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MONTHYEARRS-12-151, Fifth Interval Lnservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Lnservice Inspection Program Plan and Relief Requests Project stage: Request RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Inservice Inspection Program Plan and Relief Requests Project stage: Request RS-12-202, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-19019 November 2012 Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01 Project stage: Supplement ML12331A2772012-11-28028 November 2012 Supplemental Information Needed for Acceptance of RLA, I5R-02 Project stage: Acceptance Review RS-12-203, Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-28028 November 2012 Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01 Project stage: Supplement RS-12-205, Supplement to Fifth Inservice Inspection Interval Relief Request I5R-022012-11-28028 November 2012 Supplement to Fifth Inservice Inspection Interval Relief Request I5R-02 Project stage: Supplement ML12348A8302012-12-13013 December 2012 NRR E-mail Capture - Acceptance Review of Dresden, Units 2 and 3, Relief Request I5R-02 Project stage: Acceptance Review ML12348A4272012-12-21021 December 2012 Request for Additional Information Related to the Request for Alternative I5R-03 Project stage: RAI RS-13-005, Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-032013-01-10010 January 2013 Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-03 Project stage: Supplement RS-13-040, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-042013-01-24024 January 2013 Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04 Project stage: Supplement ML13099A2802013-04-0909 April 2013 NRR E-mail Capture - Finalized Dresden RAI I5R-01 I5R-02 and I5R-07 Project stage: RAI ML13110A0072013-04-19019 April 2013 NRR E-mail Capture - RAI for Dresden Units 2 and 3 Exelon Generation Company, LLC Relief Request Nos. I5R-01, I5R-02, and I5R-07 Docket Numbers 50-237 and 50-249 TAC Nos. ME9682-83, ME9684-85, and ME9692-93 Project stage: RAI ML13115A2322013-04-24024 April 2013 NRR E-mail Capture - Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information Project stage: RAI ML13123A0852013-05-0202 May 2013 NRR E-mail Capture - Dresden Relief Request No. I5R-02 - Request for Additional Information Project stage: RAI RS-13-147, Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-062013-05-30030 May 2013 Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-06 Project stage: Request RS-13-107, Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-072013-06-0303 June 2013 Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-07 Project stage: Supplement ML13258A0032013-09-30030 September 2013 Safety Evaluation for the Fifth 10-Year Interval Inservice Inspection Relief Request for Exelon Generation Boiling Water Reactor (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc.) Project stage: Approval ML13260A5852013-09-30030 September 2013 Cover Letter -Safety Evaluation in Support of Request for Relief Associated with the Fifth 10-Year Interval Inservice Inspection Program (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc Project stage: Approval ML13267A0972013-09-30030 September 2013 Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Inspection Program Project stage: Approval 2013-01-24
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Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
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RS-12-202 November 19, 2012 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR
-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request 15R-01
Reference:
Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC)) to U. S.
NRC, "Dresden Nuclear Power Station, Units 2 and 3, Fifth Interval Inservice Inspection Program Plan and Relief Requests," dated September 28, 2012 In the referenced letter, EGC submitted relief requests associated with the fifth inservice inspection (ISI) interval for Dresden Nuclear Power Station (DNPS), Units 2 and 3. Upon further review of Relief Request 15R-01, it became apparent that 10 CFR 50.55a (a)(3)(ii) is the appropriate relief criterion for this request. Therefore, EGC requests to supersede the version of 15R-01 in the referenced letter with the version in the attachment to this letter in its entirety.
EGC continues to request approval of this relief request by September 28, 2013, to support examination of components during the DNPS, Unit 2 Fall 2013 refueling outage which falls within the fifth 10-year ISI interval.
There are no regulatory commitments contained within this letter.
Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC
Attachment:
10 CFR 50.55a Request Number 15R-01, Revision 1 1 RS-12-202 November 19, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed FacilityOperating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 10 CFR 50.55a
Subject:
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request 15R-01
Reference:
Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC>> to U. S. NRC, "Dresden Nuclear Power Station, Units 2 and 3, Fifth Intervallnservice Inspection Program Plan and Relief Requests," dated September 28,2012 In the referenced letter, EGC submitted relief requests associated with the fifth inservice inspection (lSI) interval for Dresden Nuclear Power Station (DNPS), Units 2 and 3. Upon further review of Relief Request 15R-01, it became apparent that 10 CFR 50.55a (a)(3)(ii) is the appropriate relief criterion for this request. Therefore, EGC requests to supersede the version of 15R-01 in the referenced letter with the version in the attachment to this letter in its entirety.
EGC continues to request approval of this relief request by September 28, 2013, to support examination of components during the DNPS, Unit 2 Fall 2013 refueling outage which falls within the fifth 10-year lSI interval.
There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
Patrick R. Simpson Manager -Licensing Exelon Generation Company, LLC
Attachment:
10 CFR 50.55a Request Number 15R-01, Revision 1 ATTACHMENT 10 CFR 50.55a Request Number 15R
-01, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--
1.ASME Code Component(s) Affected:
1 IWB-2500, Table IWB-2500-1 B-D83.100 Inspection of Standby Liquid Control Nozzle Inner Radius Unit 2: N12-1 Unit 3: N12-1 Unit 2: ISI-128, Sheet 3 Unit 3: ISI-125, Sheet 3 2.
The Dresden Nuclear Power Station (DNPS), Units 2 and 3 Inservice Inspection Program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2007 Edition through the 2008 Addenda.
3.Applicable Code Requirement:
IWB-2500 states that components shall be examined and tested as specified in Table IWB-2500-1.
Table IWB-2500-1 requires a volumetric examination to be performed on the inner radius section of all reactor pressure vessel nozzles each inspection interval.
4.
Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that conformance with the Code requirements impose hardship without a compensating increase in the level of quality and safety.
The Standby Liquid Control (SBLC) nozzle, as shown in Figure 15R-01.1, is designed with an integral socket to which the boron injection piping is fillet welded. The SBLC nozzle is located near the bottom of the vessel in an area which is inaccessible for ultrasonic examinations from the inside of the vessel. Therefore, ultrasonic examinations would need to be performed from the outside diameter of the vessel. As shown in Figure 15R-01.1, the ultrasonic scan would need to travel through the full thickness of the vessel into a complex cladding/socket configuration. These geometric and material reflectors inherent in the design prevent a meaningful examination from being performed on the inner radius of the SBLC nozzle.
In addition, the inner radius socket attaches to piping which injects boron at locations far removed from the nozzle. Therefore, the SBLC nozzle inner radius is not subjected to turbulent mixing conditions that are a concern at other nozzles.
Page 1 of 3 Code Class:
Reference:
Examination Category:
Item Number:
==
Description:==
Component Number:
Drawing Number:
ATTACHMENT 10 CFR SO.SSa Request Number ISR-01, Revision 1 Proposed Alternative In Accordance with 10 CFR SO.SSa(a)(3}(ii}
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--1. ASME Code Component(s)
Affected:
Code Class:
Reference:
Examination Category:
Item Number:
Description:
Component Number: Drawing Number: 1 IWB-2500, Table IWB-2500-1 B-D B3.100 Inspection of Standby Liquid Control Nozzle Inner Radius Unit 2: N12-1 Unit 3: N12-1 Unit 2: ISI-128, Sheet 3 Unit 3: ISI-125, Sheet 3 2. Applicable Code Edition and Addenda: The Dresden Nuclear Power Station (DNPS), Units 2 and 3 Inservice Inspection Program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2007 Edition through the 2008 Addenda. 3. Applicable Code Requirement:
IWB-2500 states that components shall be examined and tested as specified in Table IWB-2500-1.
Table IWB-2500-1 requires a volumetric examination to be performed on the inner radius section of all reactor pressure vessel nozzles each inspection interval.
- 4. Reason for Request: Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that conformance with the Code requirements impose hardship without a compensating increase in the level of quality and safety. The Standby Liquid Control (SBLC) nozzle, as shown in Figure 15R-01.1, is designed with an integral socket to which the boron injection piping is fillet welded. The SBLC nozzle is located near the bottom of the vessel in an area which is inaccessible for ultrasonic examinations from the inside of the vessel. Therefore, ultrasonic examinations would need to be performed from the outside diameter of the vessel. As shown in Figure 15R-01.1, the ultrasonic scan would need to travel through the full thickness of the vessel into a complex cladding/socket configuration.
These geometric and material reflectors inherent in the design prevent a meaningful examination from being performed on the inner radius of the SBLC nozzle. In addition, the inner radius socket attaches to piping which injects boron at locations far removed from the nozzle. Therefore, the SBLC nozzle inner radius is not subjected to turbulent mixing conditions that are a concern at other nozzles. Page 1 of 3 ATTACHMENT 10 CFR 50.55a Request Number 15R-01, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--
Compliance with the applicable Code requirements would require an ultrasonic examination to be performed on the outside diameter of the reactor pressure vessel. Geometric and material reflectors would prevent a meaningful examination, resulting in inaccurate data.
Based on this, the Code requirements impose hardship without a compensating increase in the level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(ii).
5.
As an alternate examination, Exelon Generation Company, LLC will perform a VT-2 visual examination of the subject nozzles at DNPS, Units 2 and 3 each refueling outage in conjunction with the Class 1 System Leakage Test.
6.Duration of Proposed Alternative:
Relief is requested for the Fifth Ten-Year Inspection Interval for Dresden Nuclear Power Station Units 2 and 3.
7.
DNPS, Units 2 and 3 fourth inspection interval Relief Request 14R
-01 was authorized in an NRC safety evaluation (SE) dated September 4, 2003. The fifth inspection interval relief request (i.e., 15R-01, Revision 1) utilizes a similar approach that was previously approved.Quad Cities Nuclear Power Station, Units 1 and 2 fourth inspection interval Relief Request 14R-01 was authorized in an NRC SE dated January 28, 2004.
Page 2 of 3 ATTACHMENT 10 CFR SO.SSa Request Number ISR-01, Revision 1 Proposed Alternative In Accordance with 10 CFR SO.SSa(a}(3}(ii}
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--Compliance with the applicable Code requirements would require an ultrasonic examination to be performed on the outside diameter of the reactor pressure vessel. Geometric and material reflectors would prevent a meaningful examination, resulting in inaccurate data. Based on this, the Code requirements impose hardship without a compensating increase in the level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(ii).
S. Proposed Alternate and Basis for Use: As an alternate examination, Exelon Generation Company, LLC will perform a VT-2 visual examination of the subject nozzles at DNPS, Units 2 and 3 each refueling outage in conjunction with the Class 1 System Leakage Test. 6. Duration of Proposed Alternative:
Relief is requested for the Fifth Ten-Year Inspection Interval for Dresden Nuclear Power Station Units 2 and 3. 7. Precedents:
DNPS, Units 2 and 3 fourth inspection interval Relief Request 14R-01 was authorized in an NRC safety evaluation (SE) dated September 4, 2003. The fifth inspection interval relief request (Le., 15R-01, Revision 1) utilizes a similar approach that was previously approved.
Quad Cities Nuclear Power Station, Units 1 and 2 fourth inspection interval Relief Request 14R-01 was authorized in an NRC SE dated January 28, 2004. Page 2 of3 ATTACHMENT 10 CFR 50.55a Request Number 15R-01, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--Vessel (Mn-Mo)I.D.Cladding Safe-End (Stainless Steel)
Pipe(Mn-Mo)(Stainless Steel)
Nozzle 1 15/16" 1/8" Min 6 3/8" FIGURE 15R
-01.1: Two (2) Inch Standby Liquid Control Nozzle Page 3 of 3 ATTACHMENT 10 CFR 50.55a Request Number 15R-01, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a}(3}(ii}
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--Safe-End (Stainless Steel) Vessel (Mn-MO)\ Nozzle (Mn-Mo) 3/4" R Min FIGURE 15R-01.1:
Two (2) Inch Standby Liquid Control Nozzle Page 3 of3 1. D. Cladding