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Category:Letter type:BVY
MONTHYEARBVY 24-005, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-30030 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-004, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-23023 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-003, Nuclear Onsite Property Damage Insurance2024-01-0404 January 2024 Nuclear Onsite Property Damage Insurance BVY 24-001, Pre-Notice of Disbursement from Decommissioning Trust2024-01-0202 January 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-030, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-12-20020 December 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-029, Proof of Financial Protection2023-12-12012 December 2023 Proof of Financial Protection BVY 23-028, Pre-Notice of Disbursement from Decommissioning Trust2023-11-28028 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-21021 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-13013 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-025, Pre-Notice of Disbursement from Decommissioning Trust2023-11-0202 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023 License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317 BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-08-0202 August 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-019, Update to 2022 Radiological Effluent Release Report2023-07-24024 July 2023 Update to 2022 Radiological Effluent Release Report BVY 23-018, Update to Nuclear Onsite Property Damage Insurance2023-07-12012 July 2023 Update to Nuclear Onsite Property Damage Insurance BVY 23-017, Pre-Notice of Disbursement from Decommissioning Trust2023-06-29029 June 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023 10 CFR 72.48 Report BVY 23-015, Report of Investigation Pursuant to 1O CFR 20, Appendix G2023-06-0505 June 2023 Report of Investigation Pursuant to 1O CFR 20, Appendix G BVY 23-014, Pre-Notice of Disbursement from Decommissioning Trust2023-05-31031 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Radiological Environmental Operating Report BVY 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023 2022 Radiological Effluent Release Report BVY 23-012, Pre-Notice of Disbursement from Decommissioning Trust2023-05-0202 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-009, 2022 Individual Monitoring NRC Form 5 Report2023-04-24024 April 2023 2022 Individual Monitoring NRC Form 5 Report BVY 23-008, Pre-Notice of Disbursement from Decommissioning Trust2023-04-0606 April 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-006, Status of Decommissioning and Spent Fuel Management Fund for Year Ending 20222023-03-29029 March 2023 Status of Decommissioning and Spent Fuel Management Fund for Year Ending 2022 BVY 23-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-03-29029 March 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-005, Nuclear Onsite Property Damage Insurance2023-03-13013 March 2023 Nuclear Onsite Property Damage Insurance BVY 23-004, Pre-Notice of Disbursement from Decommissioning Trust2023-03-0202 March 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-003, Pre-Notice of Disbursement from Decommissioning Trust2023-01-31031 January 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-030, Documentary Evidence of Performance Bond2022-12-30030 December 2022 Documentary Evidence of Performance Bond BVY 22-028, Re Proof of Financial Protection2022-11-28028 November 2022 Re Proof of Financial Protection BVY 22-027, Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station2022-11-11011 November 2022 Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station BVY 22-026, Pre-Notice of Disbursement from Decommissioning Trust2022-10-31031 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-025, Pre-Notice of Disbursement from Decommissioning Trust2022-10-0404 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-023, Pre-Notice of Disbursement from Decommissioning Trust2022-09-0101 September 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-22022 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-16016 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-020, Pre-Notice of Disbursement from Decommissioning Trust2022-08-0101 August 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-019, Pre-Notice of Disbursement from Decommissioning Trust2022-07-0606 July 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-013, Notification of Revised Decommissioning Cost Estimate2022-06-17017 June 2022 Notification of Revised Decommissioning Cost Estimate BVY 22-018, Pre-Notice of Disbursement from Decommissioning Trust2022-06-0808 June 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-015, 2021 Radiological Environmental Operating Report2022-05-0505 May 2022 2021 Radiological Environmental Operating Report BVY 22-017, Pre-Notice of Disbursement from Decommissioning Trust2022-05-0505 May 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-014, 2021 Radiological Effluent Release Report2022-04-28028 April 2022 2021 Radiological Effluent Release Report BVY 22-012, Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d)2022-04-12012 April 2022 Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) BVY 22-011, Pre-Notice of Disbursement from Decommissioning Trust2022-04-0404 April 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-009, Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 20212022-03-23023 March 2022 Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 2021 BVY 22-008, Pre-Notice of Disbursement from Decommissioning Trust2022-02-24024 February 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-005, ISFSI Decommissioning Funding Plan2022-02-24024 February 2022 ISFSI Decommissioning Funding Plan 2024-01-04
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARBVY 14-075, Relief Request ISI-06 Inservice Inspection Limited Examinations for the Fourth Ten-Year Interval - Supplement 12014-10-23023 October 2014 Relief Request ISI-06 Inservice Inspection Limited Examinations for the Fourth Ten-Year Interval - Supplement 1 BVY 14-063, Relief Request ISI-06 Inservice Inspection Limited Examinations for the Fourth Ten-Year Interval Vermont Yankee Nuclear Power Station2014-08-19019 August 2014 Relief Request ISI-06 Inservice Inspection Limited Examinations for the Fourth Ten-Year Interval Vermont Yankee Nuclear Power Station BVY 13-078, Submittal of Snubber Program for the Fifth Ten-Year Inservice Inspection Interval2013-08-28028 August 2013 Submittal of Snubber Program for the Fifth Ten-Year Inservice Inspection Interval BVY 13-073, Response to Request for Additional Information Regarding Relief Request ISI-02 - Application of Code Case N-7162013-08-15015 August 2013 Response to Request for Additional Information Regarding Relief Request ISI-02 - Application of Code Case N-716 BVY 13-071, Supplemental Information Re Inservice Inspection Program for Fifth Ten-year Interval & Relief Request ISI-052013-08-0707 August 2013 Supplemental Information Re Inservice Inspection Program for Fifth Ten-year Interval & Relief Request ISI-05 BVY 13-018, Inservice Inspection Program for the Fifth Ten-Year Interval2013-03-27027 March 2013 Inservice Inspection Program for the Fifth Ten-Year Interval BVY 13-008, Inservice Testing Program Plan for the Fifth Ten-Year Interval2013-02-0101 February 2013 Inservice Testing Program Plan for the Fifth Ten-Year Interval BVY 12-086, Inservice Inspection Program Relief Request ISI-PT-02, (Fourth ISI Program Interval)2012-12-21021 December 2012 Inservice Inspection Program Relief Request ISI-PT-02, (Fourth ISI Program Interval) BVY 12-010, Vermont, Submittal of Inservice Inspection, Repair and Replacement for 20112012-02-0101 February 2012 Vermont, Submittal of Inservice Inspection, Repair and Replacement for 2011 BVY 10-049, Summary Report - Inservice Inspection and Repair and Replacement2010-08-23023 August 2010 Summary Report - Inservice Inspection and Repair and Replacement BVY 09-066, 10CFR50.55a(a)(3)(i) Inservice Inspection Program Request VY-ISI-0142009-12-14014 December 2009 10CFR50.55a(a)(3)(i) Inservice Inspection Program Request VY-ISI-014 CNRO-2009-00003, Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activ2009-03-17017 March 2009 Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activities BVY 09-011, 2008 Summary Report Inservice Inspection and Repair or Replacement2009-02-0909 February 2009 2008 Summary Report Inservice Inspection and Repair or Replacement BVY 07-071, Re-Submittal of Relief Request No. ISI-PT-01, Alternate Testing for Buried Piping Components, Fourth Inservice Inspection (ISI) Interval2007-10-18018 October 2007 Re-Submittal of Relief Request No. ISI-PT-01, Alternate Testing for Buried Piping Components, Fourth Inservice Inspection (ISI) Interval BVY 07-061, Summary Reports for Inservice Inspection and Repairs or Replacements2007-09-0404 September 2007 Summary Reports for Inservice Inspection and Repairs or Replacements BVY 06-072, Response to Request for Additional Information Regarding Relief Request ISI-013, Fourth 10-Year ISI Interval2006-08-25025 August 2006 Response to Request for Additional Information Regarding Relief Request ISI-013, Fourth 10-Year ISI Interval BVY 06-029, Relief Request ISI-013, Fourth ISI Interval2006-03-27027 March 2006 Relief Request ISI-013, Fourth ISI Interval BVY 06-013, Summary Reports for In-Service Inspection and Repairs or Replacements2006-02-0808 February 2006 Summary Reports for In-Service Inspection and Repairs or Replacements ML0706803582006-01-25025 January 2006 4.14.1: Inservice Inspection (ISI) Program, Evaluation of Aging Management Programs, 01/25/2006 ML0706703432006-01-25025 January 2006 Containment Inservice Inspection (CII) Program, Evaluation of Aging Management Programs, 01/25/2006 BVY 04-116, Summary Reports for In-service Inspection and Repairs or Replacements2004-10-20020 October 2004 Summary Reports for In-service Inspection and Repairs or Replacements ML0414602802004-05-17017 May 2004 Supplement to Relief Request ISI-06 BVY 03-106, Revision to Vermont Yankee'S 2002 Summary Report for In-service Inspection (NIS-1 Report)2003-11-18018 November 2003 Revision to Vermont Yankee'S 2002 Summary Report for In-service Inspection (NIS-1 Report) ML0328104402003-10-0101 October 2003 Supplement 2 to Fourth-Interval Inservice Inspection (ISI) Program Plan, Submittal of Relief Request RI-01 ML0327403892003-09-25025 September 2003 Supplement to Fourth Interval Inservice Inspection (ISI) Program Plan, Submittal of Relief Request ISI-06 ML0316309692003-06-0505 June 2003 Supplement to Fourth-Interval Inservice Testing (IST) Program Plan ML0309903502003-04-0101 April 2003 Fourth-Interval Inservice Inspection Program Plan, Fourth-Interval Inservice Inspection Pressure Test Program & Request for Approval of ISI Relief Requests, Attachment 2, Appendix C - Attachment 3, Appendix a, Table 1 ML0309903282003-04-0101 April 2003 Fourth-Interval Inservice Inspection Program Plan, Fourth-Interval Inservice Inspection Pressure Test Program & Request for Approval of ISI Relief Requests, Attachments 1 and 2, Appendix B ML0305805442003-01-22022 January 2003 Fourth-Interval Inservice Testing (IST) Program Plan and Request for Approval of IST Relief Requests, Tables 1 - 21 ML0305805372003-01-22022 January 2003 Fourth-Interval Inservice Testing (IST) Program Plan and Request for Approval of IST Relief Requests, Attachments 1 and 2 ML0706802592001-05-15015 May 2001 Report for IWE Inspections Performed for RF022, 05/15/2001 ML0706704081999-11-28028 November 1999 Torus General Visual Report, 10/28/1999 (55 Pages) 2014-08-19
[Table view] |
Text
Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Rd
%-lmýEnhqW Vernon, VT 05354 Tel 802 257 7711 Christopher J. Wamser Site Vice President BVY 12-086 December 21, 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Inservice Inspection Program Relief Request ISI-PT-02 (Fourth ISI Program Interval)
Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Nuclear Operations, Inc. (Entergy) hereby requests NRC approval of the following relief request for Vermont Yankee Nuclear Power Station (VY) for the fourth ten-year inservice inspection (ISI) program interval, which began on September 1, 2003.
Entergy has determined that compliance with certain inspection requirements of ASME Section XI would result in unnecessary hardship or unusual difficulty without a compensating increase in the level of quality and safety. The details of the proposed relief request are attached.
Entergy requests approval by March 1, 2013, to support the upcoming VY refueling outage in March 2013.
There are no new regulatory commitments being made in this submittal.
If you have any questions or require additional information, please contact Mr. Robert J. Wanczyk at (802) 451-3166.
Sincerely, CJW/plc cc list: next page bqj
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BVY 12-086 / Page 2 of 2 Attachments: 1. 10 CFR 50.55a Relief Request ISI-PT-02
- 2. Reactor Pressure Vessel Head Flange Leak-Off Lines Sketches cc: Mr. William M. Dean Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of 'Prussia, PA 19406-2713 Mr. Richard V. Guzman, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Rd Vernon, VT 05354 Ms. Elizabeth Miller, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, VT 05620-2601
BVY 12-086 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station 10 CFR 50.55a Relief Request ISI-PT-02
BVY 12-086 / Attachment 1 / Page 1 of 3 10 CFR 50.55a Relief Request ISI-PT-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without a Compensating Increase in Level of Quality or Safety--
- 1. ASME Code Components Affected
Description:
Reactor pressure vessel head flange leak-off lines originating from reactor vessel nozzles N-13 and N-14 ASME Code Class: 2 Examination Category: C-H (all pressure retaining components)
Item Number: C7.10 Components Affected: Valve FCV-2-20, valve FCV-2-21, orifice RO-2-23, valve V2-22, excess flow check valve SL-2-23, pressure instrument PI-2-101, pressure switch PS-2-102, and associated piping and fittings
- 2. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition through 2003 Addenda
- 3. Applicable Code Requirement IWC-5221: The system leakage test shall be conducted at the system pressure obtained while the system, or portion of the system, is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability (e.g., to demonstrate system safety function or satisfy technical specification surveillance requirements).
- 4. Reason for Request The ASME Boiler and Pressure Vessel Code requirement for the ASME Code Class 2 reactor pressure vessel (RPV) head flange leak-off lines is to perform a system leakage test at a pressure corresponding to 100% rated power. This is approximately 1005 psig.
However, the configuration of the leak-off lines makes testing difficult and presents a personnel and equipment hazard.
The RPV head flange leak-off line originating from reactor vessel nozzle N13 (N13 leak-off line) is separated from the reactor coolant pressure boundary by one passive membrane, which is a metallic seal ring located on the inner vessel flange. A second seal ring is located on the outside of the tap in the vessel flange. The leak-off line originating from reactor vessel nozzle N14 (N14 leak-off line) has a tap located outside of the second seal ring. For the N13 leak-off line, failure of the inner seal ring is the only condition under which this line is pressurized. The N14 leak-off line requires both seal rings to fail. Therefore, these lines are not expected to be pressurized during normal reactor operation.
The configuration of this piping precludes system leakage testing while the RPV head is removed because the configuration of the vessel taps, coupled with the high test pressure, prevents the taps from having test equipment installed. The N1 3 leak-off line tap has a diameter of 3/16" and the N14 leak-off line tap has a diameter of 1/2". Both taps are smooth walled making the effectiveness of a temporary test connection seal at high pressure
BVY 12-086 / Attachment 1 / Page 2 of 3 limited. Failure of the test connection presents a personnel safety hazard and may result in foreign material entering the reactor vessel.
The configuration also precludes pressurizing the lines with the RPV head installed. The head contains two grooves that hold the seal rings. The seal rings are held in place by a series of retainer clips that are housed in recessed cavities in the flange face. If a system leakage test was performed via the N13 leak-off line, the inner seal ring would be pressurized in a direction opposite its design function. This test pressure would result in a net inward force on the inner seal ring that would tend to push it into the recessed cavity that houses the retainer clips. The thin seal ring material would likely be damaged by the inward force. The same situation exists for the outer seal ring when testing via the N14 leak-off line.
Also, not installing the seal rings in order to perform a system leakage test requires the additional time and radiation exposure associated with the subsequent removal and reinstallation of the RPV head to install the seal rings prior to startup. Purposely failing the seal rings would require purchasing new seal rings in addition to the subsequent removal and reinstallation of the RPV head.
Considering this information, compliance with IWC-5221 will result in undue hardship and unusual difficulty without a compensating increase in the level of quality or safety.
- 5. Proposed Alternative and Basis for Use In lieu of the requirements of IWC-5221, a VT-2 visual examination will be performed during the next refueling outage in March 2013 on the accessible portions of the affected components. This is the last refueling outage in the fourth inservice inspection (ISI) program interval. The examination will be conducted with the affected components subject to static pressure head with the RPV head removed and the refueling cavity filled to its normal refueling water level for at least four (4) hours. The static head developed with the leak-off lines filled with water will allow for detection of pressure boundary failures.
This proposed alternative is identical to that presented in Code Case N-805. However, this Code Case has not yet been approved by the NRC and is not yet identified in Regulatory Guide 1.147, "In-service Inspection Code Case Acceptability, ASME Section XI, Division 1".
- 6. Duration of Proposed Alternative This alternative is requested for the remainder of the fourth ISI program interval, which ends on August 31, 2013.
BVY 12-086 / Attachment 1 / Page 3 of 3
- 7. Precedents (1) Comanche Peak, Unit 1, Relief Request No. C-2 for the Unit 1 Reactor Pressure Vessel Leak-off Flange (Third ISI Interval Start Date: August 13, 2010); submittal, dated August 23, 2012, is under review by NRC; Docket No. 50-445 (ADAMS Accession No. ML12250A670]
(2) LaSalle County Station, Units 1 and 2 - Request for Relief Nos. 13R-03, 13R-04, 13R-08, 13R-09 and 13R-10: Third 10-Year Interval In-service Inspection Program Plan (TAC NOS. MD5459, MD5460, MD5390, MD5463, MD5464, MD5465, MD5466, MD5467, and MD5468); January 30, 2008; Docket Nos. 50-373 and 50-374 [ADAMS Accession No. ML073610587]
(3) Susquehanna Steam Electric Station, Units 1 and 2 - Third 10-Year Inservice Inspection Interval Program Plan (TAC NOS. MC1185, MC1186, MC1191, MC1192, MC1193, MC1194, MC1195, MC1196, MC1197, MC1198, MC1199, MCI200); September 24, 2004; Docket Nos. 50-387 and 50-388 [ADAMS Accession No. ML042680078]
The following precedents pertain to approved relief requests for leak-off lines classified as ASME Code Class 1:
(4) Millstone Power Station, Unit No. 3 - Issuance of Relief Request IR-3-11 Regarding Use of American Society of Mechanical Engineering Code,Section XI, 2004 Edition (TAC No. ME1263); April 29, 2010; Docket No. 50-423 [ADAMS Accession No. ML101040042]
(5) Limerick Generating Station, Units 1 and 2, Evaluation of Relief Requests RR-33, RR-34 and RR-35, Associated with the Second In-service Inspection Interval (TAC Nos.
MD8071, MD8073, MD8074, MD8075, and MD8076); January 27, 2009; Docket Nos.
50-352 and 50-353 [ADAMS Accession No. ML090060218]
(6) Limerick, Units 1 and 2 -- Evaluation of Relief Requests 13R-02, 13R-06, 13R-07, 13R-08, 13R-09, 13R-10, 13R-1 1, 13R-12, Associated with the Third In-service Inspection Interval (TAC Nos. MD5200 and MD5201); March 11, 2008; Docket Nos. 50-352 and 50-353
[ADAMS Accession No. ML080500584]
(7) North Anna Power Station, Unit No's. 1 and 2 Re: ASME Code Third 10-year ISI Program. (TAC No's MC5588, MC5589, MC5590, MC5591, MC5592, MC5593, MC5594, MC5595, MC5599 and MC5600); February 9, 2006; Docket Nos. 50-338 and 50-339 [ADAMS Accession No. ML060450517]
- 8. Reference Code Case N-805, "Alternative to Class1 Extended Boundary End of Interval or Class 2 System Leakage Testing of the Reactor Vessel Head Flange O-Ring Leak-Detection System," approved by the American Society of Mechanical Engineers (ASME) on February 25, 2011
BVY 12-086 Docket No. 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Reactor Pressure Vessel Head Flange Leak-Off Lines Sketches
BVY 12-086 / Attachment 2 / Page 1 of 2 4
FRESSUM 1--IA
BVY 12-086 / Attachment 2 / Page 2 of 2 Inner Seal Outer Seal Ring (typ.) -* *Ring (typ.)
Detail of Reactor Pressure Vessel Head Flange Leak Detection Taps (From drawing 5920-00327)