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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects ML20245E9441989-01-31031 January 1989 Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant ML20196C2701988-12-0202 December 1988 Notification of 881207 Meeting W/Util in Rockville,Md to Discuss Dcrdr Submittal of 880825 ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20206M9231988-11-23023 November 1988 Lists Questions Raised by Board Study of Licensee Environ Repts on Facilities,For Responses & Comments.Served on 881125 ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20206J6441988-11-16016 November 1988 Requests Responses to Listed Questions Re Proceeding, Including Explanation of Environ Consequences Caused by Movement of Centrifuges from State of Oh to State of Tn. Served on 881117 ML20206E6361988-11-14014 November 1988 Forwards Fr Notice Re Applications for Amends to Licenses DPR-51,NPF-6 & NPF-38,authorizing Addition of Sys Energy Resources,Inc as Licensee & Requests Comments on Antitrust Issues ML20206J5741988-11-10010 November 1988 Forwards H Thompson as Balance of NRC Response to State of Tn Re Enrichment of Naturally Occurring Radionuclides in Proposed Facilities,Per NRC ML20206J5571988-11-0909 November 1988 Forwards NRC Review & Evaluation of Facilities Security Plans Discussing Equipment & Procedures Used by Applicant to Meet Requirements in 10CFR95.W/o Encl ML20195G2581988-11-0808 November 1988 Partially Deleted Memo Re Commissioner Carr 880113-15 Visit to Plant,Meeting W/State of Mo Officials & Visit to Mallinckrodt,Inc ML20205T6491988-11-0707 November 1988 Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20205R6731988-11-0404 November 1988 Forwards NRC Testimony of Jj Swift Addressing ASLB Inquiries of 881018 & Two Attachments.Related Correspondence ML20205N3691988-10-28028 October 1988 Advises That ASLB Tentatively Calling for Telcon on 881109 W/Parties & State of Tn to Discuss Need for Further Prehearing Conference & Other Scheduling Matters,Per 881026 Request.Served on 881031 ML20206B2481988-10-27027 October 1988 Notice of Significant Licensee Meeting 88-174 on 881118 in King of Prussia,Pa to Discuss Configuration Mgt ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20205K3321988-10-26026 October 1988 Forwards SER Re Const Mod & Licensing of & Application for CP for Facilities.Nrc Review of Safeguards/Security Plans for Two Proposed Facilities Sent to Board & Applicant.Telcon to Discuss Scheduling Matters Requested.W/O Encls ML20155H3621988-10-18018 October 1988 Requests Addl Info Re NRC Environ Assessments Submitted on 880914 for Uncontested Proceedings,To Complete Review of Adequacy of NEPA Assessments.Served on 881018 ML20204G0741988-10-17017 October 1988 Forwards Mh Mobley from State of Tn to NRC Not Received Until 881014.NRC Will Address Matters in Ltr in SER ML20205L2281988-10-12012 October 1988 Forwards AEOD/e807, Pump Damage Due to Low Flow Cavitation, in Response to Action Item 5 Assigned by EDO in 880406 Memo Re Diagnostic Evaluation Team Rept for Plant. NRR Issued Bulletin 88-004 Addressing Recirculation Problem ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20155C6941988-10-0505 October 1988 Advises That Review Briefing for Listed Plants Scheduled for 881013.Viewgraphs Encl ML20205Q4941988-10-0303 October 1988 Discusses Concerns Raised by State of Tn Re Abundance of Naturally Occurring Radioactivity in Alchemie Processing. Enrichment of Naturally Occurring Radioisotopes Will Not Pose Significant Health Hazard ML20206E0861988-09-28028 September 1988 Requests Verbal Concurrence W/Publishing Notice of Receipt of Petition for Rulemaking PRM-50-50,per 880926 Telcon W/ C Young.Related Info Encl 1990-02-26
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants ML20245E9441989-01-31031 January 1989 Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant ML20196C2701988-12-0202 December 1988 Notification of 881207 Meeting W/Util in Rockville,Md to Discuss Dcrdr Submittal of 880825 ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20206M9231988-11-23023 November 1988 Lists Questions Raised by Board Study of Licensee Environ Repts on Facilities,For Responses & Comments.Served on 881125 ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20206J6441988-11-16016 November 1988 Requests Responses to Listed Questions Re Proceeding, Including Explanation of Environ Consequences Caused by Movement of Centrifuges from State of Oh to State of Tn. Served on 881117 ML20206E6361988-11-14014 November 1988 Forwards Fr Notice Re Applications for Amends to Licenses DPR-51,NPF-6 & NPF-38,authorizing Addition of Sys Energy Resources,Inc as Licensee & Requests Comments on Antitrust Issues ML20206J5741988-11-10010 November 1988 Forwards H Thompson as Balance of NRC Response to State of Tn Re Enrichment of Naturally Occurring Radionuclides in Proposed Facilities,Per NRC ML20206J5571988-11-0909 November 1988 Forwards NRC Review & Evaluation of Facilities Security Plans Discussing Equipment & Procedures Used by Applicant to Meet Requirements in 10CFR95.W/o Encl ML20195G2581988-11-0808 November 1988 Partially Deleted Memo Re Commissioner Carr 880113-15 Visit to Plant,Meeting W/State of Mo Officials & Visit to Mallinckrodt,Inc ML20205T6491988-11-0707 November 1988 Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20205R6731988-11-0404 November 1988 Forwards NRC Testimony of Jj Swift Addressing ASLB Inquiries of 881018 & Two Attachments.Related Correspondence ML20205N3691988-10-28028 October 1988 Advises That ASLB Tentatively Calling for Telcon on 881109 W/Parties & State of Tn to Discuss Need for Further Prehearing Conference & Other Scheduling Matters,Per 881026 Request.Served on 881031 ML20206B2481988-10-27027 October 1988 Notice of Significant Licensee Meeting 88-174 on 881118 in King of Prussia,Pa to Discuss Configuration Mgt ML20205K3321988-10-26026 October 1988 Forwards SER Re Const Mod & Licensing of & Application for CP for Facilities.Nrc Review of Safeguards/Security Plans for Two Proposed Facilities Sent to Board & Applicant.Telcon to Discuss Scheduling Matters Requested.W/O Encls ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20155H3621988-10-18018 October 1988 Requests Addl Info Re NRC Environ Assessments Submitted on 880914 for Uncontested Proceedings,To Complete Review of Adequacy of NEPA Assessments.Served on 881018 ML20204G0741988-10-17017 October 1988 Forwards Mh Mobley from State of Tn to NRC Not Received Until 881014.NRC Will Address Matters in Ltr in SER ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20205L2281988-10-12012 October 1988 Forwards AEOD/e807, Pump Damage Due to Low Flow Cavitation, in Response to Action Item 5 Assigned by EDO in 880406 Memo Re Diagnostic Evaluation Team Rept for Plant. NRR Issued Bulletin 88-004 Addressing Recirculation Problem 1990-02-26
[Table view] |
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- August 11,1982 MLI)0 hah 00M FOR: D. UArent, Cnain.an, ACRS Subconnittee on Midland Plant -
Units 1 6 2 FHon: u. tisenor, Staf f Engineer hubJLLT: ACdd Sublu:VillTLt. UN MIDLAltu PLAf4T UNil51 & 2 - Justl 2,1982 WASdliab10!i, O.C.
I nave prepared tne attacned es eting sustury f or your review. Copfes are being distributed to the other ACRS menders and Subconnittee consultants for their inf on ation and coi,=nt. Correctims and additions will be included in tne Minutes of the nnecting.
Attacn:.ent :
M stated cc: ACR$ Hencers Acks Tecnnical Statf L. Epler, ACx5 Consultant N W. Lipinski, A(.kS Consultant J. usteroerg, ACKS Consultant .
E. Case, fMit E. buodain, hkR
- k. UeVoung, IL
- k. Minuque, KES U. Lisennut, fikk R. Vollr.er, hdk J. Keppler,f4HR T. hovak, NKk L. Adensa.n hRk Fo/A 4 w o2-D. Hood, hdR R. Hernan, fikk J. Knisnt, liRn gi g Fil.E: MIDLAND PLANT UNIT 1 & 2 0510000420 050730 PDH FOIA IIN UNNE R O S-60_2_P DR
. . . ... .. .A.f.M. . .. ...QEl.S.G!tER/.hgi..........a.11. 0?
orrice s ........................ ....................... .. . .
eva m > ........................ ................................................ ........................
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Nac roau m oo e sacu ono OFFiClAL RECORD COPY u o m i- m m
- (
i I
- PROPOSED
SUMMARY
l' OF THE JUNE 2,1982 MEETING OF THE SUBCOMMITTEE ON MIDLAND PLANT UNITS 1 8 2 PURPOSE:
The purpose of the meeting was to review the application of Consumers Power Company for a license to operate the Midland Plant Units 18 2.
l PRINCIPAL ATTENDEES:
ACRS Consumers Power Comp,ang
+ D. Okrent, Chairman J. Cook W. Mathis, ACRS Member T. Sullivan l D. Moeller, ACRS Member D. Budzik
! E. Epler, ACRS Consultant K. Drehobl W. Lipinski, ACRS Consultant 8. Harshe D. Fischer, Designatsed Fed. Empi. R. Hamm i J. McKinley, ACRS Staff J. Zabritski L. Gibson
- NRC Staff H. Slager R. Tedesco R. Polich l E. Adensam J. Pastor
- D. Hood J. Keninger R. Defayette G. Slade T. Dunning P. Jacobsen R. Eberly B. Margulio W. Hazelton R. Berry W. Jenson J. Mazetis Bechtel C. D. Sellers T. Ballweg M. Pratt Babcock & Wilcox 4
J. Taylor
(
MEETING HIGHLIGHTS, AGREEMENTS, AND REQUESTS
- 1. The NRC Staff indicated that the list of open itens and ifcensing conditions had not changed since the May 20-21,1982 Midland Plant Subcommittee meeting. .
MIOLAND
SUMMARY
t'
- 2. The Subcommittee members and consultants questioned the NRC Staff and Applicant on items in the operating license Safety Evaluation Report (OLSER).
- a. Dr. Okrent asked the Staff to discuss the question of natural circu-lation during a small break LOCA. The Staff was not prepared to address this item.
- b. In response to a question by Dr. Okrent, the Staff indicated there was no problem with regard to diesel generator accessibility subsequent to the probable maximum flood (PMF).
- c. Dr. Moeller asked what impact flooding might have on the evacuation of the Dow Chemical plant and on Midland's Emergency Plan. The Applicant said that the chemical plant would have to be shutdown and evacuated long before the power plant would be affected (since there is a signi-ficant dif ference in the elevation of the plants).
- d. When questioned about turbine missile open item resolution, the Staff referred Dr. Okrent to the discussion of turbine missiles contained in "NRC Staf f Responses To Questions By The ACRS Subcommittee During Meeting Of May 20-21, 1982 On Midland, Units 1 And 2."
- c. The Staff confirmed that credit cannot be taken for containment pressure when computing a pump's available net positive suction head (NPSH).
. f. While the Staff is concerned about the configuration of a plant's con-tainment isolation system, it has no criteria regarding containment isolation reliability.
- g. Midland's containment purge and vent valves are designed to operate under the containment's design differential pressure of 60 psi.
- h. The Applicant's failure analysis of its Feed Only Good Generators (FOGG)
System employs the single failure criterion.
- 3. The Subcommittee reviewed and discussed the NRC Staff's written response to concerns expressed in previous ACRS reports on Midland Plant, Units 1 and 2. l
i e
MIDLAND
SUMMARY
- 4. Mr. 8. Harshe, CPCo. described Midland's program for reducing the potential for common cause failures. He defined common cause failures
! as systems interactions. He described three types of systems interactions :
(ie., spatial, functional, and human) and explained how CPCo is methodically searching for each type. The scope of Midland's program includes both safety-grade / safety grade and nonsafety-grade / safety-grade types of interactions. Mr. Harshe identified several plant modtfications which have been made as a result of CPCO's search for adverse systems interactions.
- 5. Mr. R. Hamm, CPC0, outlined the functions, interfaces, and improve-ments that have been made in Midland's integrated control system (105). He compared Midland's ICS with the standard 88W ICS. Mr.
Hamm described CPCo's extensive efforts 'to preclude loss of power to both the ICS and the non-nuclear instrumentation (NN!). CPCo now has a non-safety grade loss of ICS/NNI power alarm in the control room. He mentioned evaluations of the ICS, NNI, and These EvaporatorSteamDemandDevelopment(ESDD)thatareongoing.
evaluations will essentially constitute a systems interaction study relative to the ICS.
- 6. Mr. J. Zabritski, CPCo, discussed the seismic and environment qualiff-cation of equipment important to plant safety. He mentioned the organizations that are participating in Midland's equipment quali-fication programs. He highlighted the elements of the equipment environmental qualification program and provided a status of the environment qualification review. Similarly, Mr. Zabritski discussed the elements and status of Midland's program to seismically qualify equipment.
- 7. Mr. L. Gibson, CPCo, described the various means of rer.oving re-actor decay heat at Midland following a shutdown or reactor trip. He it explained simplified system diagrams of the auxiliary feedwater (AFW) and decay heat renoval (OHR) systems. He indicated that each loop of the DHR system can handle the system's design heat load. He also said that one high pressure coolant injection pump operating at the power l
i operated relief valve setpoint is capable of removing the primary system's decay heat.
- 8. Mr. H. Slager, CPCo, outlined the bolting experiences at the Midland site. He listed four groups of low-alloy quenched and tempered The*,e bolts include:
bolts alch have failed or been found deficient.
Unit I reactor vessel anchor bolts, pipe whip restraint bolts, steam generator anchor bolts, and reactor coolant pump snubber anchor bolts.
l "he failure mechanism and corrective actions for the reactor vessel anchor bolt problem were discussed in detail. Mr. Slager described an ongoing low-alloy quenened and tempered bolt survey. The Staff i
l acknowledged the adequacy of CPCo's program to correct tiotting def t-i ciencies.
5,l*. ,
,' MIDLAND
SUMMARY
- 9. Mr. R. Polich, CPCo, summarized Midland's fire protection program. He indicated that the open item related to fire protection would soon be resolved. The potential for flooding and wetting of critical com-ponents was discussed. Mr. Polich highlighted fire damper design and operation (fire dampers are not gas-tight). Midland's ability to achieve and maintain hot shutdown in the event of a fire was mentioned.
- 10. Mr. B. Harshe, CPCo, discussed Midland's control room habitability and specific hazards existing at the Midland plant that could affect control room habitability. He explained how data was col-lected about potential hazards in order to establish the design basis for the plant and to identify potential worst case situations.
A number of these situations were analyzed in detail. Based on these analyses. CPCo has or will be instituting a number of plant pro-tective features. Plant protective features incorporate: telephone and radio communications with the 00W Chemical and Dow Corning plants, a hazardous gas monitoring system which can automatically isolate the control room, numerous control room design features, and self-contained breathing apparatus in the control room for plant operators.
Mr. Harshe also outlined the special habitability features of the various emergency response facilities at Midland. Dr. Hoeller ques-tioned CPCo on how it would assure itself of the adequacy of the control room heating and ventilation systems.
- 11. The Subcommittee discussed with the NRC Staff, the Applicant, and their consultants responses to questions raised by the ACRS Subcom-mittee on Midland Plant Units 1 and 2 during its May 20-21, 1982 Subcommittee meeting.
The Staff provided the Subcommittee with written "NRC Staff Responses To Questions By The ACRS Subcommittee During Meeting Of May 20-21,1982 On Midland Plant, Units 1 And 2." In general, the Subcommittee was satisfied with the Staff's responses. Dr. Okrent questioned the Staff on the cri-teria it is using to resolve the turbine missile open item. The Staff said that it was awaiting receipt of a GE report, which the Applicant is taking credit for, and that uses a turbine missile generation probability on the order of ten to the minus nine per year. The Staff, which used to assume that the probability of generating the missile was ten to the minus four per year, is now taking a close look at missile generation probabilities when it reviews an Applicant's calculations. The Staff is still using a damage criterion of ten to the minus seven per year.
The Applicant indicated that the two off site power supply lines could not interfere with each other if one of the supporting towers was to fall over.
In response to a request by Dr. Moeller, the Applicant described those systems at Midland which are capable of being drained and/or flushed. The Applicant's criteria for draining and flushing radioactive systems fits into its compre.
hensive program to control occupational exposure.
- 12. The Subcommittee chairman outlined some of the topics for discussion at the June 4,1982 ACRS full Committee meeting.
- 13. The meeting went into closed session to discuss Midland's plant security program and systems.