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MONTHYEARULNRC-05844, Facility Operating License NPF-30 10 CFR50.55a Request: Proposed Alternative Regarding ASME OM Code Replacement Interval for Main Steam Isolation Value Actuator Rupture Disks2012-03-30030 March 2012 Facility Operating License NPF-30 10 CFR50.55a Request: Proposed Alternative Regarding ASME OM Code Replacement Interval for Main Steam Isolation Value Actuator Rupture Disks Project stage: Request ML1210105772012-04-0505 April 2012 Request for Additional Information Re E-mail, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks Project stage: RAI ML1210105692012-04-0909 April 2012 Attachment 5 Project stage: Other ML1210105602012-04-0909 April 2012 Attachment 4 Project stage: Other ML1210105572012-04-0909 April 2012 Attachment 3 Project stage: Other ML1210105522012-04-0909 April 2012 Attachment 2 Project stage: Other ML1210105382012-04-0909 April 2012 Attachment 1 Project stage: Other ML1210105182012-04-0909 April 2012 Email Licensee Responses to Request for Additional Information Regarding Relief Request, Main Steam Isolation Valve Actuator Rupture Disks Replacement Interval Project stage: Response to RAI ML1210104882012-04-10010 April 2012 Request for Additional Information Email to the Licensee, Relief Request Main Steam Isolation Valve Actuator Rupture Disks Replacement Interval Project stage: RAI ML1211502472012-05-0303 May 2012 Memo to File, Verbal Authorization, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks Project stage: Other ML12220A2322012-08-0909 August 2012 Request for Additional Information, Verbal Authorization of Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of MSIV Actuator Rupture Disks Project stage: RAI ULNRC-05905, Response to NRC Request for Additional Information Regarding 10 CFR 50.55a Request: Proposed Alternative to ASME OM Code Replacement Interval for Main Steam Isolation Valve Actuator Rupture Disks2012-09-10010 September 2012 Response to NRC Request for Additional Information Regarding 10 CFR 50.55a Request: Proposed Alternative to ASME OM Code Replacement Interval for Main Steam Isolation Valve Actuator Rupture Disks Project stage: Response to RAI ML12258A0452012-09-18018 September 2012 Relief Request VR-01 from Requirements of ASME OM Code, Mandatory Appendix I, One-time Extension for 5-Year Replacement Interval, from 4/11/12 to 6/2013, Main Steam Isolation Valve Actuator Rupture Disks Project stage: Other 2012-04-09
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Category:Letter type:ULNRC
MONTHYEARULNRC-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-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds 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-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for 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 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 Callaway'S 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 Callaway'S 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-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a 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-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-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-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms 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-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-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control 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-06781, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) 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-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 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-06765, 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 Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 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 Testing Frequencies (LDCN 2020-0004) 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-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) 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-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 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, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information 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 ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
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-wAmeren Callaway Plant MISSOURI March 30, 2012 ULNRC-05844 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 10 CFR 50.55a(a)(3)(ii)
Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 10CFR50.55a REQUEST: PROPOSED ALTERNATIVE REGARDING ASME OM CODE REPLACEMENT INTERVAL FOR MAIN STEAM ISOLATION VALVE ACTUATOR RUPTURE DISKS Pursuant to 10 CFR 50.55a(a)(3)(ii), Union Electric Company (Ameren Missouri) hereby requests NRC approval of attached ReliefRequest VR-01 regarding requirements of the ASME OM Code, Mandatory Appendix 1, 1-1360 for periodic replacement of Class 2 and 3 non-reclosing pressure relief devices. (The Code Edition currently applicable to Callaway is the ASME OM Code 2001 Edition through 2003 Addenda.) At Callaway, such relief devices include the rupture disks associated with the actuators for the main steam line isolation valves (MSIVs). Per the noted OM Code requirement, the rupture disks are to be replaced every 5 years (unless historical data indicates a requirement for more frequent replacement).
The current MSIV rupture disks were installed when the MSIV actuators were replaced in 2007, i.e.,
during Refuel 15 which was conducted during the spring of that year. The rupture disks are therefore required to be replaced this spring (2012), i.e., during the current Operating Cycle while the plant is or is expected to remain on line. Per the attached 10 CFR 50.55a request, however, Ameren Missouri proposes an alternative wherein the interval for replacing the MSIV rupture disks would be extended to the next refueling outage, i.e., by approximately one year, on a one-time basis. This would allow the replacement work to be done with the plant in a shutdown condition. Details regarding justification for the proposed alternative are provided in the attached request.
PO Box 620 Fulton, MD 65251 AmerenMissouri.com
ULNRC-05844 March 30, 2012 Page2 Ameren Missouri appreciates your prompt attention to this matter. No new regulatory commitments have been made or identified in this letter or its attachment. Please contact me at 573-823-4970 or Tom Elwood at 314-225-1905 for any questions you may have regarding this request.
Sincerely, flAy S. A. Maglio Regulatory Affairs Manager TBE/nls Attachment
ULNRC-05844 March 30, 2012 Page 3 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)
Senior Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-SB 1 Washington, DC 20555-2738
ULNRC-05844 March 30, 2012 Page4 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Other Situations ULNRC Distribution:
A. C. Heflin F. M. Diya C. 0. Reasoner ill L. H. Graessle S. A. Maglio R. Holmes-Bobo F. J. Bianco J. C. Pitts B. N. Oquejiofor NSRB Secretary T. B. Elwood Mr. Bill Muilenburg (WCNOC)
Mr. Tim Hope (Luminant Power)
Mr. Ron Barnes (APS)
Mr. Tom Baldwin (PG&E)
Mr. Wayne Harrison (STPNOC)
Ms. Linda Conklin (SCE)
Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)
Missouri Public Service Commission
Attachment to ULNRC-05844 Page 1 of3 10 CFR 50.55a Request Number VR-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety
- 1. ASME Code Components Affected Rupture Disc System Safety Class Category Number ABPSE0001 Main Steam (AB) 2 D ABPSE0002 Main Steam (AB) 2 D ABPSE0003 Main Steam (AB) 2 D ABPSE0004 Main Steam (AB) 2 D
- 2. Applicable Code Edition and Addenda ASME OM Code 2001 Edition through 2003 Addenda
- 3. Applicable Code Requirement Mandatory Appendix 1, 1-1360: Class 2 and 3 non-reclosing pressure relief devices shall be replaced every 5 years unless historical data indicates a requirement for more frequent replacement.
Safety Class 2: Represents the ASME Code Class of the rupture discs.
Category D: Represents valves that are actuated by an energy source capable of only one operation, such as rupture discs or explosively actuated valves.
- 4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3)(ii), relief is requested from the requirement of the ASME OM Code, Mandatory Appendix 1, 1-1360. The basis of the relief request is that the proposed alternative (explained later) would extend the 5-year replacement interval one time, from April11, 2012 until June 2013 (Refuel19).
Attachment to ULNRC-05844 Page 2 of3 The Main Steam Isolation Valve (MSIV) Rupture Discs (ABPSEOOOl/2/3/4) are currently scheduled to be replaced online per the mentioned ASME OM Code requirement. The rupture discs were installed in 2007 (Refuel 15). Performing this surveillance activity will involve significant maintenance activities and out-of-service time, including the hanging of tags (workman's protection assurance), performing the rupture disc replacement work, clearing tags, and performing applicable post maintenance tests (PMT). Isolating the rupture discs for this work makes the MSIVs inoperable and requires entry into plant Technical Specification (T/S) 3.7.2.F actions: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore or hot standby in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Based on the short T/S duration time and the time needed to replace these rupture discs online, the T/S completion time may be exceeded during this surveillance activity. In light of the short T/S completion time, the rupture disc replacement activity poses elevated risk to continued plant operations if the surveillance is performed online.
- 5. Proposed Alternative and Basis for Use The proposed alternative is a one-time extension of the current replacement interval such that its end date would be extended from April11, 2012 to June 2013. This would allow replacing the rupture discs during Callaway's next refuel. Replacing the rupture discs online by surveillance due dates would result in elevated risk to the plant, without a compensating increase in the level of quality or safety.
The rupture discs are 1.375 inches diameter stainless steel (316SS), rated 150 psig at 450 F. The rupture discs are subjected to day-to-day plant operating conditions of a nominal temperature of 142 F and pressure of3.04 psia. For such conditions, the calculated stress acting on the rupture disc(s) was found to be significantly less than the fatigue strength or endurance limit [39,000 psi]
for the 316SS stainless steel, as provided in the ASM Handbook, Volume 19, Fatigue and Fracture, ASM International (1996), Page 1814. Based on this evaluation, the rupture discs are not expected to fail due to fatigue before they are replaced in the next refuel outage (June 2013-Refuel19).
The safety function of the rupture discs is to open to allow the lower piston chamber (LPC) of the MSIV actuators to vent and close the MSIV within the required time frame. To close an MSIV, the LPC must be open or vented. Two vent lines are provided for each MSIV actuator. The normal, non-safety vent line is routed from the actuator through a locked open manual valve and back to the condenser. The backup vent line is routed from the MSIV actuator through a locked open manual isolation valve and a safety-related rupture disc set at 150 psig to an equipment floor drain. A one-time extension of the 5-year surveillance replacement interval for the rupture discs would not prevent the rupture disc(s) from performing its safety function.
Attachment to ULNRC-05844 Page 3 of3 Using the provisions of this relief request as a one-time alternative to the specific requirement of the ASME OM Code Mandatory Appendix 1 1-1360, pursuant to 10 CFR 50.55a (a)(3)(ii), relief from the identified ASME OM Code requirement is requested.
- 6. Duration of Proposed Alternative The proposed alternative would be a one-time extended replacement interval for the MSIV rupture discs such that the interval would expire June 2013 instead of Apri111, 2012. Subsequent rupture discs replacements will be in accordance with the ASME OM Code requirements.
- 7. Precedents A related relief request was approved for the Southern Nuclear Operating Company, Hatch Nuclear Plant Units 1 and 2, Docket Nos. 50-321 and 50-366. Valve ReliefRequest RR-V-5, was approved for the In-service Testing (1ST) fourth 10-year interval for both units. Relief was approved to replace four HPCI system rupture discs every 6 years (3rd refuel) versus every 5 years per the ASME OM Code Mandatory Appendix 1.