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| #REDIRECT [[TMI-13-043, Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval]] | | {{Adams |
| | | number = ML13074A700 |
| | | issue date = 03/15/2013 |
| | | title = Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval |
| | | author name = Jesse M D |
| | | author affiliation = Exelon Generation Co, LLC |
| | | addressee name = |
| | | addressee affiliation = NRC/NRR, NRC/Document Control Desk |
| | | docket = 05000289 |
| | | license number = DPR-050 |
| | | contact person = |
| | | case reference number = RR VR-01, TMI-13-043 |
| | | document type = Inservice/Preservice Inspection and Test Report, Letter |
| | | page count = 5 |
| | | project = |
| | | stage = Response to RAI |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:TMI-13-043 March 15,2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 10 CFR 50.55a |
| | |
| | ==Subject:== |
| | Response to Request for Additional Information |
| | -Relief Request VR-01 Associated with the Fifth Inservice Testing (1ST) Interval |
| | |
| | ==References:== |
| | : 1) Letter from M. Jesse (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Submittal of Relief Request VR-01 Associated with the Fifth Inservice Testing (1ST) Interval," dated October 18, 2012 2) Letter from P. Bamford (U.S. Nuclear Regulatory Commission) to M. Pacilio (Exelon Generation Company, LLC), "Three Mile Island Nuclear Station, Unit 1 -Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval (TAC No. ME9819)," dated February 25,2013 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) submitted for your review and approval Relief Request VR-01 associated with the Fifth Inservice Testing (1ST) interval for Three Mile Island Nuclear Station (TMI), Unit 1. In the Reference 2 letter, the U.S. Nuclear Regulatory Commission Staff requested additional information. |
| | Attached is our response. |
| | There are no regulatory commitments in this letter. If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510. |
| | Respectfully, ichael D. Jesse / Director -Licensing |
| | & ulatory Affairs Exelon ompany, LLC Response to Request for Additional Information |
| | -RR VR-01 Associated with the Fifth Inservice Testing (1ST) Interval March 15, 2013 Page 2 |
| | |
| | ==Attachment:== |
| | |
| | Response to Request for Additional Information |
| | -Relief Request VR-01 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI Project Manager, [TMI] USNRC Attachment Response to Request for Additional Information |
| | -Relief Request VR-01 Question: |
| | Response to Request for Additional Information Relief Request VR-01 Page 1 of 2 1.) The PORV, 1-RC-RV-2, is categorized as a BIC valve in the referenced request. In addition to the requirements of the OM Code, ISTC-3310 and ISTC-3510 (for which relief is being requested), are any other ASME OM Code ISTC or Mandatory Appendix I test requirements applicable to this valve? Please provide any specific ASME OM Code test requirements for this valve type, but don't provide general test requirements from the OM Code. Response: |
| | Exelon Generation Company, LLC (Exelon) has determined that the following specific ASME OM Code requirements also apply to the Three Mile Island Nuclear Station (TMI), Unit 1 pressurizer Pilot Operated Relief Valve (PORV) and is not requesting relief from any of these: |
| | * ISTC-5110, "Power-Operated Relief Valves (PORVs)." -"Power-operated relief valves shall meet the requirements of ISTC-5100 for the specific Category B valve type and ISTC-5240 for Category C valves." This paragraph specifies the applicable testing for the type of power operator and that Mandatory Appendix I has additional test requirements invoked by ISTC-5240. |
| | These requirements are outlined in the following items. |
| | * ISTC-5111, "Valve Testing Requirements" -This requirement specifies the sequence of the individual tests -seat tightness I leakage testing, stroke testing, and position indication testing. It also requires calibration of the pressure-sensing device in accordance with the Owner's QA program. Position indication testing has been determined to not apply to the TMI, Unit 1 's PORV design. |
| | * ISTC-5112, "Leak Testing" -This requirement specifies that seat tightness of the PORV shall be verified by leak testing in accordance with the requirements of Mandatory Appendix I. This paragraph directs leak testing using the test methodology and requirements for relief valves. |
| | * ISTC-5113, "Valve Stroke Testing" -This requirement provides the Category B exercising requirements, which include stroke time measurement, establishment of limiting stroke time, and testing at normal operating conditions. |
| | * 1-8110, "Steam Service" -This requirement specifies the detailed testing requirements for exercising the valve. Those that apply to TMI, Unit 1 's PORV testing are: test media, thermal equilibrium, and ambient temperature. |
| | * 1-8200, "Seat Tightness Testing" -This requirement specifies that seat tightness testing shall be performed in accordance with the Owner's valve test procedure. |
| | Consideration shall be given to test media, temperature stability, and ambient temperature, as required in 1-8100. Seat tightness testing shall be performed using Response to Request for Additional Information Relief Request VR-01 Page 2 of 2 the same fluid used for set-pressure testing, except as provided by 1-8300. This paragraph and associated subparagraphs (1-8210, 1-8220, and 1-8230) specify seat tightness testing using relief valve requirements (specified in 1-8100). The plant's PORV is not tested with alternative media. The PORV testing described in Exelon's relief request complies with these requirements to ensure the operational readiness of the valve. Question: |
| | 2.) Is the Pressurizer PORV block valve included in the TMI-1 1ST program? If not, please provide the basis for not including this valve in the program. Response: |
| | The pressurizer PORV block valve is identified as 1-RC-V-2 in the TMI, Unit 1 1ST Program Plan, and this valve is included in the scope of the program with both open and closed safety functions.}} |
Letter Sequence Response to RAI |
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MONTHYEARTMI-12-158, Three Mile, Unit 1, Submittal of Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval2012-10-18018 October 2012 Three Mile, Unit 1, Submittal of Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval Project stage: Request ML12321A0922012-11-16016 November 2012 E-mail Acceptance Review Project stage: Acceptance Review ML13044A6652013-02-13013 February 2013 Electronic Transmission, Draft Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval Project stage: Draft RAI ML13045A6432013-02-25025 February 2013 Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval Project stage: RAI TMI-13-043, Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval2013-03-15015 March 2013 Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval Project stage: Response to RAI ML13232A0512013-08-28028 August 2013 Relief Request VR-01, Proposed Alternative Testing of the Pressurizer Pilot Operated Relief Valve Project stage: Other 2013-02-13
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants ML18085A1682018-03-19019 March 2018 Inspection Report for End of Cycle 21 Refueling Outage ML18009A4342018-01-0808 January 2018 Submittal of T1R22 Refueling Outage Lnservice Inspection Owner'S Activity Report ML17087A0822017-03-28028 March 2017 Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program ML16144A7912016-05-21021 May 2016 Inspection Report for Refueling Outage T1R21 TMI-16-023, T1R21 Refueling Outage Inservice Inspection (Isli) Owner'S Activity Report and Attachments2016-02-22022 February 2016 T1R21 Refueling Outage Inservice Inspection (Isli) Owner'S Activity Report and Attachments TMI-15-048, Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program2015-04-13013 April 2015 Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program TMI-14-058, (TMI-1) - Steam Generator Tube Inspection Report2014-05-22022 May 2014 (TMI-1) - Steam Generator Tube Inspection Report TMI-14-069, Submittal of the Fifth Ten-Year Interval Inservice Testing Program2014-05-16016 May 2014 Submittal of the Fifth Ten-Year Interval Inservice Testing Program TMI-14-029, T1R20 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments2014-02-25025 February 2014 T1R20 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments TMI-13-048, Response to Request for Additional Information - Submittal of End of Interval Relief Request RR-12-012013-03-18018 March 2013 Response to Request for Additional Information - Submittal of End of Interval Relief Request RR-12-01 TMI-13-043, Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval2013-03-15015 March 2013 Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval TMI-13-038, Relief Request RR-12-02 Concerning the Installation of a Full Structural Weld Overlay on the Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds and Alloy 600 Safe-End2013-03-11011 March 2013 Relief Request RR-12-02 Concerning the Installation of a Full Structural Weld Overlay on the Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds and Alloy 600 Safe-End TMI-12-071, Transmittal of Steam Generator Tube Inspection Report2012-05-15015 May 2012 Transmittal of Steam Generator Tube Inspection Report TMI-12-016, T1R19 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments2012-02-20020 February 2012 T1R19 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments TMI-11-158, Submittal of Relief Request PR-05 Associated with the Fourth Inservice Testing (IST) Interval2011-10-28028 October 2011 Submittal of Relief Request PR-05 Associated with the Fourth Inservice Testing (IST) Interval ML11105A1602011-04-0505 April 2011 2010 Augmented Reactor Building (Iwl) In-Service Inspection, Topical Report 204, Rev. 0 TMI-11-060, Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval2011-04-0505 April 2011 Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval2011-03-15015 March 2011 ISI Program Plan, Fourth Ten-Year Inspection Interval TMI-11-007, Response to Request for Additional Information Concerning Relief Requests Associated with the Fourth Inservice Inspection Interval2011-01-25025 January 2011 Response to Request for Additional Information Concerning Relief Requests Associated with the Fourth Inservice Inspection Interval TMI-10-101, Three Mile, Unit 1, Supplemental Information Request - Fourth Inservice Inspection (ISI) Interval Relief Request I4R-022010-10-0808 October 2010 Three Mile, Unit 1, Supplemental Information Request - Fourth Inservice Inspection (ISI) Interval Relief Request I4R-02 TMI-10-079, Submittal of Relief Requests Associated with the Fourth Inservice Inspection Interval2010-08-10010 August 2010 Submittal of Relief Requests Associated with the Fourth Inservice Inspection Interval TMI-10-069, Supplement to Cycle 17 Refueling (T1R18) Inservice Inspection (ISI) Summary Report2010-07-0707 July 2010 Supplement to Cycle 17 Refueling (T1R18) Inservice Inspection (ISI) Summary Report TMI-10-033, TMI Unit 1 T1 R18 Outage ASME Code Section XI Inservice Inspection (ISI) Form NIS-1 Owner'S Report for Inservice Inspections, Part I, TMI Unit 1 Form NIS-2 Owner'S Report for Repairs or Replacements, and Topical Report Number 203, Part 22010-04-21021 April 2010 TMI Unit 1 T1 R18 Outage ASME Code Section XI Inservice Inspection (ISI) Form NIS-1 Owner'S Report for Inservice Inspections, Part I, TMI Unit 1 Form NIS-2 Owner'S Report for Repairs or Replacements, and Topical Report Number 203, Part 2 ML1014002732010-04-21021 April 2010 TMI Unit 1 T1 R18 Outage ASME Code Section Xi Inservice Inspection (ISI) Form NIS-1 Owner'S Report for Inservice Inspections, Part I, TMI Unit 1 Form NIS-2 Owner'S Report for Repairs or Replacements, and Topical Report Number 203, Part 1 TMI-09-101, Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 20142009-08-14014 August 2009 Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014 TMI-09-086, Submittal of Concerning Unsatisfactory Laboratory Performance Tests2009-07-30030 July 2009 Submittal of Concerning Unsatisfactory Laboratory Performance Tests ML0605404122006-02-15015 February 2006 Cycle 16 Refueling (T1R16) Inservice Inspection (ISI) Summary Report ML0529403472005-10-14014 October 2005 Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria ML0325213752003-08-27027 August 2003 TMI, Unit 1 - Third Ten-Year Inservice Inspection (ISI) Program, Supplemental Information, Risk-Informed Inservice Inspection Program Alternative to the ASME Boiler & Pressure Vessel Code, Section XI Requirements for Class 1 & 2 Piping Weld ML0227701442002-10-0808 October 2002 (TMI-1), Amergen Energy Company, LLC (Amergen), March 5, 2002, Cycle 14, Inservice Inspection (ISI) Summary Report ML0228302112002-10-0101 October 2002 Third Ten-Year Interval Inservice Inspection (ISI) Program Risk-Informed Inservice Inspection Program Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping Welds 2019-04-30
[Table view] Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24242A3032024-09-0909 September 2024 Letter - Three Mile Island Station, Unit 2, Issuance of Amendment No. 68, Historic and Cultural Resources IR 05000320/20240012024-08-28028 August 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report Nos. 05000320/2024001 and 05000320/2024002 ML24240A2222024-08-27027 August 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24220A2742024-08-15015 August 2024 Request for Additional Information Clarification Call Regarding Three Mile Island Station, Unit 2, Amended Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24135A3292024-08-0909 August 2024 Amendment No 68, Historic and Cultural Resources Cover Letter IR 07200077/20240012024-06-18018 June 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 07200077/2024001 ML24135A1972024-06-13013 June 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0091 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24157A3672024-06-13013 June 2024 Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24120A3242024-05-24024 May 2024 TMI-2 Email to Fws RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24120A2552024-04-29029 April 2024 Annual Radiological Environmental Operating Report ML24113A0212024-04-18018 April 2024 (TMI-2), Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24065A0042024-03-28028 March 2024 Submittal of 2023 Aircraft Movement Data Annual Report ML24088A0122024-03-28028 March 2024 Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) in Accordance with 10 CFR 50.82(a)(7), Revision 6 ML24092A0012024-03-28028 March 2024 (TMI-2), Decommissioning Trust Fund Annual Report ML24085A2152024-03-25025 March 2024 (TMI-2) - Annual Notification of Property Insurance Coverage RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24052A0602024-03-20020 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0061 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24074A3922024-03-14014 March 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML24075A0062024-03-14014 March 2024 List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24044A0092024-02-12012 February 2024 License Amendment Request – Three Mile Island, Unit 2, Historic and Cultural Resources Review, Response to Request for Additional Information IR 05000320/20230042024-02-0707 February 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023004 ML24038A0222024-02-0505 February 2024 Achp Letter on Section 106 Programmatic Agreement Participation IR 05000289/20230062024-01-29029 January 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006 ML23342A1242024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23325A1092024-01-0505 January 2024 Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000320/20230032023-11-28028 November 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003 ML23243A9082023-08-29029 August 2023 Shpo Letter to TMI-2 Regarding Section 106 Activities IR 05000320/20230022023-08-17017 August 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23200A1882023-07-31031 July 2023 TMI-2 Correction Letter Amendment 67 ML23209A7632023-07-28028 July 2023 Letter from PA Shpo to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning ML23192A8272023-07-10010 July 2023 TMI-2 Solutions, LLC - Response to Shpo Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23167A0312023-06-28028 June 2023 Acceptance Review and Schedule for the Request for Exemption from a Requirement from 10 CFR 20, Appendix G, Section Iii.E, EPID L-2023-LLE-0016 ML23171B0222023-06-19019 June 2023 (TMI-2) - Notification Pursuant to 10 CFR 72.140(d) Regarding Application of Previously Approved TMI-2 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 2024-09-09
[Table view] |
Text
TMI-13-043 March 15,2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 10 CFR 50.55a
Subject:
Response to Request for Additional Information
-Relief Request VR-01 Associated with the Fifth Inservice Testing (1ST) Interval
References:
- 1) Letter from M. Jesse (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Submittal of Relief Request VR-01 Associated with the Fifth Inservice Testing (1ST) Interval," dated October 18, 2012 2) Letter from P. Bamford (U.S. Nuclear Regulatory Commission) to M. Pacilio (Exelon Generation Company, LLC), "Three Mile Island Nuclear Station, Unit 1 -Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval (TAC No. ME9819)," dated February 25,2013 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) submitted for your review and approval Relief Request VR-01 associated with the Fifth Inservice Testing (1ST) interval for Three Mile Island Nuclear Station (TMI), Unit 1. In the Reference 2 letter, the U.S. Nuclear Regulatory Commission Staff requested additional information.
Attached is our response.
There are no regulatory commitments in this letter. If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Respectfully, ichael D. Jesse / Director -Licensing
& ulatory Affairs Exelon ompany, LLC Response to Request for Additional Information
-RR VR-01 Associated with the Fifth Inservice Testing (1ST) Interval March 15, 2013 Page 2
Attachment:
Response to Request for Additional Information
-Relief Request VR-01 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI Project Manager, [TMI] USNRC Attachment Response to Request for Additional Information
-Relief Request VR-01 Question:
Response to Request for Additional Information Relief Request VR-01 Page 1 of 2 1.) The PORV, 1-RC-RV-2, is categorized as a BIC valve in the referenced request. In addition to the requirements of the OM Code, ISTC-3310 and ISTC-3510 (for which relief is being requested), are any other ASME OM Code ISTC or Mandatory Appendix I test requirements applicable to this valve? Please provide any specific ASME OM Code test requirements for this valve type, but don't provide general test requirements from the OM Code. Response:
Exelon Generation Company, LLC (Exelon) has determined that the following specific ASME OM Code requirements also apply to the Three Mile Island Nuclear Station (TMI), Unit 1 pressurizer Pilot Operated Relief Valve (PORV) and is not requesting relief from any of these:
- ISTC-5110, "Power-Operated Relief Valves (PORVs)." -"Power-operated relief valves shall meet the requirements of ISTC-5100 for the specific Category B valve type and ISTC-5240 for Category C valves." This paragraph specifies the applicable testing for the type of power operator and that Mandatory Appendix I has additional test requirements invoked by ISTC-5240.
These requirements are outlined in the following items.
- ISTC-5111, "Valve Testing Requirements" -This requirement specifies the sequence of the individual tests -seat tightness I leakage testing, stroke testing, and position indication testing. It also requires calibration of the pressure-sensing device in accordance with the Owner's QA program. Position indication testing has been determined to not apply to the TMI, Unit 1 's PORV design.
- ISTC-5112, "Leak Testing" -This requirement specifies that seat tightness of the PORV shall be verified by leak testing in accordance with the requirements of Mandatory Appendix I. This paragraph directs leak testing using the test methodology and requirements for relief valves.
- ISTC-5113, "Valve Stroke Testing" -This requirement provides the Category B exercising requirements, which include stroke time measurement, establishment of limiting stroke time, and testing at normal operating conditions.
- 1-8110, "Steam Service" -This requirement specifies the detailed testing requirements for exercising the valve. Those that apply to TMI, Unit 1 's PORV testing are: test media, thermal equilibrium, and ambient temperature.
- 1-8200, "Seat Tightness Testing" -This requirement specifies that seat tightness testing shall be performed in accordance with the Owner's valve test procedure.
Consideration shall be given to test media, temperature stability, and ambient temperature, as required in 1-8100. Seat tightness testing shall be performed using Response to Request for Additional Information Relief Request VR-01 Page 2 of 2 the same fluid used for set-pressure testing, except as provided by 1-8300. This paragraph and associated subparagraphs (1-8210, 1-8220, and 1-8230) specify seat tightness testing using relief valve requirements (specified in 1-8100). The plant's PORV is not tested with alternative media. The PORV testing described in Exelon's relief request complies with these requirements to ensure the operational readiness of the valve. Question:
2.) Is the Pressurizer PORV block valve included in the TMI-1 1ST program? If not, please provide the basis for not including this valve in the program. Response:
The pressurizer PORV block valve is identified as 1-RC-V-2 in the TMI, Unit 1 1ST Program Plan, and this valve is included in the scope of the program with both open and closed safety functions.