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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20135F6941996-11-27027 November 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of Atomic Safety & Licensing Board Terminating Proceedings in Docket Has Expired.W/Certificate of Svc.Served on 961127 ML20128L7761996-10-10010 October 1996 Notification of 961023 Meeting W/Wppss,Energy Facility Site Evaluation Council & State & Local Govt Agencies in Elma,Wa to Discuss Proposed Termination of CP & OL Application for Plant ML20058C2811990-10-26026 October 1990 Summary of 901018 Meeting W/Util Re Potential Restart of Units 1 &/Or 3 ML20151T9551988-08-0808 August 1988 Notification of 880915 Meeting W/Util in Rockville,Md to Review 880630 Submittal to Resolve Open Issues Re Ground Motion Attenuation ML20155E8511988-06-0909 June 1988 Notification of 880707 Meeting W/Util in Rockville,Md to Discuss Probabilistic Seismic Hazard Analysis Submitted by ML20196J9081988-06-0909 June 1988 Notification of 880707 Meeting W/Util in Rockville,Md to Discuss Probabilistic Seismic Hazard Analysis Submitted by .Meeting Room Changed ML20150C4201988-03-10010 March 1988 Forwards BNL Re Ssi/Deconvolution Issue.Ltr Received for Distribution to Applicant,Util & Lpdrs ML20149K1061988-02-18018 February 1988 Notification of 880301-02 Meetings W/Util in New York,Ny to Discuss Soil Structure Interaction/Deconvolution Issue ML20236W0451987-12-0101 December 1987 Notification of 871215 Meeting W/Util in Bethesda,Md to Discuss soil-structure Interaction/Deconvolution Analysis Used in Facility Seismic Evaluation ML20236N1221987-11-0909 November 1987 Forwards Structural & Geosciences Branch Observation & Findings Re Concrete Module on (C3-02) - Const Assurance Program.Observation & Findings Should Be Identified to Region V Lead Reviewer ML20236A7421987-10-14014 October 1987 Forwards Draft Status of Plant Seismic Review to Be Filed ML20214P5991987-05-21021 May 1987 Notification of Significant Meeting on 870529 W/Util in Walnut Creek,Ca to Discuss Licensee Overview Presentation of Completed Activities of Readiness Review Const Assurance Module C3-02 Re Concrete ML20215F9171986-12-11011 December 1986 Notification of Significant Meeting on 870107 W/Util at Region V Ofc to Review Commitments & Schedules for Readiness Review Program ML20207E5431986-07-18018 July 1986 Notification of 860801 Meeting W/Util in Walnut Creek,Ca to Discuss Const Assurance Program Earthwork Module ML20211G7741986-06-16016 June 1986 Advises That G Dick Assigned as Licensing Project Manager for Facility.Dick Will Be point-of-contact for All NRR Activities,Including Readiness Review ML20141D3631986-03-25025 March 1986 Suggests That Response to Util Re Delay Should Be Sent by NRR Rather than EDO ML20153F1681986-02-21021 February 1986 Requests Approval/Disapproval of Encl DOE Proposal, Readiness Review,Const Assurance Program Insp of Washington Nuclear Plant,Unit 3 ML20210B9881986-02-0505 February 1986 Forwards Util 850731 Request for Review of Itt Grinnell Stiff Clamps.Util Prepared to Make Presentation of Rept & Respond to Questions.Complete Review Requested by 860430 ML20137R8821986-02-0404 February 1986 Notification of 860213 Meeting W/Util in Bethesda,Md to Discuss Recent Developments Re Engineering Assurance Program of Readiness Review Program ML20210A9471986-01-15015 January 1986 Responds to 851219 Request for Info Re S&W Engineering Assurance Program.Principal Differences Between Engineering Assurance Program & Idvp Is Review Timing & Who Performs Review ML20210A6731985-12-0606 December 1985 Forwards Summary of OL Review Costs & Supporting Documentation for 840624-1222.W/o Supporting Documentation from Program Ofcs ML20209H0891985-10-0707 October 1985 Concurs w/marked-up Environ & Hydrologic Enginering Branch Review of Section 2.4 of Draft SER Re PMF on Streams & Rivers & Potential Dam Failures ML20132F2071985-09-27027 September 1985 Notification of Significant Licensee Meeting on 851029 W/Util in Elma,Wa to Examine Readiness Review Const Appraisal Program ML20209H0691985-09-19019 September 1985 Forwards marked-up Section 2.4 of Draft SER for Use in Responding to T Novak Undtd Memo.Figures 2.4.1 & 2.4.2 Missing from Draft ML20209H0811985-09-19019 September 1985 Recommends Concurrence W/Draft SER.Marked-up Page 6-19 of Draft SER Re Combustible Gas Control Sys Encl ML20198A1571985-09-19019 September 1985 Comments on WPPSS Project 3 Draft Ser,Including Sections 13.2,14 & 18 Re Training,Initial Test Program & Human Factors Engineering,Respectively.Comments on Sections 13.1, 13.4 & 13.5 Not Provided ML20210A7421985-09-11011 September 1985 Advises That Input in Draft SER Contains Outstanding Issues, Including Responses to Concerns Received in June 1984.Issues Must Be Received & Resolved at Such Time as Licensing Process Reinstated for Unit ML20210A7451985-09-0404 September 1985 Forwards Draft SER for Comments & Concurrence by 850920. Identification of Change in Staff Positions from Feb 1984 - Aug 1985 Requested So That Applicant May Be Advised of Items Requiring Reconsideration.W/O Encl ML20209G1251985-08-29029 August 1985 Forwards Draft SER for Comments & Concurrence by 850920. Draft Originally to Be Issued in Feb 1984.Draft to Provide Baseline Record of Review in Case Const Reinstated. W/O Encl ML20209G1101985-08-23023 August 1985 Forwards Draft SER Input,Based on FSAR Submitted to Date. Unresolved Issues Requiring Addl Info Listed ML20197K2061985-08-21021 August 1985 Recommends That a Bournia & T Cox Be Made Available If Members of NRR Required to Provide Depositions in WPPSS Securities Litigation.Listing of NRR Personnel Involved in Review of CPs of Facilities Forthcoming ML20209E5861985-06-28028 June 1985 Forwards Comments on Design Review Program to Be Implemented by Util as Second Module of Readiness Review Program,Per 850607 Memo.Specific Input from NRR (Secondary Reviewer) Not Required ML20127G1161985-06-21021 June 1985 Responds to Jg Partlow 850508 Memo Requesting Comments on Eight Draft Emergency Preparedness Preoperational Procedures.Program Should Be Similar to Other IE Insp Programs.Inclusion of Procedure 82102 Not Supported ML20209E5021985-06-12012 June 1985 Forwards Meeting Notice on Readiness Review Program Scheduled by Region V for 850701-02.T Ankrum Comments on Meeting Submitted.Implementation of Design Review Ie/Region V Responsibility.W/O Encl ML20197J5561985-05-0202 May 1985 Forwards Fes for Final Concurrence to Permit Issuance. Responses Received Re 841123 Memo Resolved.W/O Encl ML20209E3071985-04-16016 April 1985 Describes Site Environ Status,As Determined by 850411 Telcons W/F Hahn,A Moore & a Christian.Stabilization & Revegetation Efforts Along Stein Creek & Elizabeth Creek Satisfactory.Site Visit Not Necessary for Environ Review ML20209E3681985-04-12012 April 1985 Informs That Development of Draft SER Not Worthwhile,Per 850129 Request That Draft SER Be Provided by 850301,since Most Responses to Questions Not Received.No Approved Schedule Exists for Facility ML20209E0271985-03-0404 March 1985 Advises That Branch Has No Further Input to 831013 Draft SER & Section 3.11,per 850129 Request.Addl Input for Section 3.10 Will Be Provided at Later Time ML20209E0761985-03-0101 March 1985 Forwards Draft SER Re FSAR Chapter 14 Concerning Initial Plant Test Program.Test Program Acceptable & Meets Requirements of 10CFR50 ML20209D9871985-02-26026 February 1985 Forwards Draft SER Input on FSAR Section 4.2, Fuel Sys Design. License Condition 4.2.3.1(g) Re Maintaining Shoulder Gap Clearance During First Two Refueling Outages Should Be Relaxed ML20209E0061985-02-25025 February 1985 Confirms 850208 Notes That No Revs or Additions to 831213 Draft SER Input Provided,Per 850129 Request ML20209D9541985-02-19019 February 1985 Forwards Proposed License Condition & Safeguards SER Input, Based on Review of Facility Security Plan.Protected SER App Containing Safeguards Info Available from E Mcpeek. SALP Input Also Encl ML20209D9711985-02-19019 February 1985 Advises That Meteorology Sections in Draft SER Require No Changes & Should Be Used,Per G Knighton 850129 Request ML20209D9771985-02-15015 February 1985 Advises of Dr Muller 840511 Memo to Tm Novak That Provided Final SER Input Identifying One Open Item Re Control Room Habitability from Section 6.4.Item Remains Open Due to Lack of Info from Util ML20209D9371985-02-0808 February 1985 Forwards 831031 Draft SER Re Radiation Exposure in Response to 850129 Memo.Fsar Review Status Continuing Since Response to Eight Open Items Not Yet Received.W/O Encl ML20209D8971985-02-0606 February 1985 Discusses Review of Section 4.0, Identification of Vital Areas & App of Safeguards SER for Facility.No Concerns Re 10CFR73.55 Found ML20209D8481985-01-29029 January 1985 Informs That Draft SER Issuance Rescheduled for Mar 1985. Draft SER Input Indicating Appropriate Findings Re Topic Review or Inadequate Applicant Response Requested by 850301 ML20209D7321985-01-0303 January 1985 Forwards Summary of Review Costs Incurred by Various Program Ofcs Directly Involved in Processing of Ol.W/O Encl ML20209D6671984-12-0505 December 1984 Informs That Listed Items Should Be Corrected in Draft Fes. Corrections Needed Include Encl Table 4.7 Changes Re Population Distribution within 0-10 Miles in 1980 & Changes to Sections 4.2.2 & 5.9.4.4(2) Per Encl 840927 Memo ML20209D6331984-11-30030 November 1984 Forwards Comments on Portions of Fes,Per T Novak 841123 Request 1996-11-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20135F6941996-11-27027 November 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of Atomic Safety & Licensing Board Terminating Proceedings in Docket Has Expired.W/Certificate of Svc.Served on 961127 ML20128L7761996-10-10010 October 1996 Notification of 961023 Meeting W/Wppss,Energy Facility Site Evaluation Council & State & Local Govt Agencies in Elma,Wa to Discuss Proposed Termination of CP & OL Application for Plant ML20058C2811990-10-26026 October 1990 Summary of 901018 Meeting W/Util Re Potential Restart of Units 1 &/Or 3 ML20151T9551988-08-0808 August 1988 Notification of 880915 Meeting W/Util in Rockville,Md to Review 880630 Submittal to Resolve Open Issues Re Ground Motion Attenuation ML20155E8511988-06-0909 June 1988 Notification of 880707 Meeting W/Util in Rockville,Md to Discuss Probabilistic Seismic Hazard Analysis Submitted by ML20196J9081988-06-0909 June 1988 Notification of 880707 Meeting W/Util in Rockville,Md to Discuss Probabilistic Seismic Hazard Analysis Submitted by .Meeting Room Changed ML20150C4201988-03-10010 March 1988 Forwards BNL Re Ssi/Deconvolution Issue.Ltr Received for Distribution to Applicant,Util & Lpdrs ML20149K1061988-02-18018 February 1988 Notification of 880301-02 Meetings W/Util in New York,Ny to Discuss Soil Structure Interaction/Deconvolution Issue ML20236W0451987-12-0101 December 1987 Notification of 871215 Meeting W/Util in Bethesda,Md to Discuss soil-structure Interaction/Deconvolution Analysis Used in Facility Seismic Evaluation ML20236N1221987-11-0909 November 1987 Forwards Structural & Geosciences Branch Observation & Findings Re Concrete Module on (C3-02) - Const Assurance Program.Observation & Findings Should Be Identified to Region V Lead Reviewer ML20236A7421987-10-14014 October 1987 Forwards Draft Status of Plant Seismic Review to Be Filed ML20214P5991987-05-21021 May 1987 Notification of Significant Meeting on 870529 W/Util in Walnut Creek,Ca to Discuss Licensee Overview Presentation of Completed Activities of Readiness Review Const Assurance Module C3-02 Re Concrete ML20215F9171986-12-11011 December 1986 Notification of Significant Meeting on 870107 W/Util at Region V Ofc to Review Commitments & Schedules for Readiness Review Program ML20207E5431986-07-18018 July 1986 Notification of 860801 Meeting W/Util in Walnut Creek,Ca to Discuss Const Assurance Program Earthwork Module ML20211G7741986-06-16016 June 1986 Advises That G Dick Assigned as Licensing Project Manager for Facility.Dick Will Be point-of-contact for All NRR Activities,Including Readiness Review ML20141D3631986-03-25025 March 1986 Suggests That Response to Util Re Delay Should Be Sent by NRR Rather than EDO ML20153F1681986-02-21021 February 1986 Requests Approval/Disapproval of Encl DOE Proposal, Readiness Review,Const Assurance Program Insp of Washington Nuclear Plant,Unit 3 ML20210B9881986-02-0505 February 1986 Forwards Util 850731 Request for Review of Itt Grinnell Stiff Clamps.Util Prepared to Make Presentation of Rept & Respond to Questions.Complete Review Requested by 860430 ML20137R8821986-02-0404 February 1986 Notification of 860213 Meeting W/Util in Bethesda,Md to Discuss Recent Developments Re Engineering Assurance Program of Readiness Review Program ML20210A9471986-01-15015 January 1986 Responds to 851219 Request for Info Re S&W Engineering Assurance Program.Principal Differences Between Engineering Assurance Program & Idvp Is Review Timing & Who Performs Review ML20210A6731985-12-0606 December 1985 Forwards Summary of OL Review Costs & Supporting Documentation for 840624-1222.W/o Supporting Documentation from Program Ofcs ML20209H0891985-10-0707 October 1985 Concurs w/marked-up Environ & Hydrologic Enginering Branch Review of Section 2.4 of Draft SER Re PMF on Streams & Rivers & Potential Dam Failures ML20132F2071985-09-27027 September 1985 Notification of Significant Licensee Meeting on 851029 W/Util in Elma,Wa to Examine Readiness Review Const Appraisal Program ML20209H0691985-09-19019 September 1985 Forwards marked-up Section 2.4 of Draft SER for Use in Responding to T Novak Undtd Memo.Figures 2.4.1 & 2.4.2 Missing from Draft ML20209H0811985-09-19019 September 1985 Recommends Concurrence W/Draft SER.Marked-up Page 6-19 of Draft SER Re Combustible Gas Control Sys Encl ML20198A1571985-09-19019 September 1985 Comments on WPPSS Project 3 Draft Ser,Including Sections 13.2,14 & 18 Re Training,Initial Test Program & Human Factors Engineering,Respectively.Comments on Sections 13.1, 13.4 & 13.5 Not Provided ML20210A7421985-09-11011 September 1985 Advises That Input in Draft SER Contains Outstanding Issues, Including Responses to Concerns Received in June 1984.Issues Must Be Received & Resolved at Such Time as Licensing Process Reinstated for Unit ML20210A7451985-09-0404 September 1985 Forwards Draft SER for Comments & Concurrence by 850920. Identification of Change in Staff Positions from Feb 1984 - Aug 1985 Requested So That Applicant May Be Advised of Items Requiring Reconsideration.W/O Encl ML20209G1251985-08-29029 August 1985 Forwards Draft SER for Comments & Concurrence by 850920. Draft Originally to Be Issued in Feb 1984.Draft to Provide Baseline Record of Review in Case Const Reinstated. W/O Encl ML20209G1101985-08-23023 August 1985 Forwards Draft SER Input,Based on FSAR Submitted to Date. Unresolved Issues Requiring Addl Info Listed ML20197K2061985-08-21021 August 1985 Recommends That a Bournia & T Cox Be Made Available If Members of NRR Required to Provide Depositions in WPPSS Securities Litigation.Listing of NRR Personnel Involved in Review of CPs of Facilities Forthcoming ML20209E5861985-06-28028 June 1985 Forwards Comments on Design Review Program to Be Implemented by Util as Second Module of Readiness Review Program,Per 850607 Memo.Specific Input from NRR (Secondary Reviewer) Not Required ML20127G1161985-06-21021 June 1985 Responds to Jg Partlow 850508 Memo Requesting Comments on Eight Draft Emergency Preparedness Preoperational Procedures.Program Should Be Similar to Other IE Insp Programs.Inclusion of Procedure 82102 Not Supported ML20209E5021985-06-12012 June 1985 Forwards Meeting Notice on Readiness Review Program Scheduled by Region V for 850701-02.T Ankrum Comments on Meeting Submitted.Implementation of Design Review Ie/Region V Responsibility.W/O Encl ML20197J5561985-05-0202 May 1985 Forwards Fes for Final Concurrence to Permit Issuance. Responses Received Re 841123 Memo Resolved.W/O Encl ML20209E3071985-04-16016 April 1985 Describes Site Environ Status,As Determined by 850411 Telcons W/F Hahn,A Moore & a Christian.Stabilization & Revegetation Efforts Along Stein Creek & Elizabeth Creek Satisfactory.Site Visit Not Necessary for Environ Review ML20209E3681985-04-12012 April 1985 Informs That Development of Draft SER Not Worthwhile,Per 850129 Request That Draft SER Be Provided by 850301,since Most Responses to Questions Not Received.No Approved Schedule Exists for Facility ML20209E0271985-03-0404 March 1985 Advises That Branch Has No Further Input to 831013 Draft SER & Section 3.11,per 850129 Request.Addl Input for Section 3.10 Will Be Provided at Later Time ML20209E0761985-03-0101 March 1985 Forwards Draft SER Re FSAR Chapter 14 Concerning Initial Plant Test Program.Test Program Acceptable & Meets Requirements of 10CFR50 ML20209D9871985-02-26026 February 1985 Forwards Draft SER Input on FSAR Section 4.2, Fuel Sys Design. License Condition 4.2.3.1(g) Re Maintaining Shoulder Gap Clearance During First Two Refueling Outages Should Be Relaxed ML20209E0061985-02-25025 February 1985 Confirms 850208 Notes That No Revs or Additions to 831213 Draft SER Input Provided,Per 850129 Request ML20209D9541985-02-19019 February 1985 Forwards Proposed License Condition & Safeguards SER Input, Based on Review of Facility Security Plan.Protected SER App Containing Safeguards Info Available from E Mcpeek. SALP Input Also Encl ML20209D9711985-02-19019 February 1985 Advises That Meteorology Sections in Draft SER Require No Changes & Should Be Used,Per G Knighton 850129 Request ML20209D9771985-02-15015 February 1985 Advises of Dr Muller 840511 Memo to Tm Novak That Provided Final SER Input Identifying One Open Item Re Control Room Habitability from Section 6.4.Item Remains Open Due to Lack of Info from Util ML20209D9371985-02-0808 February 1985 Forwards 831031 Draft SER Re Radiation Exposure in Response to 850129 Memo.Fsar Review Status Continuing Since Response to Eight Open Items Not Yet Received.W/O Encl ML20209D8971985-02-0606 February 1985 Discusses Review of Section 4.0, Identification of Vital Areas & App of Safeguards SER for Facility.No Concerns Re 10CFR73.55 Found ML20209D8481985-01-29029 January 1985 Informs That Draft SER Issuance Rescheduled for Mar 1985. Draft SER Input Indicating Appropriate Findings Re Topic Review or Inadequate Applicant Response Requested by 850301 ML20209D7321985-01-0303 January 1985 Forwards Summary of Review Costs Incurred by Various Program Ofcs Directly Involved in Processing of Ol.W/O Encl ML20209D6671984-12-0505 December 1984 Informs That Listed Items Should Be Corrected in Draft Fes. Corrections Needed Include Encl Table 4.7 Changes Re Population Distribution within 0-10 Miles in 1980 & Changes to Sections 4.2.2 & 5.9.4.4(2) Per Encl 840927 Memo ML20209D6331984-11-30030 November 1984 Forwards Comments on Portions of Fes,Per T Novak 841123 Request 1996-11-27
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13.0 STRUCTURAL ENGIf;EERING BRANCH 13.1 The procedures presented in this section for combining the (3.3.2.2) various effects of the design basis tornado are not sufficiently explicit. In particular, expand the procedures to show how these effects are combined to produce the most adverse total o response of structures or portions thereof. Also indicate that the effects of (a), (c) and (d) of Section 3.3.2.1 will be combined and not (a), (b) and (c) as indicated.
13.2 Indicate if the Turbine Administrative and Service Buildin (3.3.2.3) designed for the design basis tornado to satisfy the stip gs will be ulation of Section 3.3.2.3 and if so, to what extent.
13.3 Describe more explicitly the procedures that will be utilized (3.5.4.1) in designing a roof slab or a wall panel for missile impact near the support where shear effects may govern the design.
13.4 (RSP The period intervals at which the spectral values of the
( 3. 7.1. 2) ) design time history are computed, as indicated in Section 3.7.1.2, are not in accordance with the Regulatory Staff position which lists the following intervals as a minimum:
- Increment Frequency Range (hertz) (hertz)
- 0. 2 - 3. 0 0.10 3.0 - 3.6 0.15
- 3. 6 - 5. 0 0.20 5.0 - 8.0 0.25 8.0 -15.0 0.50 15.0 -18.0 1.00 18.0 -22.0 2.00 22.0 -34.0 3.00 Indicate that the increments you are proposing will produce equally or more conservative results otherwise revise your procedures and utilize the above-listed increments.
13.5 Indicate if the more than 70'-0 of soil backfill surrounding (3.7.1.6) the auxiliary building is considered in the seismic analysis of the structure, as seems to be indicated by the spring at elevation 360'-0 shown in Figure 3.7-19. If so, describe the procedures utilized for representing this fill and discuss the expected effects it may have on the response of the structure and equipment.
13-2 )
bination t!nere the time-history method of analysis is used, the com k 13.6 (RSP) of the responses to the three components of the se earthqua e (3.7.2.1) may be based on the SRSS method only if the maximum respon i to the three components is the objective, whereby the max mum response to each component is utilized in the combination.
i three If the combined time-history is the objective, the time-histories step.
should be combined l algebraically revise the third paragraph of Section 3.7.2.1 according y.
In your response to Q.1 on Section 3.7.1, provide justi-13.7 (3.7.2.1) fication for not incorporating the NSSS seis The containment shell is represented by a stick model in Fig 13.8 In view of the fact that the polar crane is supported 3.7-19 ide (3.7.2.1) on the shell, indicate if the ovalling modes of re the bases for arriving at such a conclusion.
The information provided in Section 3.7.2.6 is not sufficient.
13.9 Describe the procedures that will be used in developing tiensof the three (3.7.2.6) floor response spectra including the combination components of the carthquake and in particular the consid given to ficor response in one direction due to input in another direction.
. The conclusion orrived at in Section 3.7.2.7 may not be a build-13.10 (RSP) Indicate what is meant by "within always For true. example, the differential displacement between the (3.7.2.7) ing".
top of the steam generator and the next anchoronse point of the steam line may not be that insignificant to the r of the steam line.
should be provided for this section.
is as 1
The Staf f's position on design criteria to acc i follows:
Where the response First,spectrum method a static analysis is used, the procedure is made involves two steps:
by considering the maximum Second, relative displa a dynamic analysis by cdding the absolute sums.is made assuming no relative points, but using the worst floor response spectrum h the when the support points are in the same structure, id r w ere it worst floor response spectrum can be easily
13-2 4
)
13.6(RSP Where the time-history method of analysis is used, the combination (3.7.2.1)) of the responses to the three components of the earthquake may be based on the SRSS method only if the maximum response to the three components is the objective, whereby the maximum response to each component is utilized in the combination.
If the combined time-history is the objective, the three time-histories should be combined algebraically at each time step. Indicate your intent to comply with this position and revise the third paragraph of Section 3.7.2.1 accordingly.
13.7 In your response to Q.1 on Section 3.7.1, provide justi-(3.7.2.1) fication for not incorporating the NSSS seismic model (mass and stiffness) in the seismic model of the interior structures.
13.8 The containment shell is represented by a stick model in Figure (3.7.2.1) 3.7-19. In view of the fact that the polar crane is supported on the shell, indicate if the ovalling modes of response of the shell could be excited significantly and if not provide the bases for arriving at such a conclusion.
13.9 The information provided in Section 3.7.2.6 is not sufficient.
(3.7.2.6) Describe the procedures that will be used in developing floor response spectra including the combination of the three components of the earthquake and in particular the consideratiens given to floor response in one direction due to input in I
another direction.
13.10(RSp)
The conclusion arrived at in Section 3.7.2.7 may not be (3.7.2.7) always true. Indicate what is meant by "within a build-ing". For example, the differential displacement between the top of the steam generator and the next anchor point of the steam line may not be that insignificant to the response of the steam line. Clarification and additional justification should be provided for this secticn.
The Staff's position on design criteria to account for relative displacements between component support points is as follows:
Where the response spectrum method is used, the procedure involves two steps: First, a static analysis is made by considering the maximum relative displacements between support points; i.e., the design displacement is obtained by adding the absolute sums. Second, a dynamic analysis is made assuming no relative displacement between support point >, but using the worst floor response spectrum when toe support points are in the same structure, where the worst floor response spectrum can be easily identified, or the enveloped floor response spectrum when the support points
fi 13-3 )
are in separate structures, where a frequency shift is expected.
Results from these two steps, static and dynamic, should be combined in an absolute manner.
State your intent to confom to the Regulatory staff position as stated above or describe and provide justifica-tion for any exceptions to the position.
13.11 -
It is stated in Section 3.8.2.1.1 that the containment (3.8.2.1) shell provides vertical support for the proposed 300 ton polar crane bridge. Confirm that the containment shell will also provide lateral support to the crane and provide the following:
- a. General details of the crane bridge supports including the rail, ring girder, and brackets,
- b. A discussion of the loads and combinations thereof for which the connection to the containment will be designed l including the allowable stresses. I
- c. The treatment given to the expected radial differential displacements between the crane support and the contain-ment shell.
13.12 Identify the containment penetFations that will be designed (3.8.2.1) to withstand jet forces to satisfy the third stipulation of Section 3.8.2.1.2 (a) and describe with the help of sketches the. procedures of such a design.
13.13 Provide details and all the pertinent infomation on the design (3.8.2.1) of the multi-ply primary bellows that form (ontainment boundary as shown in Figures 3.8-1 and 3.8-2 and discussed briefly in Section 3.8.2.1.2 (c) and (d).
13.14 Identify the operating conditions which can result in the
( 3. 8. 2. 3) external pressure on the containment (identified as Ps in Section 3.8.2.3.1) and indicate if it will be accompanied by any temperature changes and, if so, justify the omission of this thermal load from the combinations that contain Ps-13.15 For load combinations (a) (1) and (a) (2) of Section 3.8.2.3.2, (3.8.2.3) justify the use of the operating thermal loads at the penetrations in lieau of the loads associated with Ta which may be higher for pipes with relatively low temperatures.
13.16 For load combinations (3) and (4) of Section 3.8.2.3.2, (3.8.2.3) justify the use of Poin lieau of a higher pressure that will be associated with a rupture at, for example, a steam line penetration.
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13.17 (3.8.2.3) For load combination (d) (1) of Section 3.8.2.3, justify the omissionduring if expected of Tt, the the temperature test. load associated with Pt.
13.18 (3. 8. 2. 3) dustiiv the omission of a load combination representing the external pressure, Ps, with the SSE.
13.19 l
' (3.8.2.4) Since tiere are no apparent mechanical connections between the inttrnal concrete and the concrete underlying the bottom head of the containment, the loads will be transferred from the interior concrete to the underlying concrete through the contaiament shear friccion. Describe bottom head either through bearing or through the procedures and treatment of this aspect of the design.
13.20 (3.8.2.7) Describe the construction sequence of the bottom head of the containment and the measures that will be taken to preclude any voids in the underlying concreto.
13.21 .
(3.8.3.1) Provide general details of the removable shield blocks above the reactor nozzles and describe the analysis procedures and design measures taken to preclude these blocks from becoming missiles. Also describe the pressure-time load in the annulus around the primary pipes and the jet load that ni .
t on these blocks in caajunction with the pressure.ght impinge 13.22 (3.8.3.4) Provide the following information for the primary shield wall:
a) The accident pressure-time curve and the accident temperature gradient, if any, b)
The operating cooling system thermal provided. gradient and a description of any 13.23 l (3.8.3.4) Provide the accident pressure-time curve for the secondary shield walls and the time curve for any jet loads that might impinge on these walls and discuss the analytical techniques utilized to obtain the equivalent static loads due to these effects.
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