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| | issue date = 10/17/1991 | | | issue date = 10/17/1991 |
| | title = Transmits Powerplex Response Data Comparisons to Support Approval of Topical Rept PL-NF-90-001, Application of Reactor Analysis Methods for BWR Design & Analysis Dtd Aug 1990.Encl Data Comparisons Withheld (Ref 10CFR2.790)(b)) | | | title = Transmits Powerplex Response Data Comparisons to Support Approval of Topical Rept PL-NF-90-001, Application of Reactor Analysis Methods for BWR Design & Analysis Dtd Aug 1990.Encl Data Comparisons Withheld (Ref 10CFR2.790)(b)) |
| | author name = KEISER H W | | | author name = Keiser H |
| | author affiliation = PENNSYLVANIA POWER & LIGHT CO. | | | author affiliation = PENNSYLVANIA POWER & LIGHT CO. |
| | addressee name = BUTLER W R | | | addressee name = Butler W |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000387, 05000388 | | | docket = 05000387, 05000388 |
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| | page count = 8 | | | page count = 8 |
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| | =Text= |
| | {{#Wiki_filter:LERATED DI HUBUTION DEMON TION SYSTEM t |
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| | e REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:9110280248 DOC.DATE: 91/10/17 NOTARIZED: YES DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-'388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION KEISER,H.W. Pennsylvania Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R. Project Directorate I-2 |
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| | ==SUBJECT:== |
| | Transmits Powerplex response data comparisons to support approval of util application topical rept PL-NF-90-001, "Application of Reactor Analysis Methods for BWR Design & D Analysis for Aug 1990." |
| | S DISTRIBUTION CODE: APOID TITLE: Proprietary Review COPIES RECEIVED:LTR i Distribution ENCL Q SIZE: Q + |
| | Operating Reactor NOTES:LPDR 1 cy Transcripts. 05000387 A LPDR 1 cy Transcripts. 05000388 |
| | 'D RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PDl-2 LA 1 1' PD1-2 PD 1 1 RALEIGH,J. 3 INTERNAL: ACRS 6 6 AEOD OGC/HDS2 1 0 E 01 EXTERNAL: NRC PDR 1 0 NOTES: 2 2 R |
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| | D NOTE TO ALL "RIDS" RECIPIENTS: |
| | S PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15 |
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| | 4yw Pennsylvania Power 8 Light Company Two North Ninth Street ~Allentown, PA 18101-1179 ~ 215/774-5151 Harold W. Keiser Senior Vice President-Nuclear 215/7744194 OCT l7 $ 81 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Project Director Project Directorate I-2 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEIIANNA STEAM ELECTRIC STATION LICENSING METHODS: SUPPORTING INFORMATION Docket Nos. 50-387 PLA- 6 FIL R41-2 A and 50-388 ir W |
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| | ==References:== |
| | : 1. "Application of Reactor Analysis Methods for, BWR Design and Analysis", |
| | PI NF-90-001, August 1990. |
| | : 2. "Qualification of Transient Analysis'Methods for BWR Design and Analysis", PI NF-89-00$ , December 1989. |
| | : 3. PLA-3641, H.W. Ket'ser to W.R. Butler, "Licensing Methods: Plan for U1C7", dated August 29, 1991. |
| | |
| | ==Dear Dr. Butler:== |
| | |
| | To support the NRC's approval of PP&L's Applications Topical Report (Reference 1), we are transmitting data comparisons which PP&L discussed in a meeting with NRC and BNL representatives on October 4, 1991 at the NRC's White Flint office. This data was used to demonstrate that the current Siemens Nuclear Power Corporation (SNP) core monitoring system uncertainties are conservative for monitoring the core with PP&L generated input in the Susquehanna POWERPLEX core monitoring system. After discussion with the NRC staff and the reviewer, however, PP&L has agreed to use the more conservative SNP uncertainties, rather than the PP&L generated uncertainties. |
| | Please note that the data comparisons which are included in Atta'chment 1 are considered proprietary by SNP. As required by 10CFR2.790(b) an affidavit to support withholding this information from public disclosure is contained in Attachment 2. The proprietary portion of Attachment 1 will not be included in the approved version of the PP&L Applications Topical Report. |
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| | FILES R41-2/A7-8C PLA-3663 Dr. W. R. Butler As conveyed to Messrs. John Emmett and Andrew Dyszel, the transmittal of the enclosed material closes the last remaining issue identified during the review of PP&L's Applications Topical Report. Further, it is our understanding that the NRC will proceed with issuance of Safety Evaluation Reports for PP&L's Applications Topical Report (Reference 1) and Transient Analysis Topical Report (Reference 2). PP&L, in turn, is proceeding with the performance of the Unit 1 Cycle 7 reload analyses using the approach agreed to by PP&L and NRC (as described in Reference 3 and herein). |
| | In closing, PP&L would like to compliment the NRC and BNL representatives for their prompt response and cooperation in resolving this last remaining issue. Any questions on this submittal should be directed to Mr. R. Sgarro at (215) 774-7916. |
| | Very truly yours, H. W. Keiser Attachments cc: QgRC Document Contro13)eak.(original) |
| | NRC Region I Mr. G. S. Barber, NRC Sr. Resident Inspector - SSES Mr. J. J. Raleigh, NRC Project Manager - OWFN Mr. L. I. Kopp, NRR/SRXB-OWFN |
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| | ATI'ACIIMENT1 TO PLA-3663 FILES R41-2/A7-8C ATTACHMENT1 POWERPLEX TIP RESPONSE COMPARISONS TO SUPPORT APPROVAL OF PP&L'S APPLICATIONS TOPICAL REPORT (PL-NF-90-001) |
| | The Susquehanna data comparisons calculated by PP&L that are shown in this attachment support the conclusions that: 1) the POWERPLEX core monitoring system with PP&L generated CPM-2 input yields more accurate results than the POWERPLEX core monitoring system with SNP generated XFYRE input, and 2) the currently approved SNP power distribution uncertainties are conservative for Susquehanna when PP&L develops the input to the POWERPLEX core monitoring system. PP&L's core monitoring system, POWERPLEX, was developed by SNP and uses XTGBWR as the core simulation code and measured LPRM data to modify the XTGBWR calculated "base" power distribution to obtain a "measured" power distribution (i.e., UPDATE). |
| | The POWERPLEX nodal TIP RMS data presented in the following figures is an indication of how accurate the 3-D TIP response (i.e., power shape) is calculated by the core monitoring system prior to UPDATE. All the nodal TIP RMS values in the attached figures were calculated by PP&L from the "base" data. In all but a few cases, the nodal TIP RMS for POWERPLEX with CPM-2 input is less than that of POWERPLEX with XFYRE input, These results indicate that, for Susquehanna, POWERPLEX with CPM-2 input is more accurate in calculating the power shape than POWERPLEX with XFYRE input. This conclusion corroborates the PP&L uncertainty calculations presented in Reference 1-2. However, after discussions with the staff, PP&L has agreed to use the currently approved SNP set of power distribution uncertainties from Reference 1-3. Based on the above data comparisons, the SNP power distribution uncertainties are conservative for monitoring the core with CPM-2 input in the Susquehanna POWERPLEX core monitoring system. Therefore, the SNP uncertainties from Reference 1-3 will be used in the Safety Limit MCPR calculations in lieu of PP&L's proposed uncertainties. |
| | Please note that the PP&L results based on XFYRE are considered proprietary by Siemens Nuclear Power Corporation (SNP) and will not be included in the approved version of the PP&L Applications Topical Report. |
| | |
| | ==References:== |
| | 1-1 "Application of Reactor Analysis Methods for BWR Design and Analysis", PI NF-90-001, August 1990. |
| | 1-2 PI'A-3578, H.W. Keiser to W.R. Butler, "Final Response to RAI on PI NF-90-001", dated June 4, 1991. |
| | 1-3 "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis", XN-NF-80-19 (P)(A), Volume 1 and XN-NF40-19 (P)(A), Volume 1, Supplements 1 & 2, March 1983. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant ML20207G5051999-06-0707 June 1999 Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML20203G5821999-02-17017 February 1999 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety. Documents Listed in App D Being Withheld in Part (Ref FOIA Exemption 5) ML20202F4761999-01-29029 January 1999 First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety.App B Records Being Withheld in Part (Ref FOIA Exemption 7C) ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML20195J9101998-11-18018 November 1998 Forwards Notice of Withdrawal of Application for Amends to Facility Operating Licenses (Notice).Notice Has Been Filed with Ofc of Fr.Amends Would Have Revised TS to Eliminate HPCI Pump auto-transfer on High Suppression Pool Level ML20155F7201998-11-0303 November 1998 Final Response to FOIA Request for Documents.Documents Listed in App B Being Encl & Being Released in Entirety. Documents Listed in App C Being Withheld in Part (Ref Exemption 7C) ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998 Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21 ML18030A1001998-10-12012 October 1998 Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs ML18030A4311998-09-29029 September 1998 Forwards Rev 27 & 28 to SSES Emergency Plan ML20151W4951998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs for Region I IR 05000387/19980081998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved ML18030A0991998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved ML18026A4961998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations IR 05000387/19980031998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations ML20202F5501998-07-17017 July 1998 Responds to PP&L Corp Auditing Repts 739459-97,739459-1-97 & 739459-2-98 Re SSES Investigations Into Missed Alarm Tests ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML18030A4291998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue ML18017A2181998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance ML18026A2901998-06-0909 June 1998 Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed ML18026A2891998-05-22022 May 1998 Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods ML18026A4941998-05-12012 May 1998 Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document ML20202H1331998-04-16016 April 1998 Partially Deleted Ltr Re Concerns Raised to NRC Concerning PP&L Susquehanna Facility NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable1998-04-15015 April 1998 Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable ML20216B6811998-04-0101 April 1998 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Being Released in Entirety ML17159A2341998-03-30030 March 1998 Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998 Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML17159A1781998-03-0202 March 1998 Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4. PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998 Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998 Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213 ML20203M5071998-02-26026 February 1998 Final Response to FOIA Request for Documents.Records in App a Being Placed in PDR & Encl.Records in App B Partially Withheld (Ref FOIA Exemption 6) ML20203B5931998-02-23023 February 1998 Ack Receipt of & Wire in Amount of $55,000 in Payment for Civil Penatly Proposed by NRC Ltr . Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized ML18030A1001998-10-12012 October 1998 Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998 Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21 ML18030A4311998-09-29029 September 1998 Forwards Rev 27 & 28 to SSES Emergency Plan ML18030A0991998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved IR 05000387/19980081998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved ML18026A4961998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations IR 05000387/19980031998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations ML18017A2181998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance ML18030A4291998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue ML18026A2901998-06-0909 June 1998 Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed ML18026A2891998-05-22022 May 1998 Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods ML18026A4941998-05-12012 May 1998 Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document ML17159A2341998-03-30030 March 1998 Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998 Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998 Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl ML17159A1781998-03-0202 March 1998 Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4. PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998 Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213 ML20216B7031998-02-22022 February 1998 Partially Deleted Ltr Requesting Copy of OI Rept on Plant, Unit 2,case 1-96-039 PLA-4851, Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing1998-02-18018 February 1998 Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing ML20203M5791998-02-10010 February 1998 Enters Appeal Due to Lack of Response to FOIA Request 97-473 ML18030A0971998-02-0202 February 1998 Forwards Proprietary Response to RAI Re Proposed License Amend 209 to TS Supporting Cycle 11 Reload.Proprietary Info Withheld,Per 10CFR2.790 ML20203G6071998-01-26026 January 1998 Forwards Redacted Version of Pp&L,Inc Corporate Auditings Interim Rept 739459-97,dtd 971015 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept IR 05000387/19970031998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 ML18017A2931998-01-0606 January 1998 Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998 ML18030A4071998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 PLA-4828, Expresses Appreciation for Support Received by Former Project Manager C Poslusny1997-12-29029 December 1997 Expresses Appreciation for Support Received by Former Project Manager C Poslusny IR 05000387/19970041997-12-22022 December 1997 Resolves Commitments Made in Response to NOV Issued As Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval ML18026A4901997-12-22022 December 1997 Resolves Commitments Made in Response to NOV Issued as Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval ML20203M5741997-12-0505 December 1997 FOIA Request for Copy of Latest OI Rept on Susquehanna Ses Including All Exhibits & for Any Other Communication Between NRC & Susquehanna Ses/Pp&L PLA-4818, Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept1997-12-0404 December 1997 Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept 1999-09-08
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ACCESSION NBR:9110280248 DOC.DATE: 91/10/17 NOTARIZED: YES DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-'388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION KEISER,H.W. Pennsylvania Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R. Project Directorate I-2
SUBJECT:
Transmits Powerplex response data comparisons to support approval of util application topical rept PL-NF-90-001, "Application of Reactor Analysis Methods for BWR Design & D Analysis for Aug 1990."
S DISTRIBUTION CODE: APOID TITLE: Proprietary Review COPIES RECEIVED:LTR i Distribution ENCL Q SIZE: Q +
Operating Reactor NOTES:LPDR 1 cy Transcripts. 05000387 A LPDR 1 cy Transcripts. 05000388
'D RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PDl-2 LA 1 1' PD1-2 PD 1 1 RALEIGH,J. 3 INTERNAL: ACRS 6 6 AEOD OGC/HDS2 1 0 E 01 EXTERNAL: NRC PDR 1 0 NOTES: 2 2 R
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D NOTE TO ALL "RIDS" RECIPIENTS:
S PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15
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4yw Pennsylvania Power 8 Light Company Two North Ninth Street ~Allentown, PA 18101-1179 ~ 215/774-5151 Harold W. Keiser Senior Vice President-Nuclear 215/7744194 OCT l7 $ 81 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Project Director Project Directorate I-2 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEIIANNA STEAM ELECTRIC STATION LICENSING METHODS: SUPPORTING INFORMATION Docket Nos. 50-387 PLA- 6 FIL R41-2 A and 50-388 ir W
References:
- 1. "Application of Reactor Analysis Methods for, BWR Design and Analysis",
PI NF-90-001, August 1990.
- 2. "Qualification of Transient Analysis'Methods for BWR Design and Analysis", PI NF-89-00$ , December 1989.
- 3. PLA-3641, H.W. Ket'ser to W.R. Butler, "Licensing Methods: Plan for U1C7", dated August 29, 1991.
Dear Dr. Butler:
To support the NRC's approval of PP&L's Applications Topical Report (Reference 1), we are transmitting data comparisons which PP&L discussed in a meeting with NRC and BNL representatives on October 4, 1991 at the NRC's White Flint office. This data was used to demonstrate that the current Siemens Nuclear Power Corporation (SNP) core monitoring system uncertainties are conservative for monitoring the core with PP&L generated input in the Susquehanna POWERPLEX core monitoring system. After discussion with the NRC staff and the reviewer, however, PP&L has agreed to use the more conservative SNP uncertainties, rather than the PP&L generated uncertainties.
Please note that the data comparisons which are included in Atta'chment 1 are considered proprietary by SNP. As required by 10CFR2.790(b) an affidavit to support withholding this information from public disclosure is contained in Attachment 2. The proprietary portion of Attachment 1 will not be included in the approved version of the PP&L Applications Topical Report.
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FILES R41-2/A7-8C PLA-3663 Dr. W. R. Butler As conveyed to Messrs. John Emmett and Andrew Dyszel, the transmittal of the enclosed material closes the last remaining issue identified during the review of PP&L's Applications Topical Report. Further, it is our understanding that the NRC will proceed with issuance of Safety Evaluation Reports for PP&L's Applications Topical Report (Reference 1) and Transient Analysis Topical Report (Reference 2). PP&L, in turn, is proceeding with the performance of the Unit 1 Cycle 7 reload analyses using the approach agreed to by PP&L and NRC (as described in Reference 3 and herein).
In closing, PP&L would like to compliment the NRC and BNL representatives for their prompt response and cooperation in resolving this last remaining issue. Any questions on this submittal should be directed to Mr. R. Sgarro at (215) 774-7916.
Very truly yours, H. W. Keiser Attachments cc: QgRC Document Contro13)eak.(original)
NRC Region I Mr. G. S. Barber, NRC Sr. Resident Inspector - SSES Mr. J. J. Raleigh, NRC Project Manager - OWFN Mr. L. I. Kopp, NRR/SRXB-OWFN
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ATI'ACIIMENT1 TO PLA-3663 FILES R41-2/A7-8C ATTACHMENT1 POWERPLEX TIP RESPONSE COMPARISONS TO SUPPORT APPROVAL OF PP&L'S APPLICATIONS TOPICAL REPORT (PL-NF-90-001)
The Susquehanna data comparisons calculated by PP&L that are shown in this attachment support the conclusions that: 1) the POWERPLEX core monitoring system with PP&L generated CPM-2 input yields more accurate results than the POWERPLEX core monitoring system with SNP generated XFYRE input, and 2) the currently approved SNP power distribution uncertainties are conservative for Susquehanna when PP&L develops the input to the POWERPLEX core monitoring system. PP&L's core monitoring system, POWERPLEX, was developed by SNP and uses XTGBWR as the core simulation code and measured LPRM data to modify the XTGBWR calculated "base" power distribution to obtain a "measured" power distribution (i.e., UPDATE).
The POWERPLEX nodal TIP RMS data presented in the following figures is an indication of how accurate the 3-D TIP response (i.e., power shape) is calculated by the core monitoring system prior to UPDATE. All the nodal TIP RMS values in the attached figures were calculated by PP&L from the "base" data. In all but a few cases, the nodal TIP RMS for POWERPLEX with CPM-2 input is less than that of POWERPLEX with XFYRE input, These results indicate that, for Susquehanna, POWERPLEX with CPM-2 input is more accurate in calculating the power shape than POWERPLEX with XFYRE input. This conclusion corroborates the PP&L uncertainty calculations presented in Reference 1-2. However, after discussions with the staff, PP&L has agreed to use the currently approved SNP set of power distribution uncertainties from Reference 1-3. Based on the above data comparisons, the SNP power distribution uncertainties are conservative for monitoring the core with CPM-2 input in the Susquehanna POWERPLEX core monitoring system. Therefore, the SNP uncertainties from Reference 1-3 will be used in the Safety Limit MCPR calculations in lieu of PP&L's proposed uncertainties.
Please note that the PP&L results based on XFYRE are considered proprietary by Siemens Nuclear Power Corporation (SNP) and will not be included in the approved version of the PP&L Applications Topical Report.
References:
1-1 "Application of Reactor Analysis Methods for BWR Design and Analysis", PI NF-90-001, August 1990.
1-2 PI'A-3578, H.W. Keiser to W.R. Butler, "Final Response to RAI on PI NF-90-001", dated June 4, 1991.
1-3 "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis", XN-NF-80-19 (P)(A), Volume 1 and XN-NF40-19 (P)(A), Volume 1, Supplements 1 & 2, March 1983.
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