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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
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- j g UNITED STATES j g j t
NUCLEAR REGULATORY COMMISSION i
WASHINGTON. D.C. 20666-0001 o\ ..../
j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ASME CODE CASE N-53 s
UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1
} DOCKET NO. 50-483 3
1.0 INTRODUCTION
The Technical Specifications for Callaway Plant, Unit 1, state that the I inservice inspection and testing of the American Society of Mechanical
! Engineers (ASME) Code Class 1, 2, and 3 components shall be performed in j accordance with Section XI of the ASME Boiler and Pressure Vessel Code and ,
! applicable Addenda as required by 10 CFR 50.55a. Section 50.55a(a)(3) of ;
l Title 10 of the Code of Federal Regulations states that alternatives to the i requirements of paragraph (g) may be used, when authorized by the NRC, if (i)
! the proposed alternatives would provide an acceptable level of quality and
! safety, or (ii) compliance with the specified requirements would result in
! hardship or unusual difficulty without a compensating increase in the level of I quality and safety.
I Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components
! (including supports) shall meet the requirements, except the design and access
- provisions and the preservice examination requirements, set forth in the ASME
- Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant i
Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests
! conducted during tha first ten-year interval and subsequent intervals comply
! with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to ti.e start of the 120-month interval, subject to the
- limitations and modifications listed therein. The components (including j supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission 4 approval.
2 Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance
- with an examination requirement of Section XI of the ASME Code is not i practical for its facility, information shall be submitted to the Commission I in support of that determination and a reouest made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR
! 50.55a(g)(6)(i), the Commission may grant relief and may impose alternative j requirements that are determined to be authorized by law, will not endanger 9610170056 961011 PDR ADOCK 05000483
, P PDR
a .
life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
By letter dated September 18, 1996, as supplemented by letter dated September 30, 1996, Union Electric Company (the licensee) requested approval for the implementation of the alternative rules of ASME Section XI Code Case N-533, entitled " Alternative Requirements for VT-2 Visual Examination of Class 1 Insulated Pressure-Retaining Bolted Connections,Section XI, Division 1,"
pursuant to 10 CFR 50.55a(a)(3) to be applied to the Inservice Inspection (ISI) program for the Callaway Plant.
The NRC staff has reviewed and evaluated the licensee's request to use Code Case N-533 as a proposed alternative to the Cede requirements for the Callaway Plant. !
2.0 EVALUAUM Reauest for Authorization to Use Code Case N-533. Alternative Reaufrements for VT-2 Visual Examination of Class 1 Insulated Pressure-Retainina Bolted Connections.Section XI. Division 1 Code Reauirement: IWA-5242(a) states that for systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure-retaining bolted connections for a direct VT-2 visual examination.
Code cases are periodically published by ASME to either clarify the ir. tent of the Code rules or to provide alternatives to existing Code requirements. Use of these nonmandatory Code cases for inservice inspection is subject to general acceptance by the NRC staff and incorporation into Regulatory Guide 1.147. Pursuant to 10 CFR 50.55a, other Code cases may be used provided specific authorization is granted.
Licensee's Code Relief Reauest: The licensee has requested authorization to use Code Case N-533, Alternative Requirements for VT-2 Visual Examination of Class 1 Insulated Pressure-Retaining Bolted Connections,Section XI, Division 1.
If utilizing the provisions of Code Case N-533, the licensee will ensure that the component to be examined has been pressurized at normal operating pressure for a least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> since the previous refueling outage.
Licensee's Basis for Reauestina Relief (as stated): .
" Insulation removal and inspection of components at a system operating temperature of 557*F is a parsonnel safety hazard."
Licensee's Proposed Alternative Examination:
In accordance with Code Case N-533, the following alternative requirements will be met in lieu of the requirement of IWA-5242(a) to remove insulation from Class 1 pressure retaining bolted connections to perform a VT-2 visual examination:
i t
f I i i
! 1. A system pressure test and VT-2 visual examination shall be performed each refueling outage without insulation removal.
)
- 2. Each refueling outage the insulation shall be removed from the bolted connection, and a VT-2 visual examination shall be performed. The
- connection is not required to be pressurized. Any evidence of leakage l shall be evaluated in accordance with IWA-5250. .
l Evaluation:
} Paragraph IWA-5242(a) requires the removal of all insulation from pressure- l j retaining bolted cennections in systems borated for the purpose of controlling l i reactivity when performing VT-2 visual examinations during system pressure i tests. The licensee has proposed to use Code Case N-533, which requires (1)
- performance of the Code-required pressure test without removing the i
! insulation, (2) examination of Class 1 bolted connections, each refueling ;
I outage, at atmospheric or static pressure with the insulation rencved, and (3) '
evaluation of any evidence of leakage in accordance with IWA-5250. l 1
i Paragraph IWA-5242(a) provides requirements for detecting leakage or evidence j of leakage at bolted connections. After a 4-hour hold time, performing a l VT-2 visual examination during system pressure tests, as required by Code
! Case N-533, with the insulation in place will likely result in the detection l of any significant leakage. Furthermore, performing a VT-2 visual examination
! after removal of the insulation at atmospheric or static pressure during i outages, as specified by Code Case N-533, will allow examination for evidence i of borated water leakage. Evidence of leakage will be evaluated in accordance i with IWA-5250 of Section XI.
\ l
3.0 CONCLUSION
i
! The staff has reviesed the licensee's submittal and concluded that by using j
- Code Case N-533 the ficensee will locate and evaluate leakage, or evidence of j leakage, in a manner comparable to following the requirements of the Code, and
! thus the licensee's proposed alternative provide
- an acceptable level of j quality and safety. Therefore, the licensee's pcoposed alternative, to
- implement Code Case N-533 following a 4-hour hold time at normal operating j pressure, is authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of this 2
Code Case is authorized for the Callaway Plant for the Second 10-year ISI
- Interval or until the Code Case is approved for general use by reference in i Regulatory Guide 1.147. After that time, the licensee may continue to use j Code Case N-533 with the limitations, if any, listed in Regulatory i Guide 1.147.
) Principal Contributor: T. McLellan K. Thomas l
- Cate
- October 11, 1996
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