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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D0711999-09-14014 September 1999
Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities
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
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
ML20210H6531999-07-30030 July 1999
SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1
ML20205Q5561999-04-19019 April 1999
Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp
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
ML20217F3181998-03-24024 March 1998
SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program
ML20217J9981997-10-16016 October 1997
Safety Evaluation Concluding That Proposed Transaction Will Not Affect Qualifications of Ue as Holder of Plant,Unit 1 License
ML20141C9031997-05-13013 May 1997
Safety Evaluation Supporting Second 10 Yr Interval ISI Program Plan Requests for Relief ISI-10 & ISI-11
ML20129J3541996-10-31031 October 1996
Safety Evaluation Approving Revised Relief Request Including EN-01,EN-03,EP-02 & FC-01 Pursuant to 10CFR50.55a(f)(6)(i)
ML20128N8661996-10-11011 October 1996
Safety Evaluation Approving Licensee Request to Use Code Case N-533 as Alternative to Code Requirements,Per 10CFR50.55a(a)(3)
ML20129G8941996-10-0303 October 1996
Safety Evaluation Re Second 10-yr Interval Insp Program Plan Revised Request for Relief ISI-07B
ML20058L7031993-12-10010 December 1993
Safety Evaluation Supporting Relaxation of RG 1.97 Environ Qualification Requirements Re Pressurized Water Reactors Accumulator Pressure & Volume Instrumentation
ML20057E2641993-09-30030 September 1993
Safety Evaluation Granting Relief Request PO-7,BB-12 & EP-2 in Part,Per 10CFR50.55a
ML20056A5611990-08-0606 August 1990
Safety Evaluation Re Util 860108 Submittal of Steam Generator Tube Rupture Analysis.Nrc Does Not Concur W/ Conclusion Reached as to No Steam Generator Overfill During Design Basis Steam Generator Tube Rupture Accident
ML20195J6951988-06-14014 June 1988
Safety Evaluation Approving Rev 10 to Facility Inservice Insp Program & Util Requests for Relief from Certain ASME Code Requirements
ML20155J4901988-05-26026 May 1988
Safety Evaluation Accepting Util Corrective Actions & Commitments Re Reactor Vessel Head Closure Stud Problems
ML20147D9631988-02-25025 February 1988
Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90
ML20149K0501988-02-18018 February 1988
Safety Evaluation Accepting Util Analyses Re Main Steam Line Break Outside Containment W/Superheated Steam Releases
ML20234D8261987-12-24024 December 1987
Safety Evaluation Conditionally Accepting Proposed ATWS Mitigation Sys Actuation Circuitry Design Per ATWS Rule (10CFR50.62)
ML20236H0071987-10-26026 October 1987
Safety Evaluation Supporting Licensee First 10-yr Inservice Testing Program Update
ML20237H5971987-08-19019 August 1987
Safety Evaluation Re Inservice Testing Program & Requests for Relief.Program Acceptable for Implementation
ML20214V8911987-06-0404 June 1987
Safety Evaluation on 870528 Request for Emergency Relief from Inservice Testing Requirements Re Four Check Valves on RHR Injection Lines to Hot Leg Connections.Relief Granted
ML20206K5171987-04-10010 April 1987
SER Accepting Util 831118,840312,0521,1227 & 870127 Responses to Item 2.2 (Part 1) of Generic Ltr 83-28, Equipment Classification Programs for All Safety-Related Components
ML20206K5611987-04-10010 April 1987
SER Accepting Util 831118,840312,0521,1227 & 850517 Responses to Item 2.2 (Part 2) of Generic Ltr 83-28, Vendor Interface (Programs for All Safety-Related Components)
ML20212H8111987-03-0404 March 1987
Safety Evaluation Accepting Util 860114 & 0709 Responses to 851104 Request for Addl Info Re Dcrdr Function & Task Analysis & How Function & Analysis Applied to Upgrading Emergency Operating Procedures
ML20207C0801986-12-22022 December 1986
SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Parts 1 & 2 Re Equipment Classification for Reactor Trip Sys (RTS) Components & RTS Vendor Interface,Respectively
ML20211P2251986-12-15015 December 1986
Safety Evaluation Re 860121 Response to PTS Rule,Per 10CFR50.61.Matl Properties of Reactor Vessel Beltline Matls, Projected Fluence at Inner Surface of Reactor Vessel for end-of-life of Plant & Calculated Rt PTS Acceptable
ML20215E0121986-10-0707 October 1986
SER Re Util 831118 & 860812 Responses to Generic Ltr 83-28, Items 3.1.3 & 3.2.3 Re post-maint Testing (Reactor Trip Sys Components,All Other safety-related Components).Responses Acceptable
ML20203G6401986-07-24024 July 1986
SER Supporting Util post-trip Review Data & Info Capability, Per Generic Ltr 83-28,Item 1.2
ML20203H2481986-07-23023 July 1986
SER Denying Proposed Rev to Tech Spec 4.6.1.2, Containment Leakage Surveillance Requirements for Valves Pressurized W/Fluid from Seal Sys
ML20207H3711986-07-21021 July 1986
SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 Re Part 1 Equipment Classification
ML20205F0001985-10-28028 October 1985
Safety Evaluation Supporting Util 831118,840312,0521 & 1227 Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability
ML20134J9251985-08-27027 August 1985
Safety Evaluation Re Dcrdr & Related Function & Task Analysis.Implementation Schedule for Control Room Human Factors Improvements Acceptable
ML20133E5121985-07-30030 July 1985
Safety Evaluation Supporting RHR Sys Low Temp Overpressure Protection Sys Mods
ML20128L1491985-07-0303 July 1985
Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Items 3.1.1 & 2,3.2.1 & 2,4.1 & 4.5.1 Re post- Maint Testing & Reactor Trip Sys Reliability
1999-09-02
[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
.
1
, SAFETY EVALUATION REPORT
) GENERIC LtilER 83-28, IItM Z.1 (PART 1)
EQUIPMENT CLASSIFICATION (RT5 COMPONENTS)
CALLAWAY PLANT, UNIT 1 DOCKET N05. 483
.:.~i.E UCTION AND
SUMMARY
en re5ruary 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem
..s.iear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. The incident was tenninated manually by the operator about 30 seconds after the initiation of the automatic trip signal.
The failure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior to this incident, on February 22, C, Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coin-cidentally with the automatic trip.
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (ED0), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.
The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000 " Generic Implications of the ATWS l
Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8,1983I) all licensees of operating reactors, applicants for an operating license, and holders of construction pennits to respond to generic issues raised by the analyses of these two ATWS events, i
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t 2
This report is an evaluation of the response submitted by Union Electric Company, the licensee for the Callaway Plant, Unit 1 for Item 2.1 (Part 1) of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the references at the end of the report.
Item 2.1 (Part 1) requires the licensee to confirm that all Reactor Trip System components are identified, classified and treated as safety-related as indicated in the following statement:
Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as .
safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, in-cluding maintenance, work orders, and parts replacement.
EVALUATION The licensee for the Callaway Plant Unit I responded to the requirements of Item 2.1 (Part 1) with a series of submittals 2,3,4,5,6 referenced below. The first three submittals described the licensee's classification program that was
- being developed and provided progress reports. The licensee stated in the final two submittals that the program was fully implemented and reaffinned that all com-ponents that are required to perform the reactor trip function were reviewed to verify that these components are classified as safety-related equipment. The licensee further stated that the developed 0 list is used in the generation of
1 3-
)
wo-k requests and in assignment of surveillance and preventative meintenance sasks.
CONCLUSION Based on our review of these responses, we find the licensee's statements confirm that a program exists for identifying, classifying and treating ccmponents that are required for performance of the reactor trip function as safety related. This program meets the requirements of Item 2.1 (Part 1) of the Generic Letter 83-28, and is therefore acceptable.
REFERENCES
- 1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8,1983. '
- 2. Letter, D. F. Schnell, Union Electric Co. , to H. R. Denton, NRC, November 8, 1983.
- 3. Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, March 12, 1984.
- 4. Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, May 21, 1984.
- - , - - - . , . - - - - - - - ,, ,-,.,,c .-- , . . , - , - - - - , . - . - - - . - . _ - . -
,--.,.---,n-. - . - - - - e,,.- ,
-1 4
?
REFERENCES (CONT.) -
- 5. Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, December 27, 1984.
- 6. Letter, D. F. Schnell, Union Electric Co., to H. R. Denton, NRC, May 17, 1985.
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