiencies noted in the correlation. For example, GE recommended use of 1.0 (the maximum value it can reach) for the compression factor (f,) irrespective of flow rate. According to the test data, at a flow rate of 10,000 GPM the actual compression factor is approximately 0.75, which is 25% lower than the design value of 1.0. The staff concluded that this margin would allow GE to apply its correlation within a narrow range beyond the range for which the test data obtained. LANL also conducted independent analyses to evaluate the applicability of GE methodology to each of the plant applications cited in GE's submittals. These analyses used an updated version of the NUREG/CR-6224 head loss correlation which was modified to
! better predict the characteristics of the GE strainer geometry. The modified NUREG/CR-6224 L correlation was then applied to each plant specified in the GE submittals. Based on the results l of these calculations, the staff concluded that the use of GE's hydraulics design method is l acceptable for all the plants, with the one exception noted above. For the one exception, the i staff identified specific concerns relative to the application of the GE correlation. The staff is
! concerned about the applicability of the GE correlation to this plant because:
(1) neither the GE correlation nor the NUREG/CR-6224 correlations were tested to sludge-to-fiber ratios approaching the value for this plant (i.e., thin-bed effects), and
'(2) the controlling insulation in this case may be a different type of fibrous insulation for which no head loss data have previously been obtained. The staff concludes, therefore, that i
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GE's approach of validating its hydraulics methodology using head loss data from an additional test is the most prudent approach.
The staff also reached the following conclusions:
-(1) GE's use of bump-up factors, consistent with the guidance of NEDO-32686A " Utility Resolution Guidance for ECCS Suction Strainer Blockage" (URG), to account for miscellaneous debris is acceptable. l (2) GE's approach to estimate head loss contribution from reflective metallic insulation (RMI) i debris appears reasonatste; however, the staff notes that GE should ensure that NRC 1 comments provided Appendix K to the staff's safety evaluation report on the URG are properly reflected in any GE plant-specific analyses. Specifically, GE should not neglect the potential contribution of RMI debris to strainer head loss without supporting analyses i establishing .that RMI contribution is negligible. The staff was unable to verify the contribution to strainer head loss from RMI debris because GE did not provide information relative to the assumed RMI loadings for any of the plants using GE strainers.
Principal contributors: Rob Elliott, NRC D.V. Rao, LANL l l
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