Similar Documents at Maine Yankee |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211G4771999-08-27027 August 1999 Notification of 990908 Meeting with Util in Rockville MD to Discuss License Termination Plan That Myap & Contractors Are Preparing as Part of Decommissioning of Myaps ML20210P1311999-08-11011 August 1999 Notification of 990823 Meeting with Maine Yankee Atomic Power Co in Rockville,Md to Discuss License Termination Plan That Util & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20212H9551999-06-23023 June 1999 Notification of 990707 Meeting with Myap in Rockville, Maryland to Discuss License Termination Plan for Maine Yankee Atomic Power Station ML20196E1351999-06-23023 June 1999 Notification of 990707 Meeting with Util in Rockville,Md to Discuss License Termination Plan for Plant ML20207A6481999-05-19019 May 1999 Discusses Director Review of Plant Backfit Claim Re beyond- design-basis SFP Accidents & NRR Staff Response to Backfit Review Panel Findings ML20206H1571999-05-0606 May 1999 Notification of 990525 Meeting with Util in Rockville,Md to Discuss License Termination Plan That MYAPC & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20207G2921999-03-0404 March 1999 Provides Status on Wits Item 9600184, Clarity & Intent of NRC Safety Guide 1, as It Related to Isat Insp of Maine Yankee Atomic Power Station ML20196D5271998-11-24024 November 1998 Notification of 981215 Meeting for Docket 7200030 with Myap in Rockville,Md,To Discuss Plans for General License to Store Spent Fuel at Onsite ISFSI ML20155C3891998-10-29029 October 1998 Notification of 981102 Meeting with Util in Rockville,Md to Discuss industry-wide Power Reactor Decommissioning Issues as Well as Status of Plant Licensing Action ML20195C3941998-10-28028 October 1998 Discusses Results of Backfit Review Panel Re Emergency Preparedness Requirements for Maine Yankee Panel Determined That Staff Not Imposed Backfit on Licensee.Other Issues, Which Arose During Panel Deliberations,Identified & Encl ML20154L1371998-10-14014 October 1998 Notification of 981109 Meeting W/Util to Present NRC Staff Overview of Mgt of Decommissioning of Maine Yankee Atomic Power Station,Including Proposed Schedule ML20237B3941998-08-11011 August 1998 Forwards Hg Brack s Re Grossly Careless NRC Oversight of Licensees.Copy of Response to Brack Ltr Will Be Provided ML20236V9151998-07-31031 July 1998 Notification of 980814 Meeting W/Util Re Proposed License Defueled Security Plan ML20237A7521998-07-31031 July 1998 Notification of Cancelled 980814 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20236F6531998-06-30030 June 1998 Notification of 980710 Meeting W/Maine Yankee in Rockville,Md to Provide Myap Opportunity to Discuss Appeal of NRC Backfit Determination Re Maine Yankee Emergency Preparedness Exemption Request ML20248M0341998-06-0909 June 1998 Informs of Appointment to Backfit Review Panel to Review 980506 Appeal Filed by Myap Re NRC Determination Involving Backfit Claim Made by Licensee Under 10CFR50.109.Util Requests for Exemption from EP Requirements Unwarranted ML20248A4391998-05-26026 May 1998 Notification of 980609 Meeting W/Util in Rockville,Md to Discuss Maine Yankee Spent Fuel Heatup Analysis in Support of Emergency Plan & Financial Protection Exemption Requests ML20247N3471998-05-0808 May 1998 Responds to 980126 Memo Requesting Action Taken as Result of Event Inquiry - Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20247N3001998-05-0505 May 1998 Responds to 980210 Memo Re Event Inquiry Involving Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20217K4941998-04-28028 April 1998 Notification of 980501 Meeting W/Licensee in Rockville,Md to Discuss Defueled Security Plan ML20217M6221998-04-28028 April 1998 Notification of 980501 Meeting W/Util in Rockville,Md to Discuss Util Defueled Security Plan.Meeting Cancelled ML20216C4421998-04-0808 April 1998 Notification of 980423 Predecisional Enforcement Conference W/Myap in King of Prussia,Pennsylvania to Discuss Apparent Violations Identified During Three Investigations Conducted by Oi,As Transmitted on 971219 to Myap ML20199B2621998-01-13013 January 1998 Notification of Significant Licensee Meeting 98-02 W/Util on 980128 to Discuss Licensee Approach to Upcoming Decontamination of Reactor Sys,Design for Sf Island Concept & Use of 10CFR50.59 for Sys Safety re-classification ML20198P7321998-01-12012 January 1998 Notification of 980121 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20199C2241997-11-12012 November 1997 Notification of 971125 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Proposed Maine Yankee Atomic Power Station Defueled Technical Specifications ML20198S9401997-11-0606 November 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Myaps Defueled TSs ML20217G4061997-10-0707 October 1997 Notification of 971106 Meeting W/Licensee in Wiscasset,Me to Solicit Public Comments on Plant Post Shutdown Decommissioning Activities Rept.Meeting Agenda Encl ML20211G0331997-09-29029 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970609-12 IR 05000309/19970041997-09-29029 September 1997 Forwards NRC Operator Licensing Exam Rept 50-309/97-04OL (Including Completed & Graded Tests) for Tests Administered on 970609-12 ML20217E1631997-09-26026 September 1997 Revised Notification W/Agenda Change of 971007 Public Meeting in Wiscasset,Maine,To Brief Public on Regulatory Process for Decommissioning of NPP ML20217E2741997-09-24024 September 1997 Requests That Mk Webb Be Added to Site Access Authority.Site Access Were Completed & Thus Capable of Safe Conduct in Radiologically Restricted Areas ML20217C1381997-09-22022 September 1997 Notification of 971007 Meeting W/Public in Wicasset,Maine to Discuss Regulatory Process for Decommissioning of Npp. Meeting Held in Response to Recent Announcement by Myapco to Permanently Cease Operation of Myaps ML20217B0741997-09-0303 September 1997 Notification of 970903 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Independent Sf Storage Installation Options Available to Maine Yankee for Storage of Sf.Notice Being Reissued to Revise Meeting Room Number ML20216A9881997-08-29029 August 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Independent Spent Fuel Storage Installation Options Available to Plant for Storage of Spent Fuel ML20210Q7291997-08-21021 August 1997 Forwards OIG Audit Rept Entitled, NRC Needs Comprehensive Plan to Resolve Regulatory Issues. Rept Reflects Results of OIG Audit of Agency Response to Events at Plants ML20217K8121997-08-13013 August 1997 Notification of 970820 Meeting W/Util in Rockville,Md to Discuss Decommissioning Activities ML20148D1731997-05-23023 May 1997 Forwards Maine Yankee Restart Action Plan for Review & Approval in Accordance W/Nrc Inspection Manual Chapter 0350. RAP Contains List of Issues That NRC Will Inspect to Assess Licensee Compliance W/Applicable Requirements.W/O Encl ML20148D1701997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-58 W/Util on 970606 in King of Prussia,Pa to Discuss Licensee Approach to Resolve Cable Separation Issues at Plant ML20236N2211997-05-0505 May 1997 Discusses Interpretation of Plant TS Re Acceptability of Grab Sampling on Leakage Detection Sys within Meaning of TS 3.14A ML20137U0031997-04-10010 April 1997 Forwards Proposed Response to Ltr from H Myers & Informs of No Need for Further Commission Review ML20137M6141997-04-0303 April 1997 Submits Documents Being Released to Public Re DSI-11, Operating Reactor Program Oversight ML20137E2041997-03-24024 March 1997 Requests Copy of Maine Yankee Restart Readiness Plan & 10CFR50.54(f) Response ML20137H4341997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-30 W/Util on 970403 in Wiscasett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20137H4361997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-31 W/Util on 970403 in Wiscassett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20136F9561997-03-13013 March 1997 Notification of 970320 Meeting W/Licensee to Discuss Proposed TS Change 194 Re Operation W/Reduced Reactor Coolant Sys Flow Rate ML20136F9651997-03-13013 March 1997 Notification of 970326 Meeting W/Licensee in Rockville,Md to Discuss SG Insp Plans & Contingencies ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20136F2431997-02-27027 February 1997 Notification of Significant Licensee Meeting 97-21 W/Util on 970311 to Discuss Apparent Violations Identified in Listed NRC Insp Repts ML20137M8101997-02-18018 February 1997 Informs That Paper Very Difficult to Get One Arms Around in Part Because It Tries to Deal Simultaneously W/Licensing, Insp & Performance Assessment in Each of Options & in Part Because Paper Implicit Assumption Ongoing Millestone. ML20134J9981997-02-10010 February 1997 Notification of 970212 Meeting W/Listed Attendees in Rockville,Md to Discuss Pending Phase I Mgt Svcs Agreement Between MYAPC & Nuclear Entergy,Inc 1999-08-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211G4771999-08-27027 August 1999 Notification of 990908 Meeting with Util in Rockville MD to Discuss License Termination Plan That Myap & Contractors Are Preparing as Part of Decommissioning of Myaps ML20210P1311999-08-11011 August 1999 Notification of 990823 Meeting with Maine Yankee Atomic Power Co in Rockville,Md to Discuss License Termination Plan That Util & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20212H9551999-06-23023 June 1999 Notification of 990707 Meeting with Myap in Rockville, Maryland to Discuss License Termination Plan for Maine Yankee Atomic Power Station ML20196E1351999-06-23023 June 1999 Notification of 990707 Meeting with Util in Rockville,Md to Discuss License Termination Plan for Plant ML20207A6481999-05-19019 May 1999 Discusses Director Review of Plant Backfit Claim Re beyond- design-basis SFP Accidents & NRR Staff Response to Backfit Review Panel Findings ML20206H1571999-05-0606 May 1999 Notification of 990525 Meeting with Util in Rockville,Md to Discuss License Termination Plan That MYAPC & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20207G2921999-03-0404 March 1999 Provides Status on Wits Item 9600184, Clarity & Intent of NRC Safety Guide 1, as It Related to Isat Insp of Maine Yankee Atomic Power Station ML20196D5271998-11-24024 November 1998 Notification of 981215 Meeting for Docket 7200030 with Myap in Rockville,Md,To Discuss Plans for General License to Store Spent Fuel at Onsite ISFSI ML20155C3891998-10-29029 October 1998 Notification of 981102 Meeting with Util in Rockville,Md to Discuss industry-wide Power Reactor Decommissioning Issues as Well as Status of Plant Licensing Action ML20195C3941998-10-28028 October 1998 Discusses Results of Backfit Review Panel Re Emergency Preparedness Requirements for Maine Yankee Panel Determined That Staff Not Imposed Backfit on Licensee.Other Issues, Which Arose During Panel Deliberations,Identified & Encl ML20154L1371998-10-14014 October 1998 Notification of 981109 Meeting W/Util to Present NRC Staff Overview of Mgt of Decommissioning of Maine Yankee Atomic Power Station,Including Proposed Schedule ML20237B3941998-08-11011 August 1998 Forwards Hg Brack s Re Grossly Careless NRC Oversight of Licensees.Copy of Response to Brack Ltr Will Be Provided ML20236V9151998-07-31031 July 1998 Notification of 980814 Meeting W/Util Re Proposed License Defueled Security Plan ML20237A7521998-07-31031 July 1998 Notification of Cancelled 980814 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20236F6531998-06-30030 June 1998 Notification of 980710 Meeting W/Maine Yankee in Rockville,Md to Provide Myap Opportunity to Discuss Appeal of NRC Backfit Determination Re Maine Yankee Emergency Preparedness Exemption Request ML20248M0341998-06-0909 June 1998 Informs of Appointment to Backfit Review Panel to Review 980506 Appeal Filed by Myap Re NRC Determination Involving Backfit Claim Made by Licensee Under 10CFR50.109.Util Requests for Exemption from EP Requirements Unwarranted ML20248A4391998-05-26026 May 1998 Notification of 980609 Meeting W/Util in Rockville,Md to Discuss Maine Yankee Spent Fuel Heatup Analysis in Support of Emergency Plan & Financial Protection Exemption Requests ML20247N3471998-05-0808 May 1998 Responds to 980126 Memo Requesting Action Taken as Result of Event Inquiry - Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20247N3001998-05-0505 May 1998 Responds to 980210 Memo Re Event Inquiry Involving Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20217K4941998-04-28028 April 1998 Notification of 980501 Meeting W/Licensee in Rockville,Md to Discuss Defueled Security Plan ML20217M6221998-04-28028 April 1998 Notification of 980501 Meeting W/Util in Rockville,Md to Discuss Util Defueled Security Plan.Meeting Cancelled ML20216C4421998-04-0808 April 1998 Notification of 980423 Predecisional Enforcement Conference W/Myap in King of Prussia,Pennsylvania to Discuss Apparent Violations Identified During Three Investigations Conducted by Oi,As Transmitted on 971219 to Myap ML20199B2621998-01-13013 January 1998 Notification of Significant Licensee Meeting 98-02 W/Util on 980128 to Discuss Licensee Approach to Upcoming Decontamination of Reactor Sys,Design for Sf Island Concept & Use of 10CFR50.59 for Sys Safety re-classification ML20198P7321998-01-12012 January 1998 Notification of 980121 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20199C2241997-11-12012 November 1997 Notification of 971125 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Proposed Maine Yankee Atomic Power Station Defueled Technical Specifications ML20198S9401997-11-0606 November 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Myaps Defueled TSs ML20217G4061997-10-0707 October 1997 Notification of 971106 Meeting W/Licensee in Wiscasset,Me to Solicit Public Comments on Plant Post Shutdown Decommissioning Activities Rept.Meeting Agenda Encl ML20211G0331997-09-29029 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970609-12 IR 05000309/19970041997-09-29029 September 1997 Forwards NRC Operator Licensing Exam Rept 50-309/97-04OL (Including Completed & Graded Tests) for Tests Administered on 970609-12 ML20217E1631997-09-26026 September 1997 Revised Notification W/Agenda Change of 971007 Public Meeting in Wiscasset,Maine,To Brief Public on Regulatory Process for Decommissioning of NPP ML20217E2741997-09-24024 September 1997 Requests That Mk Webb Be Added to Site Access Authority.Site Access Were Completed & Thus Capable of Safe Conduct in Radiologically Restricted Areas ML20217C1381997-09-22022 September 1997 Notification of 971007 Meeting W/Public in Wicasset,Maine to Discuss Regulatory Process for Decommissioning of Npp. Meeting Held in Response to Recent Announcement by Myapco to Permanently Cease Operation of Myaps ML20217B0741997-09-0303 September 1997 Notification of 970903 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Independent Sf Storage Installation Options Available to Maine Yankee for Storage of Sf.Notice Being Reissued to Revise Meeting Room Number ML20216A9881997-08-29029 August 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Independent Spent Fuel Storage Installation Options Available to Plant for Storage of Spent Fuel ML20210Q7291997-08-21021 August 1997 Forwards OIG Audit Rept Entitled, NRC Needs Comprehensive Plan to Resolve Regulatory Issues. Rept Reflects Results of OIG Audit of Agency Response to Events at Plants ML20217K8121997-08-13013 August 1997 Notification of 970820 Meeting W/Util in Rockville,Md to Discuss Decommissioning Activities ML20148D1731997-05-23023 May 1997 Forwards Maine Yankee Restart Action Plan for Review & Approval in Accordance W/Nrc Inspection Manual Chapter 0350. RAP Contains List of Issues That NRC Will Inspect to Assess Licensee Compliance W/Applicable Requirements.W/O Encl ML20148D1701997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-58 W/Util on 970606 in King of Prussia,Pa to Discuss Licensee Approach to Resolve Cable Separation Issues at Plant ML20236N2211997-05-0505 May 1997 Discusses Interpretation of Plant TS Re Acceptability of Grab Sampling on Leakage Detection Sys within Meaning of TS 3.14A ML20137U0031997-04-10010 April 1997 Forwards Proposed Response to Ltr from H Myers & Informs of No Need for Further Commission Review ML20137M6141997-04-0303 April 1997 Submits Documents Being Released to Public Re DSI-11, Operating Reactor Program Oversight ML20137H4361997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-31 W/Util on 970403 in Wiscassett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20137E2041997-03-24024 March 1997 Requests Copy of Maine Yankee Restart Readiness Plan & 10CFR50.54(f) Response ML20137H4341997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-30 W/Util on 970403 in Wiscasett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20136F9561997-03-13013 March 1997 Notification of 970320 Meeting W/Licensee to Discuss Proposed TS Change 194 Re Operation W/Reduced Reactor Coolant Sys Flow Rate ML20136F9651997-03-13013 March 1997 Notification of 970326 Meeting W/Licensee in Rockville,Md to Discuss SG Insp Plans & Contingencies ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20136F2431997-02-27027 February 1997 Notification of Significant Licensee Meeting 97-21 W/Util on 970311 to Discuss Apparent Violations Identified in Listed NRC Insp Repts ML20138M2431997-02-21021 February 1997 Staff Requirements Memo Re Briefing by Maine Yankee & NRC on 970204 Concerning Status of Corrective Actions at Facility ML20137M8101997-02-18018 February 1997 Informs That Paper Very Difficult to Get One Arms Around in Part Because It Tries to Deal Simultaneously W/Licensing, Insp & Performance Assessment in Each of Options & in Part Because Paper Implicit Assumption Ongoing Millestone. 1999-08-27
[Table view] |
Text
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NUCLEAR REGULATORY COMMISSION
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9 March 4, 1999 f:
- MEMORANDUM TO: ' William D. Travers
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Executive Director for Operations f
FROM: Samus! J. Collins, Director Office of Nuclear Reactor Re n i
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SUBJECT:
STATUS REPORT ON WITS ITEM 9600184, "Cl.ARITY AND INTENT
' )
OF NRC SAFETY GUIDE 1" l l
. 1 One of the issues identified by the NRC independent Safety Assessment Team (ISAT)
! . inspection at the Maine Yankee Atomic Power Station (in a report dated October 7,1996) was 3
[ the inclusion of containment accident pressure (containment overpressure) in determining
- . whether adequate net positive suction head (NPSH) exists for the emergency core cooling l i
! system and the containment heat removal pumps following a design-basis loss-of-coolant accident (LOCA). As a result of the review of this issue during and following the ISAT 2
inspection, tne NRC staff questioned the guidance in NRC Safety Guide 1. " Net Positive Suction
' Head for Emergency Core Cooling and Containment Heat Removal System Pumps," dated
- November 2,1970, related to reliance on containment overpressure for ensuring adequate
- NPSH for these pumps. This issue became WITS Item 9600184. The time period for responding to this issue was extended as a result of the issuance of Generic Letter (GL) 97-04,
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- " Assurance of Adequate Net Positive Suction Head for Emergency Core Cooling and 1 Containment Heat Removal Pumps," dated October 7,1997, so as to provide time for staff p revi6w of the industry responses since these were directly related to the question raised by the I l i WITE item. l i
l
- WITS 9600184 requests that the staff Review and clarify the staff's criteria relative to relying on containment overpressure for )
ensuring appropriate NPSH for emergency core cooling and containment heat removal pumps. The staff is already conducting a separate program to determine if and how all plants, including Maine Yankee, meet these criteria. Upon review of this information, the staff will determine the measures to be taken for thoss plants not in compliance with the ;
cnteria.
l We are continuing our review of licensee responses to GL 97-04. As of February 19,1999, the staff has completed the review of 88 of 103 plants for GL 97-04. The remaining reviews requia further staff discussion with licensees. The major issue has been the need to clarify the licensing basis with respect to the use of containment overpressure in NPSH calculations. The need for containment overpressure comes from several different factors, in general, the older plants have more of a need for containment ovaerpressore. Only a few pressurized water CONTACT: R. Lobel, SCSB:DSSA ;
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- William D. Travers ,
i reactors (PWRs) need containment overpressure to ensure adequate NPSH. The staff i ' considers credit for containment overpressure that has not been previously reviewed and 1 . approved by the staff to be an unreviewed safety question as defined in 10 CFR 50.59.
- Licensees have submitted revised analyses and licensing amendments, as appropriate, to resolve this issue. The staff has discussed this issue with the Advisory Committee on Reactor
. Safeguards (ACRS), and the ACRS agrees with the staff approach to this issue (see letter from
,' R. L. Seale, Chairman, ACRS, to NRC Chairman Jackson, dated December 12,1997). Some j enforcement actions have also been taken.
l The staff anticipates'that the remaining reviews will be closed by October 1,1999.
i The Office of Nuclear Regulatory Research is currently working on a related issue, Generic
] Safety issue (GSI) 191, " Assessment of Debris Accumulation on Pressurized Water Reactor :
j Sump Performance." GSI 191 deals with the adequacy of the design of PWR containment
- emergency sumps with respect to LO% generated debris, an issue with a direct impact on NPSH, (This issue was resolved for boiling water reactors with the issuance of NRC j Bu'!etin 96-03. " Potential Plugging of Emergency Core Cooling Suction Strainers ty Debris in i
- Boiling Water Reactors.") GSI 191 is not scheduled to be completed until 2001. When this
. issue is resolved, the staff will assess the need to revise the present regulatory guidance related .
- to NPSH.
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William DcTravers 1
. - reactors (PWRs) need containment overpressure to ensure adequate NPSH. The staff considers credit for containment overpressure that has not been previously reviewed and '
approved by the staff to be an unreviewed safety question as defined in 10 CFR 50.59.
Licensees have submitted revised analyses and licensing amendments, as appropriate, to l resolve this issue. The staff has discussed this issue with the Advisory Committee on Reactor .
Safeguards (ACRS), and the ACRS agrees with the staff approach to this issue (see letter from
' R. L. Seale, Chairman, ACRS,% NRC Chairman Jackson, dated December 12, j997). Some ,
enforcement actions have also been taken.
t.
The staff anticipates that the remaining reviews will be closed by October 1,1999.
h The Office of Nucleaf Regulatory Research is currently working on a related issue, Generic j
- Safety issue (GSI) 191, " Assessment of Debris Accumulation on Pressurized Water Reactor !
- Sump Performance."' GSI 191 deals with the adequacy of the design of PWR containment ,
emergency' sumps with respect to LOCA-generated debris, an issue with a direct impact on !
NPSH. (This issue was ;esolved for boiling water reactors with the issuance of NRC i
Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in .
1
' Boiling Water Reactors.") GSI 191 is not scheduled to be completed until 2001. When this issue is resolved, the staff will assess the need to revise the present regulatory guidance related to NPSH.
e
. DISTRIBUTION:
' R. Elliott . K.Kavanagh
. A. Serkiz M. Marshall .
T. Collins ~ . R. Zimmerman
~ J. Kudrick -PDR File Center .- SCSB R/F (2)
M. Bridgers A.Thadani W.- Kane F Miraglia l
P. Norry M.Knapp J. Blaha P. Magnanelli NRR Mailroom
- See previous concurrences
- DOCUMENT NAME: RG182 WIT.5
~ To receive e cor of this document, hdcate in the boa: "C" = Copy without ettachment/ enclosure 'E' = Copy with attachment / enclosure "N" = No copy j OFFICE - SCSB:DSSA:NRR- l BC:SCSB:DSSA -l TECH ED D:DSSA l '
NAME- RLobel:bw CBerlinger BCalure GHolahan DATE 1/06/99* - 1/07/99* 1/04/90* 1/20/99*
OFFICE - ADT:NRR - l D:NRR pn l - l l NAME <
BSheron L SCollins '
DATE 2/22/99* 'l 3/lf /99 2/ /99 2/ /99
. OFFICIAL RECORD COPY !
1 l
O' s; ,
]: I William D. Travers reactors (PWRs) need containment overpressure to ensure adequate NPSH. The staff considers credit for containment overpressure that has not been previously reviewed and approved by the staff to be an unreviewed safety question as defined in 10 CFR 50.59.
Licensees have submitted revised analyses and licensing amendments, as appropriate, to resolve this issue. The staff has discussed this issue with the Advisory Committee on Reactor Safeguards (ACRS), and the ACRS agrees with the staff approach to this issue (see letter from R. L. Seale, Chairman, ACRS, to NRC Chairman Jackson, dated December 12,1997). Some enforcement actions have also been taken.
The staff anticipates that the remaining reviews will be closed by October 1,1999.
The Office of Nuclear Regulatory Research is currently working on a related issue, Generic Safety issue (GSI) 191, " Assessment of Debris Accumulation on Pressurized Water Reactor Sump _ Performance." GSI 191 deals with the adequacy of the design of PWR containment emergency sumps with respect to LOCA-generated debris, an iscue with a direct impact on i NPSH. (This issue was resolved for boiling water reactors with the issuance of NRC Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suc"on Strainers by Debris in Boiling Water Reactors.") GSI 191 is not scheduled to be completed until 2001. When this issue is resolved, the staff will assess the need to revise the present regulatory guidance related
. to NPSH.
DISTRIBUTION:
R. Elliott K.Kavanagh ~
A. Serkiz M. Marshall T. Collins - R. Zimmerman i J. Kudrick PDR l
^
File Center SCSB R/F (2)
M. Bridgers A. Thadani W. Kane F. Miraglia P. Norry M. Knapp J. Blaha P. Magnanelli -
NRR Mailroom
- See previous concurrences DOCUMENT NAME: RG182 WIT.5 To receive e cop ' of this document indicats in the bos: 'C' = Copy without ettechment/ enclosure *E' = Copy with attachment / enclosure *N" = No copy OFFICE ' SCSB:DSSA:NRR l BC:SCSB:DSSA l TECH ED l D:DSSA l NAME '
RLobel:bw CBerlinnen BCalure GHolahan DATE 1/06/99*. 1/07/99* -
1/04/99* 1/20/99*
i OFFICE . ADT:NRR l D:NRR g(Q- l l l NAME BSheron L SCollins '
DATE 2/22/99*
3/4 /99 2/ /99 2/ /99 OFFICIAL RECORD COPY
.