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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML22305A6812022-11-0101 November 2022 Generator Tube Inspection Report ULNRC-06650, Resubmittal of Owner'S Activity Report (OAR-1 Form) for Cycle/Refuel 242021-04-27027 April 2021 Resubmittal of Owner'S Activity Report (OAR-1 Form) for Cycle/Refuel 24 ULNRC-06630, Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 242021-03-18018 March 2021 Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 24 ULNRC-06527, Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 232019-08-15015 August 2019 Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 23 ULNRC-06449, Supplement to Owner'S Activity Report (OAR-1 Form) for Cycle/Refuel 222018-08-0909 August 2018 Supplement to Owner'S Activity Report (OAR-1 Form) for Cycle/Refuel 22 ML18078A7882018-03-19019 March 2018 Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 22 ULNRC-06370, Supplement to Request 14R-04 for Relief from ASME Section XI Code Inservice Inspection Requirements2017-05-15015 May 2017 Supplement to Request 14R-04 for Relief from ASME Section XI Code Inservice Inspection Requirements ULNRC-06332, Results of Steam Generator Tube In-Service Inspection2016-10-11011 October 2016 Results of Steam Generator Tube In-Service Inspection ULNRC-06322, Owner Activity Reports (OAR-1 Forms) for Cycle/Refuel 212016-08-0303 August 2016 Owner Activity Reports (OAR-1 Forms) for Cycle/Refuel 21 ML14353A4422014-12-19019 December 2014 Technical Position TP-06 Position Indication Testing of EMHV8924 ULNRC-06160, 10 CFR 50.55a(g)(4)(ii) Inservice Inspection Interval ASME OM Code Dynamic Restraint (Snubbers) Testing Requirements for Fourth 120-Month Inservice Inspection Interval2014-12-11011 December 2014 10 CFR 50.55a(g)(4)(ii) Inservice Inspection Interval ASME OM Code Dynamic Restraint (Snubbers) Testing Requirements for Fourth 120-Month Inservice Inspection Interval ULNRC-05866, Results of Steam Generator Tube In-Service Inspection2012-05-17017 May 2012 Results of Steam Generator Tube In-Service Inspection ULNRC-05606, Submittal of Owner'S Activity Report (Form OAR-1) for Refuel 16 IWE - Containment Pressure Boundary Inspection2009-03-20020 March 2009 Submittal of Owner'S Activity Report (Form OAR-1) for Refuel 16 IWE - Containment Pressure Boundary Inspection ULNRC-05450, Results of First Replacement Steam Generator Tube In-Service Inspection2007-10-25025 October 2007 Results of First Replacement Steam Generator Tube In-Service Inspection ULNRC-05185, Request for Relief from ASME Section XI Code Inservice Examination Requirements2005-08-10010 August 2005 Request for Relief from ASME Section XI Code Inservice Examination Requirements ULNRC-05184, 10CFR50.55a(a)(3) Requests for Relief from ASME OM Code Pump Testing Requirements for Third 120-Month Inservice Testing Interval2005-08-0909 August 2005 10CFR50.55a(a)(3) Requests for Relief from ASME OM Code Pump Testing Requirements for Third 120-Month Inservice Testing Interval ML0515803812005-06-0202 June 2005 Results of Fourteenth Steam Generator Tube Inservice Inspection ULNRC-05025, Refuel 11, Inservice Inspection Summary Report2003-02-21021 February 2003 Refuel 11, Inservice Inspection Summary Report ULNRC-04595, Special Report 2001-02 for Callaway Plant Unit 1 Re Results of the Twelfth Steam Generator Tube In-Service Inspection2002-01-29029 January 2002 Special Report 2001-02 for Callaway Plant Unit 1 Re Results of the Twelfth Steam Generator Tube In-Service Inspection 2022-11-01
[Table view] Category:Letter type:ULNRC
MONTHYEARULNRC-06901, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)2024-10-0101 October 2024 Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter) ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaways License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaways License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Enclosure 2: Ameren Missouri Verification Ofagreement Letters with State and EPZ Counties for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Enclosure 2: Ameren Missouri Verification Ofagreement Letters with State and EPZ Counties for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report 2024-06-26
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AmerenUE PO Box 620 CallawayPlant Fulton, MO 65251 August 10, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-05185 10 CFR 50.55a wAmerefl DOCKET NUMBER 50-483 UE UNION ELECTRIC COMPANY CALLAWAY PLANT REQUEST FOR RELIEF FROM ASME SECTION XI CODE INSERVICE EXAMINATION REQUIREMENTS Pursuant to 10 CFR 50.55a(a)(3), Union Electric Company (AmerenUE) hereby requests NRC approval of the attached relief request (i.e., 10 CFR 50.55a request) for the examination of snubbers at Callaway. The relief request (attached and identified as 10 CFR 50.55a Request Number 13R-03) is for the third 10-year interval of Callaway's Inservice Inspection (ISI) Program, which begins December 19, 2005.
The Code Edition(s) and Addenda applicable to Callaway for its third 10-year ISI interval are ASME Boiler and Pressure Vessel Code,Section XI 1998 Edition through 2000 Addenda, and ASME/ANSI OM, Part 4, 1987 Edition with OMa-1998 Addenda.
The relief request would allow snubbers to continue to be inspected in accordance with the test program defined in Section 16.7.2 of the Callaway Final Safety Analysis Report (FSAR) in lieu of the applicable Code requirements specified in Article IWF-5000, "Inservice Inspection Requirements for Snubbers," Subarticles IWF-5200 and IWF-5300 (as directed by the above-noted Code Edition(s) and Addenda). The snubber test program defined in FSAR Section 16.7.2 is the NRC-approved program that was previously specified in the Callaway Technical Specifications (Appendix A of the Operating License), i.e., until the applicable Technical Specification requirements were relocated to Chapter 16 of the FSAR based on application of the Final Policy Statement on Technical Specification Improvement (1994 timeframe). The snubber visual inspection schedule specified
-fkL4V asubsidiary ofAmeren Corporation
ULNRC-05 185 August 10, 2005 Page 2 per FSAR Section 16.7.2 (and as formerly specified in the Callaway Technical Specifications) is in accordance with the "alternative" schedule recommended by NRC Generic Letter 09-09, which continues to be an NRC-accepted approach at many licensed facilities today.
Supporting information and additional justification for the requested relief is provided in the attachment. It may be noted that no new regulatory commitments have been made or identified pursuant to this letter and its attachment.
Please contact us for any questions you may have regarding this request.
Sincerely, eith D. Young Manager - Regulatory Affairs TBE/jdg
Attachment:
10 CFR50.55a Request Number l3R-03
ULNRC-05185 August 10, 2005 Page 3 cc: U.S. Nuclear Regulatory Commission (Original and 1 copy)
Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360
10 CFR 50.55a Request Number 13R-03
., -Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality and Safety
- 1. ASME Code Components Affected All safety-related ASME Section XI Code Class 1, 2, and 3 snubbers.
2. Applicable Code Edition and Addenda
ASME Boiler and Pressure Vessel Code,Section XI 1998 Edition through 2000 Addenda ASME/ANSI OM, Part 4, 1987 Edition with OMa-1988 Addenda
3. Applicable Code Requirement
The applicable Code requirements are specified in Article IWF-5000, "Inservice Inspection Requirements for Snubbers," Subarticles IWF-5200 and IWF-5300:
(a) Preservice/Inservice examinations shall be performed in accordance with ASME/ANSI OM, Part 4, using the VT-3 visual examination method described in IWA-2213.
(b) Preservice/Inservice tests shall be performed in accordance with ASME/ANSI OM, Part 4.
(c) Integral and non-integral attachments for snubbers, including lugs, bolting, pins, and clamps, shall be examined with the requirements of this Subsection.
4. Reason for Request
ASME Section XI, 1998 Edition through 2000 Addenda, Subarticles IWF-5200 and IWF-5300 specifies that snubber preservice/inservice examinations and tests be performed in accordance with ASME/ANSI OM, Part 4, as noted above. However, snubber examinations and tests at Callaway Plant are currently performed in accordance with the program described in Callaway Plant Final Safety Accident Report (FSAR) Section 16.7.2, "Snubbers." To resolve this conflict, relief is requested from the requirements of Article IWF-5000 (Subarticles IWF-5200 and IWF-5300) to allow snubbers to continue to be tested in accordance with FSAR Section 16.7.2, in lieu of the noted Code requirements.
The current inspection/testing program as defined by the FSAR provides for an acceptable level of quality and safety equal to or greater than that of ASME/ANSI OM, Part 4.
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- 5. Proposed Alternative and Basis for Use In lieu of implementing the requirements of Subarticle IWF-5200 and IWD-5300, it is proposed that the preservice/inservice examination and testing be performed under Callaway Plant FSAR, 16.7.2, "Snubbers."
Visual Snubber Examinations The Callaway Plant FSAR lists visual examination requirements for snubbers that are compatible with Section XI VT-3 requirements. IWF-5000 requires that examinations be performed using the VT-3 visual examination method described in IWA-2213. IWA-2213 reads as follows:
VT-3 examinations are conducted to determine the general mechanical and structural condition of components and their supports by verifying parameters such as clearances, settings, and physical displacements; and to detect discontinuities and imperfections, such as loss of integrity at bolted or welded connections, loose or missing parts, debris, corrosion, wear, or erosion. VT-3 includes examinations for conditions that could affect operability or functional adequacy of snubbers and constant load and spring supports.
The Callaway Plant FSAR states:
Visual inspections shall verify that: (1) There are no visible indications of damage or impaired OPERABILITY, (2) Attachments to the foundation or support structure are functional, and (3) Fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.
The Callaway Plant procedure that implements the FSAR snubber inspections identifies the following as unacceptable conditions:
- Indication of damage or impaired operability.
- Dysfunctional attachments to foundation or supporting structure.
o Dysfunctional fasteners securing snubber to component and foundation or supporting structure.
- Damage, deterioration, or deformation of snubber, snubber attachment, structural steel or concrete.
- Extensive corrosion on the support cylinder or housing snap ring.
- Arc strikes anywhere on the component support.
- Weld or paint splatter or other roughness of the support cylinder located in an area which could impede movement of the snubber.
- Obvious signs of binding.
- Missing bolts, load pins, connections or other type fasteners which are designed to be under load.
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- Fully dislodged spherical bearings.
- Piping or component interference with snubber unless interference is in the designed direction of motion.
- Rotational binding that prevents the snubber from moving as designed.
- Insulation interferences.
The differences between the requirements of IWA-2213 and the Callaway Plant FSAR are primarily semantic in nature. The intent and scope of the two documents are essentially equal, although the code wording is more detailed than the FSAR in listing specific items to be included. However, those items are intuitive to meeting the FSAR requirements and are more specifically addressed in the implementing procedure that closely parallels the code listing. FSAR examinations are performed by personnel that are qualified to perform VT-3 examinations per IWA-2300.
The Callaway Plant FSAR also incorporates the reduced visual examination frequency table as provided in NRC Generic Letter 90-09. This results in a significant reduction in unnecessary radiological exposure to plant personnel, a savings in company resources, and compliance with visual examination requirements while maintaining the same confidence level in snubber operability as that provided by following Section XI requirements.
Snubber Testing The Callaway Plant FSAR snubber testing requirements for snubbers are compatible with ASME/ANSI OM, Part 4. ASME/ANSI OM, Part 4, states:
Snubber operational readiness test shall verify the following:
(a) activation is within the specified range of velocity or acceleration in tension and in compression; (b) release rate, when applicable, is within the specified range in tension and in compression. For units specifically required not to displace under continuous load, ability of the snubber to withstand load without displacement; (c) for mechanical snubbers, drag force is within specified limits, in tension and in compression.
The Callaway Plant FSAR states:
The snubber functional test shall verify that:
- a. Activation (restraining action) is achieved within the specified range in both tension and compression; Page 3 of 4
- b. Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range, and
- c. For mechanical snubbers, the force required to initiate or maintain motion of the snubber is withinthe specified range in both directions of travel.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
The Callaway Plant FSAR snubber testing program provides for comprehensive and conservative requirements that are effective in providing a reliable snubber population.
This results in increased confidence in plant safety. The use of the Callaway Plant FSAR addresses the intent and scope of the requirementsSection XI Article IWF-5000 in a single governing document that can be consistently applied.
- 6. Duration of Proposed Alternative Snubber visual examination and testing will be scheduled and performed in accordance with FSAR 16.7.2, "Snubbers," throughout the entire third 120-month inspection interval.
- 7. Precedents None Page 4 of 4