Rev 2 to Reload SE Methods for Application to Monticello Nuclear Generating PlantML20065K162 |
Person / Time |
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Site: |
Monticello |
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Issue date: |
04/12/1994 |
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From: |
NORTHERN STATES POWER CO. |
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To: |
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Shared Package |
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ML20065K161 |
List: |
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References |
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NSPNAD-8608, NSPNAD-8608-R02, NSPNAD-8608-R2, NUDOCS 9404190201 |
Download: ML20065K162 (2) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump ML20138G7791996-12-18018 December 1996 Rev 20 to Operational QA Plan ML20101K8541996-02-29029 February 1996 Application of 'Regional Exclusion w/Flow-Biased APRM Neutron Flux Scram' Stability Solution (Option I-D) to Monticello Nuclear Generating Plant ML20115E8921995-12-31031 December 1995 FERC Form 1:Annual Rept of Major Electric Utils,Licensees & Others for NSP (Minnesota) & (Wisconsin) ML20094N9321995-11-30030 November 1995 USNRC USI A-46 Resolution Seismic Evaluation Rept Monticello Nuclear Generating Plant ML20096C3931995-10-16016 October 1995 Reload Safety Evaluation Methods for Application to Monticello Nuclear Generating Plant ML20096C3581995-10-16016 October 1995 Qualification of Reactor Physics Methods for Application to Monticello ML20087F3041995-02-28028 February 1995 Non-proprietary Application of 'Regional Exclusion w/Flow- Biased APRM Neutron Flux Scram' Stability Solution (Option I-D) to Monticello Npp ML20096F6741995-02-28028 February 1995 Application of 'Regional Exclusion W/Flow-Biased APRM Neutron Flux Scram' Stability Solution (Option I-D) to Monticello Nuclear Power Plant ML20078J0041995-01-27027 January 1995 Rev 3 of Reload Safety Evaluation Methods for Application to Monticello Nuclear Generating Plant ML20072M4551994-08-24024 August 1994 Qualification of Reactor Physics Methods for Application to Monticello ML20065K1621994-04-12012 April 1994 Rev 2 to Reload SE Methods for Application to Monticello Nuclear Generating Plant ML1132102891993-11-30030 November 1993 Control Room Habitability Toxic Chemical Study. ML20248L4081992-09-0101 September 1992 Annual Rept Review of Meteorological Data 1991 Monticello & Prairie Island Stations ML20147F8131988-01-15015 January 1988 Lab Exam of Recirculation Line Decontamination Flange from Monticello Nuclear Power Station ML20235B3121987-08-31031 August 1987 Comparison of Monticello & Brunswick Recirculation Pump Trip ML20064E5091982-10-31031 October 1982 Design Rept for Recirculation Line Cap Repair, Rev 0 ML20009C0381981-07-31031 July 1981 IE Bulletin 79-14,Safety-Related Piping Sys,Phase 2 Inaccessible Piping Insp Rept. ML19345F2491980-12-31031 December 1980 Supplemental Reload Licensing Submittal for Facility Reload 8 (Cycle 9), Class 1 ML19209C2331979-10-0808 October 1979 IE Bulletin 79-14,Safety-Related Piping Sys,Phase 2 Accessible Piping Insp Rept, ML19250A5511979-10-0808 October 1979 IE Bulletin 79-14,Safety-Related Piping Sys,Phase 2 Accessible Piping Insp Rept. ML20127H3401978-03-15015 March 1978 ASME Code Section XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements. Including Revs 1-5 ML20127H3001978-02-0808 February 1978 Reactor Containment Bldg Integrated Leak Rate Test - Nov 1977 ML20127N8951977-12-31031 December 1977 Suppl 1 to, Design Rept & SE for Replacement of Spent Fuel Pool Storage Racks ML20091A2731977-08-17017 August 1977 Design Rept & Safety Evaluation Re Replacement of Spent Fuel Pool Storage Racks ML20058L3661976-12-10010 December 1976 Comparison of Existing Fire Protection Provisions to Guidelines Contained in SRP 9.5.1 ML20091A6211976-11-11011 November 1976 Redundant Design Feature Mods & Safety Evaluation for Reactor Bldg Crane Sys at Monticello Nuclear Generating Plant ML20090L8251976-10-31031 October 1976 Suppl to Short-Term Program,Plant-Unique Torus Support & Attached Piping Analysis ML20058L4711976-07-21021 July 1976 Suppl 1 to App I Filing ML20091A9561976-06-0404 June 1976 App I Filing,Consisting of App 2.5-A & App 2.5-B Re Annual & Monthly Joint Frequency Distributions Appropriate for Surface & Elevated Releases,Respectively ML20091A8981976-04-30030 April 1976 Failure Analysis of Type 304 Stainless Steel 4-Inch Recirculation Bypass Lines of Monticello BWR Power Plant ML20079C4111976-01-23023 January 1976 Reactor Containment Bldg Integrated Leak Test ML20079C4021976-01-13013 January 1976 Analysis & Safety Evaluation of Spent Fuel Shipping Cask Handling at Monticello Nuclear Generating Plant ML20125A6251975-07-0909 July 1975 MNGP Loss-of Coolant Accident Analyses Conformance W/ 10CFR50 App K ML20127N7541975-06-30030 June 1975 Loss-of-Coolant Accident Analysis Conformance w/10CFR50 App K (Jet Pump Plant), Dtd June 1975 ML20090L6211974-10-0101 October 1974 Preliminary Rept of Fuel Cask Drop Accident Analysis ML20056B9851974-05-31031 May 1974 Reactor Containment Bldg Integrated Leak Test - May 1974 ML20090L5331974-02-11011 February 1974 Errata to Technical Rept on GE 8 X 8 Fuel Assembly, ML20090M5521974-02-0808 February 1974 Rev 1 to, Monticello Nuclear Generating Plant Second Reload Submittal ML20090L5451974-02-0505 February 1974 Technical Rept on GE 8 X 8 Fuel Assembly ML20058L0041974-01-31031 January 1974 Permanent Plant Changes to Accommodate Equilibrium Core Scram Reactivity Insertion Characteristics ML20090M5051973-11-30030 November 1973 Second Reload Submittal ML20090M6151973-10-31031 October 1973 Cycle 2 Scram Reactivity Considerations,Analysis & Mods ML20024G8091973-07-31031 July 1973 Summary Technical Rept to Us AEC Directorate of Licensing on Secondary Containment Leak Rate Test,Jul 1973. ML20024G8141973-07-12012 July 1973 Cycle 2 Startup Rept. ML20058K8921973-05-31031 May 1973 Reactor Containment Bldg Integrated Leak Test for May 1973 1999-01-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203G1431998-02-10010 February 1998 Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531 ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20202F9161998-01-29029 January 1998 Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 ML20216D2071997-12-31031 December 1997 1997 Annual Rept for Northern States Power Co ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199G7051997-11-19019 November 1997 Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump 1999-09-30
[Table view] |
Text
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Attachment 1 4.2.3 CELI 1CM POWMU16IU2 Critical Power Ratio in caltulated using the General Electric BWR Thermal Analynio Bauis (GETAB) [18,19,20). The GEXL corrolation was obtained from Gonoral Electric for use t f Northern States Power as a part of the curront fuel contract.
The GEXL correlation has been incorporated into the DYNODE-B hot channel model.
Input to this model consists of tho bundle averago radial peaking factor, the relativo bundlo inlot flow, the bundle initial prosnure and inlet enthalpy, tho bundle R-factor, and the axial power dlotribution. The axial power diatribution g-uned in tho hkywie in given in Tablo 4.2-2, which in taken from Hoference 7.
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The R-factors are uupplied by General Electric.
The bundlo averago redial peaking factor and the relative bundio inlet flow factor are accumed constant throughout the transient and are calculated from tho throo-dimonotonal simulator (1) with the appropriate uncertaintion included (coo noction 4.2.1.1). The GEXL correlation safety limit (oue section 4.3.1) includou an 8.7% (ono atandard dovlation) uncertainty on the TIP readings. As long an the NSPflAD dotormined bundio power u.odel rollability factor (coo Section 4.2.1.1) la Joun than 8.7%, no additional uncertainty need be applied.
4Q Proper progranvning and uno of the GEXL correlation wao tented by comparing ntoady stato CPR valuon for the f u o .l. types of interent. Small differences will oxiot betwoon the GE and DYNODE-U valuou due to a ulight differencu in tho water property tablon uned. Theno comparloonn are chown in Table 4.2-3. Further comparinano are alao chown in Table 4.1-5.
Theco compartoonu show that NSPNAD han properly implemented the GEXL correlation and that it can be uned, along with the acnociated nafety ilmLt (see acetion 4.3.1), in liconoing calculati.onn. !
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Attachment 2 4.2.3 SEITICAL POWER RATIO Critical Power Ratio is calculated using the General' Electric BWR Thermal ;
Analysis Basis (GETAB) [18,19,20). The GEXL correlation was obtained from General Electric for use by Northern states Power as a part of the current fuel contract.
The GEKL correlation has been incorporated into the DYNODE-B hot channel model.
Input to this model consists of the bundle average radial peaking factor, the relative bundle inlet flow, the bundle initial pressure and inlet enthalpy, the bundle R-factor, and the axial power distribution. The axial power distribution used in the benchmarks is given in Table 4.2-2, which in taken from Reference 7.
3 Time varying axial power shapes will be used for all safety evaluations. This will provide additional conservatism over the benchmark cases. The R-factors are supplied by General Electric.
1 The bundle average redial peaking factor and the relative bundle inlet flow factor are assumed constant throughout *he transient and are calculated from the three-dimensional simulator (1) with the appropriate uncertainties included (see section 4.2.1.1). The GEXL correlation safety limit (see section 4.3.1)-
includes an 8.7% (one standard deviation) uncertainty on the TIP readings. As long as the NSPNAD determined bundle power model reliability factor (see Section 4.2.1.1) is less than 8.7%, no additional uncertainty need be applied.
Proper programming and use of the GEXL correlation was tested by comparing steady state CPR values for the fuel types of interest. Small differences will extut between the GE and DYNODE-B values due to a slight difference in the water property tables used. These comparisons are shown in Table 4.2-3. Further comparisons are also shown in Table 4.1-5.
Thene comparisons show that NSPNAD has properly implemented the GEXL correlation and that it can be used, along with the associated safety limit (see section 4.3.1), in licensing calculations.
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