|
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209H7951999-07-16016 July 1999 Forwards NRC Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) (Including as-given Written Exam) for Tests Administered During Week of 990517 ML20209H6241999-07-16016 July 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered Wk of 990517 ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20212H7701999-06-18018 June 1999 Notification of 990715 Meeting with ABB-CE to Discuss Issues Re Steam Generator Welded Sleeve Problem Identified at Unit 1 ML20206S9241999-05-19019 May 1999 Forwards Insp Plans Re Prairie Island & Quad Cities,Which Identified Insp Activities That Would Be Completed at Facilities Over Next 6 to 12 Months ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20204J3521999-03-26026 March 1999 Requests That Encl Document Be Entered in NRC Pdr.Documents Consists of Composite of Attachments to NSP Ltrs, & 990308 & Should Be Linked to Both Ltr ML20198J4801998-12-21021 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss License Amend Request to Allow Limited Inoperability of Boric Acid Storage Tank Level Channels & Transfer Logic Channels for Required Testing & Maint ML20196F4021998-12-0101 December 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered on 981019-23 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20236U2071998-07-22022 July 1998 Forwards Corrected Copy of Ltr Transmitting Licensee Insp Repts 50-282/98-08 & 50-306/98-08.Date Has Been Corrected to Show Issuance on 980702 ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20217E9701998-04-20020 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Mod to Plant Units 1 & 2,which Will Add Diverse RTS to Shut Down Reactor in Event of ATWS Event ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20198S7391998-01-20020 January 1998 Forwards Operator Licensee Exam Info,Including Facility Outline,Initial Exam & as Given Operating Exam Administered During Wk of 971215 ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20202F6011997-12-0101 December 1997 Notification of 971211 Meeting W/Util in Rockville,Md to Discuss Intake Canal Seismic Issue at Plant ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20236N5001997-10-18018 October 1997 Forwards Technical Specification Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20236N4671997-10-14014 October 1997 Forwards TS Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20211A4651997-09-16016 September 1997 Requests for Waiver of Fee Billing for Replacement Pilot Insp.Nrr in Process of Developing headquarters-led Insp Procedure for Future Use at All NPP Licensee Sites ML20236N4031997-09-15015 September 1997 Forwards SER for Operability Assessment of Intermediate Range Neutron Monitoring Instrument While Instrument Undercompensated for Proper Detector Voltage for Re Ginna Nuclear Plant ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20217K8081997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Revised Methodology Used to Calculate MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration ML20217M0321997-08-13013 August 1997 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on Wk of 970616.Info Submitted for Processing Through Nudocs & Distribution to NRC Staff ML20210K6081997-08-13013 August 1997 Informs That Operator Licensing Exams Administered Wk of 970616 at Prairie Island,Units 1 & 2.Listed Info for Processing Through Nudocs & Distribution to NRC Staff, Including NRC PDR Also Encl ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20141F0451997-06-26026 June 1997 Notification of 970709 Meeting W/Nsp in Rockville,Maryland to Discuss ATWS Protection at PINGP & Possible Installation of Diverse Scram Sys ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147J2641997-04-16016 April 1997 Responds to 961126 Request Re Task Interface Agreement 96-0440, Defining Dry Cask Storage Terms. Basic Reasons to Return Cask to SFP & Unload Sf Assemblies Are Either to Retrive or Dispose or Respond to Event or Condition ML20140C3821997-04-0101 April 1997 Forwards Evaluation of TAR on Potential Unreviewed Safety Questions Re Auxiliary Feedwater Sys at Plant ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility 1999-09-23
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209H7951999-07-16016 July 1999 Forwards NRC Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) (Including as-given Written Exam) for Tests Administered During Week of 990517 ML20209H6241999-07-16016 July 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered Wk of 990517 ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20212H7701999-06-18018 June 1999 Notification of 990715 Meeting with ABB-CE to Discuss Issues Re Steam Generator Welded Sleeve Problem Identified at Unit 1 ML20206S9241999-05-19019 May 1999 Forwards Insp Plans Re Prairie Island & Quad Cities,Which Identified Insp Activities That Would Be Completed at Facilities Over Next 6 to 12 Months ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20204J3521999-03-26026 March 1999 Requests That Encl Document Be Entered in NRC Pdr.Documents Consists of Composite of Attachments to NSP Ltrs, & 990308 & Should Be Linked to Both Ltr ML20198J4801998-12-21021 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss License Amend Request to Allow Limited Inoperability of Boric Acid Storage Tank Level Channels & Transfer Logic Channels for Required Testing & Maint ML20196F4021998-12-0101 December 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered on 981019-23 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20236U2071998-07-22022 July 1998 Forwards Corrected Copy of Ltr Transmitting Licensee Insp Repts 50-282/98-08 & 50-306/98-08.Date Has Been Corrected to Show Issuance on 980702 ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20217E9701998-04-20020 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Mod to Plant Units 1 & 2,which Will Add Diverse RTS to Shut Down Reactor in Event of ATWS Event ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20198S7391998-01-20020 January 1998 Forwards Operator Licensee Exam Info,Including Facility Outline,Initial Exam & as Given Operating Exam Administered During Wk of 971215 ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20202F6011997-12-0101 December 1997 Notification of 971211 Meeting W/Util in Rockville,Md to Discuss Intake Canal Seismic Issue at Plant ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20236N5001997-10-18018 October 1997 Forwards Technical Specification Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20236N4671997-10-14014 October 1997 Forwards TS Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20211A4651997-09-16016 September 1997 Requests for Waiver of Fee Billing for Replacement Pilot Insp.Nrr in Process of Developing headquarters-led Insp Procedure for Future Use at All NPP Licensee Sites ML20236N4031997-09-15015 September 1997 Forwards SER for Operability Assessment of Intermediate Range Neutron Monitoring Instrument While Instrument Undercompensated for Proper Detector Voltage for Re Ginna Nuclear Plant ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20217K8081997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Revised Methodology Used to Calculate MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration ML20217M0321997-08-13013 August 1997 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on Wk of 970616.Info Submitted for Processing Through Nudocs & Distribution to NRC Staff ML20210K6081997-08-13013 August 1997 Informs That Operator Licensing Exams Administered Wk of 970616 at Prairie Island,Units 1 & 2.Listed Info for Processing Through Nudocs & Distribution to NRC Staff, Including NRC PDR Also Encl ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20141F0451997-06-26026 June 1997 Notification of 970709 Meeting W/Nsp in Rockville,Maryland to Discuss ATWS Protection at PINGP & Possible Installation of Diverse Scram Sys ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147J2641997-04-16016 April 1997 Responds to 961126 Request Re Task Interface Agreement 96-0440, Defining Dry Cask Storage Terms. Basic Reasons to Return Cask to SFP & Unload Sf Assemblies Are Either to Retrive or Dispose or Respond to Event or Condition ML20140C3821997-04-0101 April 1997 Forwards Evaluation of TAR on Potential Unreviewed Safety Questions Re Auxiliary Feedwater Sys at Plant ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility 1999-09-23
[Table view] |
Text
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., N NAR 1 1988 9 ;ox
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. MEMORANE"i FOR: Steven A.,Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation THRU: Martin Virgilio, Director ,
Project Directorate III-1 Division of Reactor Projects - III, IV, V !
& Special Projects i Wayne Hodges, Chief Reactor Systems Branch-FROM: Dominic C. 01 Ianni, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V ,
& Special Projects
SUBJECT:
MPA 005, UPPER PLENUM INJECTION STATUS
SUMMARY
REPORT
- 1. Enclosure 1 is a corrected copy of the Lead PM Summ.ry Report. The corrections indicated have been communicated to both the plant specific project manager (s) and plant specific reviewer (s) for proper updating of the data base tracking system.
- 2. Recommendations concerning the MPA generic priority (i.e., should it change and why) and should the MPA continue: (A "none" in this section means the generic' priority is acceptable and the MPA should continue as is.) None
- 3. Item for Senior Management Attention (Only list items which truly require senior management attention to resolve.) None
%galsi;m, Dominic C. Di Ianni, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V .
& Special Projects -
cc: Joe Gitter DISTRIBUTION David Wagner DOCKET OR CENTRAL FILE Carl Stahl NRC & LOCAL PDRs P031 READING FILE O [g $%202 l' GHOLAHAN p PDR DIIANNI RINGRAM CONTACT:
D. Di Ianni, NRR 49-21324 See previous concurrence
- SRXB* PM/P031: DRSP* C:SRXB* D/P031: DRSP* P 4
YHHsii DDilanni:cr MWHodges MVirgilio GHolahan 02/22/88 02/22/88 02/22/88 02/24/88 02/g6/88 0FFICIAL RECORD COPY F
MEMORANDUM ,FOR: Steven A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation THRU: Martin Virgilio, Director 9,roject Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects WayneH\ odges, Chief Reacto'rs Systems Branch
\
FROM: Dominic 03 Di Ianni, Project Manager Project Directorate III-1 Division ofxReactor Projects - III, IV, V
& Special Projects
SUBJECT:
N MPA 005, UPPER PLENUM INJECTION STATUS
SUMMARY
REPORT 1.
\
Enclosure 1 is corrected opy of the Lead PM Su vnary Report. The corrections indicated has i be'en communicated to both the plant specificprojectmanager(;)and}plantspecificreviewer(s)forproper updating of the data bast track ng system.
- 2. Recommendations concerning he MP generic priority (i.e., should it change and why) and should t.. 40A continue: (A "none" in this section means the generic priority =cceptable and the MPA should continue as is.) None
- 3. Rem for Senior Management Attention (Only l_ist ites ~hich truly require senior management attention to resolve.) Nons Dominic C. 01 Ianni, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects cc: see Gitter David Wagner {
l Carl Stahl i 1
I CONTACT-D. Di Ianni, NRR 49-21324 gh {
gp SRXB PM/PD31:DRSP C Rb D/PD31:DRSP AD:DRSP YHHsii DDilanni:ct WHodges MVirgilio GHolahan l 02/A2/88 02/tA/88 02 $ /88 02/B/88 02/ /88 0FFICIAL RECORD COPY
~
~
. ~
SUMMARY
REPORT MPA 005 Upper Plenum Injection for Westinghouse two-loop plants February 1, 1988 1 ,
i Westinghouse (W) two-loop plants have a low pressure safety injection system (LPSI) which injects water directly into the upper plenum of the reactor :
vessel (UPI). However, the approved ECCS evaluation models for two-loop '
plants are based on an ECCS system in which safety injection flow is injected directly into the cold leg of the reactor system. Because of the difference in the water injection between ECCS evaluation models and the actual UPI in the reactor vessels, the requirement of 10 CFR Appendix K Section II 5 may not be met. Six plants owned by four utilities are affected. These plants are j presently operating on the basis of a number of interim approaches for determining allowable peaking factors. The Westinghouse Owners Group consisting of Northern States Power Company and Wisconsin Electric Company i submitted a best estimate ECCS evaluation model using the SECY 83-472 approach to analyze the UPI for Prairie Island Nuclear Generation Plant and Point Beach I!uclear Generating station. The other plants (i.e. RE Ginna and Kewaunee) will be analyzed with a best estimate ECCS evaluation model developed by the Combustion Engineering (CE) Owners Group (Rochester Gas ,
Electric and Wisconsin Public Service Corporation). '
j Status a
! (A) Prairie Island / Point Beach 1
The staff review for the generic model is scheduled for completion on
] (both Prairie Island & Point Beach) August 15, 1988 and plant specific
! analyses should be completed on January 15, 1989. '
(B) RE Ginna/Kewaunee l A preliminary review of the CE evaluation model by the staff indicates i
the model is deficient in several areas that will require further work.
Because of these anomalies, a realistic schedule cannot be determined
- without further negotiation with CE Owners Group.
There is a single reviewer assigned for the Westinghouse and CE evaluation models in which effort is being devoted in series. Currently, the major effort is beir placed on the review of the Westinghouse evaluation model.
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