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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20129J5741996-11-0505 November 1996 Trip Rept of 961001-03 Visit to Omega Point Labs in San Antonio,Tx to Witness Three Fire Endurance Tests Conducted for PG&E ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20245F9261989-08-0707 August 1989 Summary of 890613-15 Meetings W/Util in San Francisco,Ca Re PRA long-term Seismic Program.List of Attendees & Agenda Encl ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247D3441989-05-16016 May 1989 Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20245H8011989-02-23023 February 1989 Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl ML20235M1671989-02-17017 February 1989 Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl ML20196B9821988-12-0101 December 1988 Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl ML20206L9831988-11-25025 November 1988 Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl ML20195H0271988-11-25025 November 1988 Summary of Operating Reactor Events Meeting 88-46 on 881122 ML20206E3591988-11-10010 November 1988 Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program ML20205H7521988-10-18018 October 1988 Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20207K9461988-10-0404 October 1988 Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl ML20245D8411988-09-28028 September 1988 Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 ML20155B8231988-09-20020 September 1988 Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams ML20154F7971988-09-15015 September 1988 Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl ML20154N4471988-09-0707 September 1988 Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl ML20153G6331988-08-30030 August 1988 Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program ML20153C1861988-08-23023 August 1988 Summary of Operating Reactors Events Meeting 88-34 on 880823 ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151Q8131988-08-0303 August 1988 Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl ML20207E2961988-07-28028 July 1988 Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl ML20151N0521988-07-26026 July 1988 Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML20150D7171988-07-0707 July 1988 Summary of Operating Reactors Events Meeting 88-26 on 880628 ML20153B0281988-06-22022 June 1988 Summary of Operating Reactors Events Meeting 88-25 on 880621.List of Attendees,Discussion of Significant Elements of Events & Summary of Reactor Scrams Encl ML20150E0241988-06-21021 June 1988 Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants 1996-11-05
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20245F9261989-08-0707 August 1989 Summary of 890613-15 Meetings W/Util in San Francisco,Ca Re PRA long-term Seismic Program.List of Attendees & Agenda Encl ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247D3441989-05-16016 May 1989 Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20245H8011989-02-23023 February 1989 Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl ML20235M1671989-02-17017 February 1989 Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl ML20196B9821988-12-0101 December 1988 Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl ML20206L9831988-11-25025 November 1988 Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl ML20195H0271988-11-25025 November 1988 Summary of Operating Reactor Events Meeting 88-46 on 881122 ML20206E3591988-11-10010 November 1988 Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program ML20205H7521988-10-18018 October 1988 Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20207K9461988-10-0404 October 1988 Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl ML20245D8411988-09-28028 September 1988 Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 ML20155B8231988-09-20020 September 1988 Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams ML20154F7971988-09-15015 September 1988 Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl ML20154N4471988-09-0707 September 1988 Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl ML20153G6331988-08-30030 August 1988 Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program ML20153C1861988-08-23023 August 1988 Summary of Operating Reactors Events Meeting 88-34 on 880823 ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151Q8131988-08-0303 August 1988 Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl ML20207E2961988-07-28028 July 1988 Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl ML20151N0521988-07-26026 July 1988 Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML20150D7171988-07-0707 July 1988 Summary of Operating Reactors Events Meeting 88-26 on 880628 ML20153B0281988-06-22022 June 1988 Summary of Operating Reactors Events Meeting 88-25 on 880621.List of Attendees,Discussion of Significant Elements of Events & Summary of Reactor Scrams Encl ML20150E0241988-06-21021 June 1988 Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants ML20196A9201988-06-17017 June 1988 Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl ML20195B2211988-06-0808 June 1988 Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl 1989-09-06
[Table view] |
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Docket Nos. 50-2754 6 and 50-323 SEP 7 1973 APPLICANT: PACIFIC GAS & ELECTRIC C(MFANY (PGE)
FACILITY: DIABLO CANYON UNITS 1 AND 2 ,
gUMMARY OF MEETING HELD ON AUGUST 21, 1973 TO DISCUSS DEFICIENCIES .
IN ' HIE DIABIS CANYON FSAR 'i ,
Purpose A meeting was held between representatives of PGE, Westinghouse, and (
the Regulatory staff on August 21, 1973, in Bethesda. A list of parti +
cipants is attached as Enclosure No. 1. Me meeting was requested by PG&R to discuss certain deficiencies in their Diablo Canyon FSAR submittal.
As a result of the preliminary review conducted by the staff, the applica-tion for operating licenses for Diablo Canyon Unita 1 and 2 uns rejected on August 13, 1973. We principal reasons for rejection were the extensive nature of the deficiencies identified in the FSAR, and the fact that Revision 1 of the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (October 1972) was not followed in the prepara-tion of the FSAR. PG&E plans to resubmit their application during the last week of September.
Discur tion ae following technical areas in the FSAR were discussed at the meeting; :
any decisions regarding action items are indicated below.
- 1. . Tornado Design Criteria Tornado design criteria were not discussed in the tendered FSAR.
PGE indicated that they had been working on this item, using the sechtel document (BC-Top-3) as a guide. $e staff noted that'a new regulatory guide on this subject would be issued soon, probably in November. 2 1s guide divides the country into three regions for purposes of design basis tornado characteristics (See Enclosure No.
2 for a draft summary of these characteristics for each region). . I Diablo Canyon is11e in Region II. PGE intends to supply a.euimmary of the tornado capability of all Category I structures and systems which could affect safe shutdown. M is &nalysis will include the diesels and the ecadensate water storage tank. However, the detailed
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SEP 7 1973 analysis of tornade generated missiles will not be proridad uhen the application is resubmitted, but would be available within 60-90 days i after docketing. This procedure was agreed to by the Regulatory staf f. l
- 2. protection Assinet Dynamic Ef fects Associated with the- postulated Rupture of piping 4 l
With regard to pipe break outside santainment, p06E initially indicated I' that they would like to reply by correspondence, using the letter from .
A. Giambusso dated 12/13/72 as a referense. pG&g bed retained Nuelear services Corporation to doaan analysis en this subject, and a draft ;
c' tef their report is nearly ready for submittal. The staff said'that l I
they would need more 43x tistive information in the FsAR en pipe .
break both inside and outside containment. It was finally agreed that PG6E would provide t. ore information on pipe break in the pSAR, and that the report from Huclear services would be incorporated as an Appendix to the FSAR. i I
- 3. Desian of catesory I Structures ]
The staff agreed that Document (3) on structural design criteria (see Enclosure No. 3 of letter of rejection to PG&E dated 8/13/73) is new, but the information outlined in this document is not. If this document did not exist, the applicant would have to establish some appropri.ite criteria of his own for pipe break outside contain-ment. '1hase comments were made in reference to Item 3.8.1-b of Enclosure 1 of the letter of rejection to PG6E (referred to hereafter as Enclosure 1). Also, it was agreed that Item 3.8.2-b of Inclosure 1 (position with regard to ACI-359 on concrete sontaituments) should come under the category of additional infomation to be supplied, i.e., an asterisk item not required for docketing.
- 4. Auxiliary Systems l I
With regard to item 10.1 on page 22 of Enclosure 1, the staff clarified that the statement was poorly worded, and that two separate requests for information were being stated: 1) Plant heat balance, and 2) safety related design features of the steam and power conversion system. !
- 5. Containment Functional Design and Heat Removal Systems j On page 14 of Enclosure 1 there are five deficiencies under. the heading of Containment Functional Design and Hast Resoval systems. After some discussion it was agreed that Items 1 (Containment pressure response analysis for a spectrum of hot ling breaks) and 4 (Containment and subsampertment pressure response analysis for a spectrum af snain steam line ruptures within containment) weeld not be required for ^^
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Forea AEC-318 (Rev,9-53) AECM 0240 e.o .u- to-a s ses- 444 wits
SEP 7 373
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- 6. Area Monitorina on page 25 of Ensleevre 1, the staff questioned the description of alarm set-points in terms of ei/se. PCs indicated that this was an error in the PSAR, and that the Tables containing these units would be corrected.
Also on page 25, PGE questioned the need for continuous particulate and gas monitors in the spent fuel handling compartment and in the radunste area. De staff indiasted that this was the reeammended procedure to insure against.the manual error of forgetting to turn on the monitor when entering those areas.
- 7. Diesel Generators on page 18 of Enclosure 1 (Section 8.3.2). PGE asked for clarification on the question concerning starting and loading of the shared diesel generator. We uaff amplained that information was required on the switching capability of the fif th diesel, and that PG&E should demonstrate that the provision of the fif th diesel does not impair the ability of the Emergency Power System to perform its safety function.
- 8. Physical separation Criteria of Electrical Equipment -
Again on page 18 of Enclosure 1 (Section 8.3.3), PG&E requested clarification on the question concerning physical separation criteria used for all redundant Class IE electrical power equipment, devices, circuits and raceways. We staff indicated that actual physical dimensions should be provided for distances between equipment, devices, redundant cables trays, etc. ,,
- 9. Systems Required for Safe Shutdown On page 17 of Enclosure 1 (Section 7.4.1), the staff agreed that modifications required for instrumentation and controls should refer to the cold shut down condition rather than hot shut down as stated in the Enclosure. It was further agreed that these modifications sould be delayed until the Technical Specifications stage.
- 10. Reacter Coolant System and Connected _. Systems With regard to the questions on chapter 5 of the FSAR (page 13 of Enclosure 1), the following items were discussed:
- s. 5.1-as it was agreed that appropriat& Piping and Instrumentation Diagrams were available in Otapter 3 of the PSAR. PG u will insert a creas reference to this effects omcE> . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...
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DATE > .. . . . _ _ . . . . .. -
Forrn AEC-318 (Rev.9-53) AECM 0240 oao sea-no-sises- 64s-c7s
N 4 SEP 7 1973
- b. 5.2-b: the statement with regard to overpressure protection j should be deleted 3
- e. 5.3-en the Wernal and Hydraulic Characteristics Seemary Table is sentained in Section 5.1 of the FSiR. PG&E will cross reference this .
- 11. desic Geoloaic and Seismic Information l With regard to Section 2.5.1 on page 4 of Enclosure 1. PG4E indiested that they had provided the reference document by R. R. Jahna in their FSAR submittal. De staff agreed that they did set have to provide it again.
- 12. Uses of Adjesent land and Waters Under section 2.1.4 of Enclaure 1, PG&E asked fc? a clarification of " nearby" in the statement, "... uses of nearby surface and ground water." %e staff indicated that a distance of 2-3 miles would be appropriate.
- 13. Stability of Subsurface Materials !
l On page 6 of Enclosura 1, the applicant is asked to provide assurance that oil and/or water will not be extracted fra beneath or adjacent to the plant such that it may pose a hasard to plant operation and safety. The staff is particularly concerned with adjacent offshore properties. PG&E indicated that there is currently no specific interest in of fshore properties, and asked if they could defer a detailed analysis of this item until such interest is expressed. De staff agreed that a statement in the PSAR to this effect would be astisfactory, l
but that any availabic data on these properties should be provided at this time.
,I l 14. Slope stability )
\
Pages 6-7 of Enclosure 1 contain specific comments en the slope i stability analysis presented by the applicant ta the FSAR. PG6E l
~
asked for clarification as to what information une required for docketing and what could be provided later. %e staff indicated that the following information must be provided for docketing:
- 1) Details of the static stability analysis, including soil and rock properties and assumptions, 2) A description of the boring j program, including the proposed schedule for this program. We I deteripties of this boring program should inelods an acceptable l l mothed of sampling which produces undisturbed ears borings and samples l
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Form AEC-Sis (Rev.9-53) AECM 0140 ..o .4bie-aises- 446-ers
1 w
5 SEP 7 W3 taken should be representative of all material in the slope above the plant which could pose a hasard in the event of failure. The dynamic stability analysis does not have to have been completed j for docketing, but the results of this work should be available i within 60-90 days from the date of dockating. l l
Original Signed by Thomas J. Hirons FWR Branch No. 3 Directorate of Licensing
Enclosures:
- 1. Attendance List i
- 2. Design Lasta Tornado Characteristics cc w/encia:
AEC PDR Local PDR R. C. DeYoung j K. R. Coller R. W. Klecker R0 (3) l TR Assistant Directors TR aranch Chiefs R, Cushman V.11. Wilson i RP Assistant Directors RP branch Chiefs L. Chandler, OGC 1
! R. Fraley, ACRS (16)
Heating Attendees frca REG J. H. llendria l
DI STRI BUTION :
Docket (2)
RP Rending !
PWR-3 Reading l
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sum , TJHiro, , , , p, , ,,EHMarkee ,_ , _ , _ _ ,
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Forn AEC-St8 (Rev.453) AECM 0240 sao .4a-se-si4as.: 44s47s l
ENCLOSURE NO. 1 l
1 ATTENDANCE LIST l PACIFIC GAS & ELECTRIC COMPANY V. J. Ghio J. B. Hoch U. J. Lindblad E. P. Wollak WESTINGHOUSE I
'A. J. Abels j P. Blau j J. W. Dorrycott ]
4 AEC* l i
1 J. S. Boegli l S. Block l A. T. Cardone J. E. Fairobent l
K. R. Goller T. J. Hirons R. E. Lipinski E. H. Markee W. C. Milstead J. E. Richardson G. W. Rivenbark I M. Srinivasan C. W. Sullivan i A. R. Ungaro )
l With the exception of J. S. Boegli and T. J. Hirons, all AEC attendance was on a part time basis.
I
DRAFT ENCLOSURE NO. 2 TABLE 1 DESIGN BASIS TORNADO CHARACTERISTICS Rotational Transnational Pressure Rate of Speed Radius Drop Pressure Drop Region (mph) Speed Maximum (mph)
Minimum 2_ / (feet) (psi) (psi /sec)
I 300 60 20 275 3.0 1.0 II 250 50 15 275 2.25 0.6 III 200 40 10 275 1.5 0.3
-2/The minimum transnational speed, which allows maximum transit time of the tornado across exposed plant features, is to be used whenever low l l l
travel speeds (maximum transit time) is a limiting factor in design of the l ultimate heat sink.
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