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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20153F0511998-09-21021 September 1998
Rev 2 to MNGP Colr,Cycle 19
ML20153E9361998-09-0808 September 1998
Rev 1 to MNGP Colr,Cycle 19
ML20217D8731998-04-13013 April 1998
Rev 0 to MNGP Colr,Cycle 19
ML20129K3221996-11-11011 November 1996
Rev 3 to Monticello Nuclear Generating Plant COLR for Cycle 18
ML20115H2851996-07-11011 July 1996
Rev 2 to MNGP COLR for Cycle 18
ML20112C2311996-05-18018 May 1996
Rev 1 to Monticello Nuclear Generating Plant COLR for Cycle 18
ML20112A2501996-05-14014 May 1996
Rev 0 to Monticello Nuclear Generating Plant COLR for Cycle 18
ML20073F7001994-09-22022 September 1994
Rev 0 of Monticello Nuclear Generating Plant COLR for Cycle 17
ML20070C2791994-06-24024 June 1994
Rev 2 to Core Operating Limits Rept for Cycle 16
ML20062N8801994-01-0404 January 1994
Proposed Rev to Page 1 of 8 from Colr
ML20003E5701981-03-31031 March 1981
Supplemental Reload Licensing Submittal for Monticello Nuclear Generating Plant Reload 8 (Cycle 9).
ML19210E2831979-11-30030 November 1979
Suppl Reload Licensing Submittal,Reload 7.
ML20024G8161974-12-11011 December 1974
Page A-2,inadvertently Omitted from 741211 Fuel Cycle Reload Rept
ML20076M7311974-12-11011 December 1974
Third Reload Submittal
ML20056B9881974-07-31031 July 1974
Cycle 3 Startup Rept & Summary Status of Fuel Rept
1998-09-08
[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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Reference 2 stater that even though MLHrn limit s are r'et , power '.zould be reduccJ at the end of Cycle 3 unless additional analys is was done. Ar stated, this condition exit.ted because of concern that MCpR may have been limiting if MCpK calculations were perionned. Since cycle 3 calculations bound Cycle 4 conditions, the MCllrR in Cycle 4 is more cont crvative than the acceptable valu< calculatcJ for Lysle 3. Also, because Cycle 4 analysit.
of MCpR has shown acceptabic results (see Section 6.3.3.2.1), there is no need to consider an end-of-cycle power restriction in Cycle 4 as var discursed for Cycle 3. , . . .
Cycle 4 operation may therefore precced under the existing Technical Specifications with full assurance of conservative adherence to all linits . ~1his conclut. ion can be drav trom extcur.ive analysis u r i ng bat h the llench- Levy and the GUIAL/GD i he. 1. a; c.rreAallen .
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