Safety Evaluation Re Recommended Mod to Reg Guide 1.76, Tornado Design Basis for Advanced Light Water Reactor. Tornado Design Criteria in Table 2 Acceptable on Interim Basis for Advanced LWRs Until Reg Guide RevisedML20148L164 |
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03/25/1988 |
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Office of Nuclear Reactor Regulation |
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ML20148L161 |
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References |
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PROJECT-669A, RTR-REGGD-01.076, RTR-REGGD-1.076 NUDOCS 8804010192 |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20217Q7971998-05-0404 May 1998 Safety Evaluation Supporting Amends 227 & 201 to Licenses DPR-53 & DPR-69,respectively ML20128P4381996-10-0909 October 1996 Safety Evaluation Accepting Review of Cracked Weld Operability Calculations & Staff Response to NRC Task Interference Agreement ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20149H0671994-11-0404 November 1994 Safety Evaluation Supporting Amend 27 to Amended License R-103 ML20149F4151994-08-0404 August 1994 Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14) ML20149E8831994-08-0202 August 1994 Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water Sys ML20248C5731994-07-19019 July 1994 SER Step 1 Review of Individual Plant Exam of External Fire Events for Millstone Unit 3 ML20059J4591994-01-25025 January 1994 Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement ML20059H4991994-01-24024 January 1994 Safety Evaluation Accepting Revised Responses to IEB-80-04 Re MSLB Reanalysis ML20059J2491994-01-14014 January 1994 Safety Evaluation Supporting Amend 159 to License DPR-40 ML20059J1831994-01-14014 January 1994 Safety Evaluation Supporting Amend 160 to License DPR-40 ML20059F3921994-01-0707 January 1994 Safety Evaluation Approving Request for Relief from ASME Code Repair Requirements for Class 3 Piping,Per 10CFR50.55a (g)(6)(i) & GL 90-05 ML20059E0331994-01-0404 January 1994 Safety Evaluation Re Alternate Miniflow Sys Design & Operation Reassessment of Emergency Core Cooling Sys & High Pressure Injection ML20059D0931993-12-30030 December 1993 Safety Evaluation Accepting Conformance to RG 1.97 Rev 2 ML20059E2871993-12-30030 December 1993 Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively ML20059C3751993-12-29029 December 1993 Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402 ML20059C4161993-12-28028 December 1993 Safety Evaluation Granting Licensee Request to Withdraw 881202 Application for Proposed Amend to License DPR-21 ML20059D1771993-12-28028 December 1993 Safety Evaluation Supporting Amend 48 to License DPR-73 ML20058P1981993-12-16016 December 1993 Safety Evaluation Accepting Ground Response Spectra Utilized & Approaches Used in Development of Floor Response Spectra for Resolution of USI A-46 ML20058L6111993-12-13013 December 1993 Safety Evaluation Approving Second ten-year Interval Inservice Insp Request for Relief Re Use of IWA-5250 Requirements Listed in 1992 Edition of ASME Code ML20058L7031993-12-10010 December 1993 Safety Evaluation Supporting Relaxation of RG 1.97 Environ Qualification Requirements Re Pressurized Water Reactors Accumulator Pressure & Volume Instrumentation ML20058L2711993-12-0808 December 1993 Safety Evaluation Finding Overlay Repair of Weld 02C-F7 Acceptable & in Conformance W/Gl 88-01.Plant May Be Returned to Safe Operation ML20058N8021993-12-0808 December 1993 Safety Evaluation Approving Third 10-yr IST Program Requests for Pumps & Valves,Per 10CFR50.55a(f)(6)(i) & 10CFR50.55a(a)(3)(i) ML20058K2411993-12-0707 December 1993 Supplemental Safety Evaluation Supporting Structural Steel Thermal Growth Design Critera at Plant ML20058K1391993-12-0606 December 1993 Safety Evaluation Supporting Amend 193 to License NPF-1 ML20062K1041993-12-0606 December 1993 Safety Evaluation Supporting Amend 47 to License DPR-73 ML20058J1091993-12-0303 December 1993 Safety Evaluation Accepting Licensee 921228 Submittal of Suppl Response to GL 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping ML20058G9371993-12-0303 December 1993 Safety Evaluation Supporting Amend 158 to License DPR-40 ML20058H6281993-12-0202 December 1993 Safety Evaluation Granting IST Program Requests for Relief ML20058H8021993-12-0101 December 1993 Safety Evaluation Supporting Amend 70 to License DPR-21 ML20058H0221993-11-30030 November 1993 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements in PRR 15,per 10CFR50.55(a)(3)(i). Denies Pump Relief Request 14 ML20058G5171993-11-29029 November 1993 Safety Evaluation Supporting Amend 60 to License NPF-57 ML20058G2781993-11-29029 November 1993 Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv) ML20058G0561993-11-29029 November 1993 Safety Evaluation Granting Relief from Installation Requirements of Section Iii,Article 9 of 1968 Edition of ASME Boiler & Pressure Vessel Code for Plant ML20058G2981993-11-29029 November 1993 Safety Evaluation Supporting Amends 151 & 139 to Licenses DPR-39 & DPR-48 ML20058F7921993-11-29029 November 1993 Safety Evaluation Supporting Amend 10 to License R-59 ML20058G2141993-11-29029 November 1993 Safety Evaluation Accepting Category 3 Qualification in Lieu of Category 2 Qualification for post-accident Monitoring of SIT Volume & Pressure ML20058F6661993-11-24024 November 1993 Safety Evaluation Accepting Licensee Proposed Use of New DG as Alternate AC Power Source for Coping W/Sbo Subject ML20058F1151993-11-23023 November 1993 Safety Evaluation Supporting Amends 170,69,169 & 86 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20058F5951993-11-22022 November 1993 Safety Evaluation Supporting Amend 157 to License DPR-40 ML20058F3441993-11-22022 November 1993 Safety Evaluation Concurring W/Contractor Findings Presented in Technical Evaluation Rept EGG-RTAP-10816, Evaluation of Utility Responses to Suppl 1 to NRC Bulletin 90-01;Big Rock Point ML20058B1241993-11-19019 November 1993 Safety Evaluation Accepting Proposal to Leak Rate Test SI Tank Outlet Check Valves by Using Leak Test Method Described in OM-10,Paragraph 4.2.2.3(c) ML20058F5641993-11-19019 November 1993 SE Accepting Util 930305 Response to NRC Bulletin 90-01, Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20058A3041993-11-19019 November 1993 Safety Evaluation Re Accumulator Pressure & Vol Instrumentation of Reg Guide 1.97 Environ Qualification Requirements,Per Generic Ltr 82-33.Category 3 Qualification of Instrumentation Acceptable ML20058C7491993-11-18018 November 1993 Safety Evaluation,Authorizing Alternative,On One Time Basis Only,W/Conditions That Licensee Perform Volumetric Exam of nozzle-to-vessel Welds During First Refueling Outage of Third 10-yr Insp Interval ML20058A3661993-11-17017 November 1993 Safety Evaluation Allowing Accumulator Level & Pressure Monitoring Instrumentation to Be Relaxed from Category 2 to Category 3 & Allowing Commercial Grade Instruments to Be Used,In Ref to GL 82-33 & Reg Guide 1.97 1999-02-05
[Table view]Some use of "" in your query was not closed by a matching "". Category:TEXT-SAFETY REPORT
MONTHYEARML20216G0111999-09-30030 September 1999 Year 2000 Readiness in U.S. Nuclear Power Plants ML20206N2191999-04-30030 April 1999 Operator Licensing Examination Standards for Power Reactors ML20205A5291999-03-31031 March 1999 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1998.(White Book) ML20211K2851999-03-31031 March 1999 Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance ML20205A5991999-03-31031 March 1999 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1998.(White Book) ML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML20203D0541999-01-31031 January 1999 Fire Barrier Penetration Seals in Nuclear Power Plants ML20155A9281998-10-31031 October 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1998.(White Book) ML20154C2081998-09-30030 September 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,January-March 1998.(White Book) ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20203A1521998-07-31031 July 1998 Assessment of the Use of Potassium Iodide (Ki) as a Public Protective Action During Severe Reactor Accidents.Draft Report for Comment ML20153D3371998-07-31031 July 1998 Assessment of the Use of Potassium Iodide (Ki) as a Public Protective Action During Severe Reactor Accidents.Draft Report for Comment ML20236S9771998-06-30030 June 1998 Knowledge and Abilities Catalog for Nuclear Power Plant Operators.Pressurized Water Reactors ML20236S9681998-06-30030 June 1998 Evaluation of AP600 Containment THERMAL-HYDRAULIC Performance ML20236S9591998-06-30030 June 1998 Knowledge and Abilities Catalog for Nuclear Power Plant Operators.Boiling Water Reactors ML20217Q7971998-05-0404 May 1998 Safety Evaluation Supporting Amends 227 & 201 to Licenses DPR-53 & DPR-69,respectively ML20247E3951998-04-30030 April 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1997.(White Book) ML20217F3801998-03-31031 March 1998 Risk Assessment of Severe ACCIDENT-INDUCED Steam Generator Tube Rupture ML20202J3051997-11-30030 November 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1997.(White Book) ML20197B0431997-11-30030 November 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1997.(White Book) ML20211L2931997-09-30030 September 1997 Aging Management of Nuclear Power Plant Containments for License Renewal ML20210K7801997-08-31031 August 1997 Topical Report Review Status ML20149G9431997-07-31031 July 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,January-March 1997.(White Book) ML20140J4301997-05-31031 May 1997 Safety Evaluation Report Related to the Department of Energy'S Proposal for the Irradiation of Lead Test Assemblies Containing TRITIUM-PRODUCING Burnable Absorber Rods in Commercial LIGHT-WATER Reactors ML20210R2131997-05-31031 May 1997 Final Safety Evaluation Report Related to the Certification of the System 80+ Design.Docket No. 52-002.(Asea Brown Boveri-Combustion Engineering) ML20140F0801997-05-31031 May 1997 Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design.Supplement No. 1.Docket No. 52-001.(General Electric Nuclear Energy) ML20141J9391997-04-30030 April 1997 Safety Evaluation Report Related to the Renewal of the Operating License for the Research Reactor at North Carolina State University ML20141C2411997-04-30030 April 1997 Circumferential Cracking of Steam Generator Tubes ML20141A5791997-04-30030 April 1997 Proposed Regulatory Guidance Related to Implementation of 10 CFR 50.59 (Changes, Tests, or Experiments).Draft Report for Comment ML20137A2191997-03-31031 March 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1996.(White Book) ML20135D5711997-01-31031 January 1997 Operator Licensing Examination Standards for Power Reactors ML20134L3631997-01-31031 January 1997 Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance.Draft Report for Comment ML20134L3601997-01-31031 January 1997 Standard Review Plan on Antitrust.Draft Report for Comment ML20138J2461997-01-31031 January 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1996.(White Book) ML20133E9161996-12-31031 December 1996 License Renewal Demonstration Program: NRC Observations and Lessons Learned ML20149L8261996-10-31031 October 1996 Reactor Pressure Vessel Status Report ML20135A4981996-10-31031 October 1996 Historical Data Summary of the Systematic Assessment of Licensee Performance ML20128P4381996-10-0909 October 1996 Safety Evaluation Accepting Review of Cracked Weld Operability Calculations & Staff Response to NRC Task Interference Agreement ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20128Q0761994-11-0404 November 1994 Coordinating Group Evaluation,Conclusions & Recommendations ML20149H0671994-11-0404 November 1994 Safety Evaluation Supporting Amend 27 to Amended License R-103 ML20149G4281994-09-28028 September 1994 NRC Perspectives on Accident Mgt, Presented at 940928 Severe Accident Mgt Implementation Workshop in Alexandria, VA ML20149F7581994-08-25025 August 1994 Topical Rept Evaluation of WCAP-13864,Rev 1, Rod Control Sys Evaluation Program ML20149F4151994-08-0404 August 1994 Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14) ML20149E8831994-08-0202 August 1994 Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water Sys ML20248C5731994-07-19019 July 1994 SER Step 1 Review of Individual Plant Exam of External Fire Events for Millstone Unit 3 ML20059J4591994-01-25025 January 1994 Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement ML20059H4991994-01-24024 January 1994 Safety Evaluation Accepting Revised Responses to IEB-80-04 Re MSLB Reanalysis 1999-09-30
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SAFETY EVALUATION BY TH,E OFFICE OF NUCLEAR REACTOR REGULATION OF REC 0!94 ENDED MODIFICATION TO THE R.G. 1.76 TORNADO DESIGN BASIS FOR THE ALWR
1.0 INTRODUCTION
EPRI proposed that the tornado design of the Advanced Light Water Reactor (ALWR) be based upon the ANSI-ANS 2.3-1983 standard. However, the staff has not accepted the ANSI document as a replacement for R.G. 1.76, "Design Basis Tornado For duelear Power Plants," because the ANSI design parameters are largely based upon subjective judgement. However, a considerable quantity of tornado data is now available that was not available when R.G.
1.76 was developed. The following evaluation is based upon R.G. 1.76 methodology, using the new data.
2.0 EVALUATION Regulatory Guide 1.76 has been utilized since 1974 by industry and the staff. The Guide provides a regional breakdown of design basis tornadoes (DBT) for the contiguous United States and it includes the following guidance:
"1. Nuclear power plants should be designed to withstand the Design Basis Tornado (DBT). The values of the parameters specified in Table I for the appropriate regions of Figure 1 (in R.G. 1.76) are generally acceptabic to the Regulatory staff for defining the DBT for a nuclear power plant. Sites located near the general boundaries of adjoining regions may involve additional consideration.
- 2. If a DBT proposed for a given site is characterized t
by less conservative values fo: the parameters than the regional values in Table I, a comprehensive analysis should be provided to justify the selection of the less conservative design basis tornado."
Mf0Q92880325 669 PDR,
TABLE I - DESIGN BASIS TORNADO CHARACTERISTICS Radius of Translational Maximum Maximum Rotational Speed (mph) Rotational Pressure Rate of Winds)egd eed Speed Pressure Region (mpi) Sp(mph) Maximum Minimum b
(feet) Drop)
(psi Drop (psi /sec)
I 360 290 70 5 150 3.0 2.0 ZI 300 240 60 5 150 2.25 1.2 ZII 240 190 50 5 150 1.5 0.6
- The maximum wind speed is the sum of the rotational speed component and the maximum translational speed component.
b The minimum translational speed, which allows maximum transit time of the tornado across exposed plant features, it to be used whenever low travel speeds (maximum transit time) are a limiting factor in the design of the ultimate heat sink. The ultimate heat sink is that complex of water sources, including associated retaining structures, and any canals or conduits connecting the sources with, but not including, the intake structures of nuclear reactor units. Regulatory Guide 1.27 (Safety Guide 27), "Ultimate Heat Sink," describes a basis that may be used to implement General Design Crite with regard to the ultimate heat sink.,rion 44 of Appendix A to 10 CFR Part 50 The technical basis for R.G. 1.76 was presented in WASH 1300, "Tech-nical Basis for Interim Regional Tornado Criteria." Due to the fact that very little area specific data on the damage areas and tornado intensity was available, generalized conservative estimates of these parameters were utilized in the development of the DBT. Since the publication of WASH 1300, the dational Severe Storms Forecast Center (NSSFC) has developed a data base which provides specific information when available on the damage areas, and intensity of the tornadoes which have occurred in the U.S. since 1950. The majority of the tornadoes that have occurred have been characterized by damage area and tornado intensity.
Battelle Memorial Institute, Pacific Northwest Laboratories (PNL) was awarded a contract to reevaluate the viability of R.G.1.76, utilizing the new data and whatever other data were available. PNL conpleted its study and the results were published in NUREG/CR-4461, "Tornado Climatology of the Contiguous United States," dated May 1986. At the heart of this study is the tornado data tape prepared by the NSSFC with thirty years of data, 1954 through 1983. This data tape contains the data for the approximate 30,000 tornadoes that occurred during the thirty year period.
The contractor compared its analysis of the thirty years of data with -
the findings in WASH-1300. Based on this comparison the contractor made the following findings:
"Revisions to the WASH-1300 methodology for estimating maximum wind speeds, tornado areas and intensities have been proposed. These revisions include the use of the expected tornado area in computation of strike probability as is done in the TORNADO code, which is used by the NRC staff; use of affected areas rather than number of occur-rences in computation of conditional probabilities of tornado intensities; use of a Weibull rather than a log-normal form to represent the intensity distribution; and use of regional intensity distributions in the estimation of design speeds.
Using the tevised method logy, the tornado strike probabil-itiesrangefromngr]inthecentralUnitedStates.yr4 for much Theof the western United Sta,tes to about 10 yr 10' yr-1 wind speeds estimated using local strike probabilities and regional intensity probability distributions range from less than 153 mph to 332 mph. These wind speed estimates are 50 to 100 mph lower than the speed estinates presented in WASH-1300 and Regulatory Guide 1.76 for most of the United States. On the basis of this analysis, it would appear to be reasonable to reduce tornado design basis wind speeds to 200 mph for the United States west of the Rocky Mountains and to 300 mph for the United States east of the Rocky Mountains."
The staff has reviewed the contractor's study and found agreement with the proposed revisions to the WASH-1300 methodology but believes that, in order to take into account uncertainties in the data base and analyses, the upper 90% strike probability confidence level should be utilized for estimating the probability of tornado occurrence. In keeping with the R.G. 1.76 regulatory position which allows for lessening of the DBT based upon a comprehensive analysis to justify less conservative DBT parameters, the staff concluded that the 10'7/yr probability of occurrence at the upper 90% confidence level from the contractor report may be utilized as the DBT. Fig. 1, which is identical to Figure 30 in NUREG/CR-4461, shows the associated wind speed by 5-degree latitude / longitude sectors throughout the United States. These sectors may be assigned to four regions (see Figure 2), which can be characterized by the following DBT parameters:
n TABLE II - DESIGN BASIS TORNADO CHARACTERISTICS Radius of Maximum Maximum Rotational Maximum Rotational Pressure Rate of Winds)egd eed Translational Speed Pressure Region (mp1) Sp(mph) Speed (mph) (feet) Drop)
(psi Drop (psi /sec) 1 330 260 70 150 2.4 1.7 II 300 240 60 150 2.0 1.2 78I 220 170 50 150 1.0 0.5 IV 200 160 40 150 0.9 0.3 a
When a plant site falls near, or on, boundary lines separating two or three velocity zones, either (1) the higher of the two or three regional wind ;
velocities should be used or, (2) the lower of the two or three wind velocities !
may be used with appropriate justification (see Figure 2 for example).
3.0 CONCLUSION
Based on its review described above, the staff concludes that the tornado design criteria in Table II and Figure 2 are acceptable on an interim basis for ALWRs until such time as R.G.1,76 is revised.
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FIGURE 1 Wind Speeds (mph) with a 10 7 Probability of j (Fig. 30 from Occurence Estimated from the Upper End of the l NUREG/CR4461) 90% Strike Probability Confidence Interval l r
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Figure 2 Maximum Wind Speed is indicated for each of 4 regions of the United States. The circled area illustrates boundaries where a lower wind speed can be selected if justified.