|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20011F6111990-02-28028 February 1990
Summary of Operating Reactors Events Meeting 90-05 on 900228
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
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
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
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
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
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20206L9831988-11-25025 November 1988
Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl
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
1990-02-28
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20011F6111990-02-28028 February 1990
Summary of Operating Reactors Events Meeting 90-05 on 900228
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
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
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
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
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
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
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
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
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
1990-02-28
[Table view] |
Text
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}
l MEMORANDUM FOR:
ACRS Members i
FROM:
C. P. Siess
SUBJECT:
REPORT OF AD HOC SUBCOMMITTEE ON FOUNDATION PROBLEMS AND REMEDIAL ACTIONS AT MIDLAND PLANT UNITS 1 AND 2 The Ad Hoc Subcommittee met in Washington, D.C. on 29 Aprf) 1982. Those in attendance were:
C. P. Siess, ACRS Member W. M. Mathis, ACRS Member R. J. Scavuzzo, Consultant J. D. Osterberg, Consultant Z. Zudans, Consultant Presentations were made by the NRC Staff and the Consumers Power Company, Applicant.
The meeting was requested by the NRC Staff to discuss with the ACRS pro-posed remedial actions for soils-related structural settlement problems at the Midland site. The nature, scope, and status of the Staff's review of two to three year were highlighted. The NRC Staff has requested comments from the ACRS on the adequacy of the Staff requirements, and review of the remedial actions being taken or proposed by the Applicant.
Problem Plant grade is at E1. 634 feet. Good foundation material, of unquestioned capa-bility is found at E1. 595 to 600 feet. The containment buildings and a large portion of the auxiliary building a e founded on the good material. The re-maining Category 1 structures are founded on compacted fill material about 25 to 30 feet thick. This fill, consisting of both granular and cohesive materic1s, was inadequately compacted.
It is extremely variable in density and ranges from reasonably good to extremely poor foundation material.
8510080431 850930 PDR FOIA AfrAWMWT 1 l
BRUNNERB5-602 PDR
4-MIDLAND PLANT UNITS 1 8 2 The deficiency of the fill was discovered in July 1979 when the settlement of the partially completed diesel generator building reached about 7 to 8 I
inches, more than twice the expected settlement.
Potential Consequences The potential consequences of the inadequately compacted fill material are:
a.
Excessive settlement of structures founded on it.
b.
Excessive settlement of piping, electrical ducts, and tanks buried in it.
c.
Liquefaction during a seismic event of those portions of the fill consisting of granular materials.
Affected Structures and Components a.
Diesel Generator Building b.
Auxiliary Building Control tower Electrical penetration areas Feedwater isolation valve pits.
c.
Service Water Pump Structure d.
Borated Water Storage Tank e.
Underground Utilities Service water piping Borated water piping Diesel fuel piping and storage tanks Control room pressurization lines and tanks Electrical duct banks
MIDLAND PLANT UNITS 1 & 2 -
Remedial Actions The remedial actions are of several kinds, as described in very general i
terms below:
Underpinning to extend the foundation to the original soil.
a.
This is being done for the Service Water Pump Structure and portions of the Auxiliary Building (i.e. the Control Tower, the Electrical Penetration Areas and the Feedwater Isolation Valve Pits.)
b.
Surcharge to accelerate settlement and thus reduce future settl ements. This is being done for the Diesel Generator Building and the Borated Water Storage Tank.
c.
Rebedding and/or replacing portions of the buried piping, d.
Permanent dewatering of a major portion of the site to reduce the probability of liquefaction of the fill material due to an earthquake.
e.
Extensive monitoring of all affected structures and com-ponents, including those for which no remedial action is themed necessary.
Seismic Considerations The Midland Plant was designed for a SSE characterized by a zero-period acceleration of 0.12 g and a " modified" Housner spectrum. The modifi-cation consisted of increasing the acceleration in the regioni between about 1.5 and 5 Hz.
l e
l L
f MIDLAND PLANT UNITS 1 & 2
- More recently, Site Specific Response Spectra (SSRS) have been developed for the Midland Plant site. The SSRS being used to reevaluate seismic 8
margins, and for the design of underpinning, yield accelerations up to twice those for the original spectra at frequencies above about 5 Hz.
In this range, they correspond fairly closely to R.G.1.60 spectra anchored at a zero-period acceleration of 0.12 g.
For frequencies below 3 to 5 Hz the SSRS accelerations are less than those for either the original design spectra or the R.G.1.60 spectra.
Some of the new construction (underpinning) was designed before the SSRS were decided upon.
For the seismic response analysis of these structures, spectra corresponding to 1.5 times the "FSAR Spectra" were used. The Applicant has stated that these spectra envelope the SSRS.
With regard to ifquefaction, it was stated that the " loose granular back-fill supporting Seismic Category 1 facilities is safe against lique-faction for earthquakes that produce a peak ground surface acceleration of 0.19 g or less provided the groundwater. elevation in the backfill is maintained at or below E1. 610 f t."
The permanent dewatering system will maintain the groundwater level at E1. 595 ft. to provide margin to permit repair or replacement of the dewatering system if it should fail.
The setsmic input criteria and the SSRS were not reviewed by the Ad Hoc Subcommittee at this meeting. W pcomend that this be considered by the Midland Plant Subcommittee, especially with respect to the need for and I
criteria for dewatering to reduce the probability of liquefaction, e
e
I MIDLAND PLANT UNITS 1 & 2,
Findings The RC Staff's approach to the remedial measures is essentially to require that the corrected plant should comply with all regulations i
i and licensing requirements; that is, that it should be as good as it would have been if it had been designed and constructed in accordance with all commitments in the FSAR. Within this framework, the NRC Staff has made a thorough review. We found essentially no aspects of the remedial actions that had not been considered by the Applicant or the Staff. The Staff's approach is typically conservative, in some cases perhaps overly so. The Staff's requirements for monitoring are elab-orate and appropriately thorough.
Where the Staff had reason to believe that it did not have adequate ex-pertise or experience in some of the specialized areas involved in evalu-ating the problem and the remedial measures, it has engaged consultants.
Although there is some question whether the Staff and its consultants have the expertise and experience to judge the ability of the structures to serve their required functions with remedial measures short of those required to bring them into full compliance with the original criteria, requirements, and commitments, there is no question that they are adequ-ately competent to achieve compliance with the licensing requirements.
We are masonable confident, subject to resolution of the question of seismic input as it relates to soli liquefaction, that the remedial measures, if completed to the satisfaction of the NRC Staff, will restore the affected structures to an acceptable condition. We consider the moni-toring programs to be important and believe that the NRC Staff's mquire-
)
ments are appropriate.
l i
?
6-MIDLAND PLANT UNITS 1 & 2 Overall, we find the Staff's approach and requirements to be adequate to insure no' undue risk to the health and safety of the public. There was some feeling in the Subcommittee of " overkill" in some of the Staff's re-quirements. This, however, was probably the result of the Staff's attention to licensing criteria as opposed to an evaluation of the modi-fication's contribution to risk or consequences.
Recommendations We recommend:
1.
That the Midland Plant Subcommittee review the adequacy of the seismic input criteria and the SSRS and its relation to the proposed permanent site dewatering as a means of reducing the probability of liquefaction due to an earthquake.
2.
That, subject to a finding by the Midland Plant Subcommittee regarding the adequacy of the seismic input criteria, the ACRS recognize the adequacy of the NRC Staff's efforts as outlined in this report and consider the proposed remedial measures as a matter that can and should be resolved in a manner satisfactory to the NRC Staff.
3.
That the EDO be informed at this time that the ACRS has found the Staff's approach to be acceptable, subject to the further review mentioned in item 1,above.
t cc: ACRS Staff
~
1.
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1.7 Summary of Outstanding Items As a result'of the staff's safety review of the Midland plant OL application, a number of items remain open at this time. The lack of final detailed design 3
information related to the soils problems has made it difficult for the staff to complete certain areas of the OL review. A number of open items, not necessarily related to the soils proceedings, remain outstanding because final staff positions have not yet been reached or because agreement between the staff and the applicant has not been reached.
In several instances, additional information and/or commitments are needed from the applicant before the item can be resolved or reclassified as a confirmatory issue. Staff review of these items must be completed prior to a decision on issuance of an operating license.
Final staff review and resolution of these items will be presented in one or more supplements to this report.
The outstanding open items, with appropriate references to subsections of this report, are listed below.
w (1) Nearby Explosive Hazards (2.2) styr (2) Turbine Missiles (3.5.1.3) 3"'# k
AW*m (5) Soils Settlement Issue (2.4.4, 2.4.6, 2.5.2, 2.5.4, 3.7.1, 3.7.2, 3.7.3, 3.8.1,3.8.2,3.8.3,3.8.4,3.9.3)
W p # (6) Seismic and Environmental Qualification of Equipment (3.10, 3.11) gPl M (7) Natural Circulation Cooldown Analyses (5.
4.2) 4WM (8) HPI Line Makeup Nozzle Cracking (5.4.3.1) j pt.T (9) Reactor Vessel Head Vent (5.4.7)
CA# (10) Secondary System Containment Valve Testing (6.2.6) gru (11) Leak Testing of DHR and RBCWS Containment Valves (6.2.6) sks(0topM%
gn (12) Appendix R (Fire Protection) (9.5.1)
Awuubt.510empdelty M
(13) AFW Ring Header Distortion (10.'4.9)
WM#
(14) Emergency Preparedness Plan (13.3)
MPLitMT(15) Control Room Design Review (18.0)
,pg (16) Shutdown Decay Heat Removal Requirements (10.4.9, Appendix C)
ATTAC.HMttoT Io
1.9 License Conditions There are several issues for which a license condition may be desirable to ensure that staff requirements are met during plant operation. The license condition may be in the form of a condition in the body of the Operating 8
Licenses, or a limiting condition for operation in the Technical Specifications appended to the licenses.
These items, with appropriate references to subsec-tions of this report, are listed below.
(1) Groundwater Monitoring (2.4.6.4)
(2) Itemi:ed Documentation of Inadequate Core Cooling Instrumentation (J.J.4.1)
(3) Testing of Relief anc Safety Valves - II.D.1 (5.2.2.1)
(4) Inservice Inspection Program (5.2.4)
(5) AFW Level Control Details (5.5.3)
(6) Postaccident Sampling - II.S.3 (6.1.1.3, 7.5.3, 9.3.4.3)
(7) Control of Heavy Loads (9.1.5)
(8) Secondary Water Chemistry Monitoring and Control Program (10.3.5)
(9) B&W Plant Experience on Shift During Startup (13.1.2)
(10) Emergency Operating Procedures per ATOG Program (13.5.2.3)
(11) Small-Break LOCA Model (15.7.9) i I
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