Supplement to 10CFR50.59 Annual Rept, for Period Ending 920331,consisting of Info Re end-of-life Moderator Temp Coefficient for Cycle 5| ML20101U419 |
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| Site: |
Callaway  |
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| Issue date: |
03/31/1992 |
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| From: |
UNION ELECTRIC CO. |
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| To: |
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| Shared Package |
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| ML20101U417 |
List: |
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| References |
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| NUDOCS 9207230003 |
| Download: ML20101U419 (2) |
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Category:ANNUAL OPERATING REPORT
MONTHYEARML20155H7381998-06-30030 June 1998
10CFR50.59 Summary Rept for Jan-June 1998. with
ML20069D1421993-11-30030 November 1993
10CFR50.59 Safety Evaluation Summary Rept for Callaway Nuclear Plant
ML20101U3951992-06-30030 June 1992
10CFR50.46 Annual Rept - ECCS Evaluation Model Revisions, for June 1991 to June 1992
ML20101U4191992-03-31031 March 1992
Supplement to 10CFR50.59 Annual Rept, for Period Ending 920331,consisting of Info Re end-of-life Moderator Temp Coefficient for Cycle 5
ML20101F0291992-03-31031 March 1992
10CFR50.59 Safety Evaluation Summary Rept for Callaway Nuclear Plant, for Period Ending 920331
ML20155J9461988-06-15015 June 1988
Annual Rept of Changes to Approved Fire Protection Program, 870501-880412
ML20236W7181987-12-31031 December 1987
Simulator Annual Rept 1987
ML20215B8021987-06-0909 June 1987
Annual Rept of Fire Protection Program Changes,
1998-06-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217E2691999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With
ML20212D0711999-09-14014 September 1999
Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities
ML20212A3361999-09-14014 September 1999
1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included
ML20211N0451999-09-0202 September 1999
Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding
ML20212A0201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With
ML20210P0441999-08-10010 August 1999
Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1
ML20210Q8331999-08-0505 August 1999
Rev 4 to Callaway Cycle 10 Colr
ML20210T9481999-08-0303 August 1999
Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for Ue Callaway Plant,Unit 1
ML20216D8791999-07-31031 July 1999
Rev 3 to Callaway Cycle 10 Colr
ML20210T4451999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With
ML20210H6531999-07-30030 July 1999
SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1
ML20209H0881999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With
ML20195H4831999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With
ML20206R7111999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With
ML20205Q5561999-04-19019 April 1999
Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp
ML20205S5791999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Callaway Plant Unit 1.With
ML20207A7401999-03-30030 March 1999
Draft, Evaluation of Risk of Induced Steam Generator Tube Rupture, for Callaway Plant
ML20205G4071999-03-25025 March 1999
Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325
ML20204B6741999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Callaway Plant,Unit 1.With
ML20199E7011998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Callaway Plant.With
ULNRC-03990, 1998 Annual Rept for Ameren Corp/Union Electric Co. with1998-12-31031 December 1998
1998 Annual Rept for Ameren Corp/Union Electric Co. with
ML20198D9811998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Callaway Plant,Unit 1.With
ML20195C8341998-11-10010 November 1998
Rev 20 to Operating QA Manual
ML20195C8181998-11-0909 November 1998
Rev 19 marked-up Changes to Operating QA Manual
ML20195D6931998-10-31031 October 1998
Non-proprietary Rev 3 to Electrosleeving Qualification for PWR Recirculating SG Tube Repair
ML20195D3581998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Callaway Plant,Unit 1.With
ML20154L4931998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Callaway Plant Unit 1.With
ML20151Y5151998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Callaway Plant,Unit 1.With
ML20155B5871998-08-28028 August 1998
Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant
ML20237B8421998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Callaway Plant,Unit 1
ML20155H7381998-06-30030 June 1998
10CFR50.59 Summary Rept for Jan-June 1998. with
ML20236Q9991998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Callaway Plant,Unit 1
ML20249C5851998-06-30030 June 1998
Rev 1 to Callaway Cycle 10,COLR
ML20248M0501998-06-0808 June 1998
Special Rept 98-02:on 980502,Channel 3 of loose-part Detection Sys Was Declared to Be Inoperable.Caused by Failure of Component Inaccessible at Power.Addl Troubleshooting Will Be Performed
ML20249A7681998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Callaway Plant,Unit 1
ML20249B2451998-05-18018 May 1998
Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs
ML20248C3681998-05-18018 May 1998
Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants
ML20247G0811998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Callaway Plant Unit 1
ML20217R2031998-04-27027 April 1998
Cycle 10 Colr
ML20216H0651998-04-15015 April 1998
SER Approving Licensee Proposed Alternative to Use Code Case N-508-1 for Rotation of Serviced Snubbers & Prvs for Purpose of Testing in Lieu of ASME B&PV Code,Section Xi,Article IWA-7000 Requirements
ML20216K0531998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Callaway Plant,Unit 1
ML20217F3181998-03-24024 March 1998
SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program
ML20216G3551998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Callaway Plant, Unit 1
ML20203M0101998-02-25025 February 1998
Rev 11 to Callaway Cycle 9 Colr
ML20203A7951998-02-0909 February 1998
Rev 10 to Callaway Cycle 9 Colr
ML20202D4821998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Callaway Plant
ML20198S6361998-01-22022 January 1998
Ro:On 980121,determined That Plant Shutdown Would Be Required IAW TS 3.8.1.1,Action D.Caused by 'B' Train EES Charcoal Absorber Being Determined Inoperable.Requested 24 Hour Extension to Allow Restoration of EDG & ESW Train
ULNRC-03775, 1997 Annual Rept for Union Electric1997-12-31031 December 1997
1997 Annual Rept for Union Electric
ML20198Q0631997-12-31031 December 1997
Rev 9 to Callaway Cycle 9 Colr
ML20198J6791997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Callaway Plant,Unit 1
1999-09-30
[Table view] |
Text
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A * ,
. Attachment to ULNRC-26 6 3 Supplement to 10 CFR 50.59 Safety Evaluation Summary Report for Callaway Nuclear Plant RrR-07558J End-of-Life Moderator Temperature Coefficient for Cycle S The RFR extends the end-of-life (EOL) moderator temperature
-coefficient (MTC) limit for Cycle 5. Justification for extended range was performed by utill:1ng available margin in reactor vendor calculations. In order to further extend the range of acceptable EOL_MTC surveillance measurements, non LOCA safety ana)yses which use the most negative MTC as part of the conservative. input assumptions have been evaluated.
Overall protection system design is unchanged from that included in accident analyses in FSAR Chapter 15, in analysis of superheated blowdowns outside containment, and in analysis of Environmental Allowance Modifier / Trip Time Delay. There are no impacts on the LOCA and non-LOCA transient analyses documented in FSAR Chapter 15. Design of plant protection systems and the intended manner of. plant operation are unchanged. The Bases for Technical Specification 3/4.1.1.3 ensure that the most negative MTC' limit specified in the COLR, corresponding to the most pos3tive. moderator density coefficient, is not exceeded. There le to change to peaking factor limits or to the safety analysis DNbR limit. The revised EOL MTC limit has no effect on the
.results presented in FSAR 15.6.5 and the peak clad temperature remains below the ECCS Acceptance Criteria limit, i
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9207230003'920715 DR ADOCK05000g83
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4 cc: T. A. Baxter, Esq.
Shaw, Pittman, Potta & Trowbridge Wa hington D C. 2 b37 Dr. J. O. Cermak CFA, Inc. >
18225-A Flower (113 Way Gaithersburg, MD 20079-5334 R. C. Knop +
Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen-Ellyn, Illinois 60137 Bruce Bartlett Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 L. R. Wharton (2)
Office'of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E21 11555 Rockville. Pike Rockville, MD 20852 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 l[
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