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MONTHYEARML20202C0151986-06-27027 June 1986 Forwards Request for Relief from ASME Code Section XI for Reverse Purge Lines on All Feedwater Lines to Steam Generators for Listed Welds & on Nuclear Svc Water Sys Determined Impractical.W/One Oversize Drawing.Fee Paid Project stage: Request ML20206Q5711986-09-0303 September 1986 SER Granting Util 860627 Request for Relief from ASME Section XI Inservice Hydrostatic Pressure Test Requirements. Alternative Exams Will Provide Necessary Added Assurance of Svc Water Sys Structural Reliability Project stage: Other ML20206Q5441986-09-0303 September 1986 Forwards SER Granting Util 860627 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Reverse Purge Lines on Feedwater Lines to Steam Generator & Four Welds on Svc Water Sys Project stage: Approval 1986-06-27
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20249B6281998-06-12012 June 1998 Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower ML20248B0441998-05-27027 May 1998 Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety ML20197A6551998-03-0202 March 1998 Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet ML20203B1071998-02-0404 February 1998 Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20199F3361998-01-28028 January 1998 Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2 ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211E6871997-09-22022 September 1997 SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20148S2231997-07-0202 July 1997 Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2 ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20134P2421997-02-20020 February 1997 Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications ML20134G5551996-11-0707 November 1996 Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel ML20059G8601993-10-29029 October 1993 SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval ML20057F4121993-10-12012 October 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i) ML20057A0361993-08-26026 August 1993 Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively ML20056H3191993-08-24024 August 1993 SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations ML20126H3171992-12-28028 December 1992 Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage ML20058N7961990-08-0909 August 1990 Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247H7611989-07-18018 July 1989 Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively ML20246C4621989-06-29029 June 1989 Safety Evaluation Granting Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code ML20247C0171989-05-18018 May 1989 Safety Evaluation Supporting Util Actions to Recover from 890307-08 Unit 1 Steam Generator Tube Rupture Event ML20235M7781989-02-23023 February 1989 Safety Evaluation Supporting Util 890505 Relief Request 88-04 Re Addition of Insp Port on Containment Spray HX 1A ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program ML20236M9631987-11-0606 November 1987 Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue ML20236A2901987-10-14014 October 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20236H5291987-07-31031 July 1987 Safety Evaluation Granting Util 870407 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing ML20209B1511987-01-28028 January 1987 SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing ML20207E7551986-12-30030 December 1986 SER Supporting Removal of RCS Thermal Sleeves ML20212D7271986-12-29029 December 1986 SER Re Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs for Reactor Trip Sys Components. Response Acceptable.Item 2.1 Closed ML20212D7411986-12-29029 December 1986 Safety Evaluation Re Util 850827 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys.Relief Justified ML20206M5621986-08-13013 August 1986 SER Accepting 840808 & 850621 Responses to IE Info Notice 84-90, Main Steam Line Break Effect on Environ Qualification of Equipment. Higher Temp Will Not Preclude Ability to Shut Down Reactor in Safe Shutdown Condition ML20215A9671986-05-22022 May 1986 SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl ML20137Y1761986-02-28028 February 1986 SER Accepting SPDS for Interim Implementation Until Listed Open Items Resolved ML20137T8871986-02-0606 February 1986 Safety Evaluation Supporting SPDS as Interim Implementation Until Open Issues Resolved.Issues Include Hot Leg Temp,Rhr Flow Rate,Stack Monitor,Steam Generator Radiation & Containment Isolation ML20138R5841985-10-31031 October 1985 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.1.3,3.2.1,3.2.2,3.2.3,4.1 & 4.5.1 ML20134B8221985-08-0606 August 1985 Sser Supporting Dcrdr ML20128G1111985-06-21021 June 1985 SER of Util Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability).Response to Item 1.2 Complete & Acceptable ML20129D5521985-05-30030 May 1985 SER Accepting Licensee Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program Description & Procedure ML20126J3601981-04-30030 April 1981 Safety Evaluation Re Emergency Preparedness Evaluation Rept 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
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-h' ENCLOSURE SAFETY EVALUATION REPORT ON RE00ESTS FOR RELIEF FROM INSERVICE INSPECTION REOUIREMENTS DUKE POWER COMPANY MCGUIRE NUCLEAR STATION UNIT 2 DOCKET NO. 50-370 t
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I. BACKGROUND By letter dated June 27, 1986, Duke Power Company (the licensee) requested relief from inservice hydrostatic pressure test requirements of the 1980
, Edition through Winter 1980 Addenda of Section XI of the ASME Code at McGuire Nuclear Station Unit 2. This report provides an evaluation of the licensee's requests, supporting information, and alternative examinations or tests, as well as the staff's bases for granting or denying the requests pursuant to 10 CFR 50.55a(g). The reliefs granted remain in effect for the first ten-year inspection interval unless revised or modified prior to the end of the interval . The relief requests are evaluated below.
II. EVALUATION OF RELIEF REQUEST
- 1. Class 2 Hydrostatic Pressure Test of Feedwater System Code Examination Requirement 4
After repairs by welding on the pressure retaining boundary, a system hydrostatic test shall be performed in accordance with IWC-5000.
Code Relief Request Relief is requested from performing the hydrostatic pressure test on four full penetration groove 2-inch pipe welds and five 2-inch socket welds on four separate feedvater lines, after feedwater system modification. The subject welds are on the reverse purge lines on the feedwater lines to the steam l genera tors.
Licensee Basis for Relief The main feedwater system supplies water to the steam generators where it removes heat from the reactor coolant system. Piping on Unit 2 feedwater (CF) .
- system is to be modified in order to prevent a possible 2" Ifne rupture due to I insufficient weld size where the concentric reducer attaches to the 2" piping.
Performing a hydrostatic test on the feedwater piping would be impractical, extre:nely difficult, and very costly, due to the following reasons:
8609050046 860903 PDR ADOCK 05000369
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ENCLOSURE SAFETY EVALUATION REPORT ON REOUESTS FOR RELIEF FROM INSERVICE INSPECTION RE0VIREMENTS DUKE POWER COMPANY MCGUIRE NUCLEAR STATION UNIT 2 DOCKET NO. 50-370 I. BACKGROUND By letter dated June 27, 1986, Duke Power Company (the licensee) requested relief from inservice hydrostatic pressure test requirements of the 1980 Edition through Winter 1980 Addenda of Section XI of the ASME Code at McGuire Nuclear Station Unit 2. This report provides an evaluation of the licensee's requests, supporting information, and alternative examinations or tests, as well as the staff's bases for granting or denying the requests pursuant to 10 CFR 50.55a(g). The reliefs granted remain in effect for the first ten-year inspection interval unless revised or modified prior to the end of the interval. The relief requests are evaluated below.
II. EVALUATION OF RELIEF REQUEST
- 1. Class 2 Hydrostatic Pressure Test of Feedwater System '
Code Examination Requirement After repairs by welding on the pressure retaining boundary, a system hydrostatic test shall be performed in accordance with IWC-5000.
i l
Code Relief Request Relief is requested from performing the hydrostatic pressure test on four full
- penetration groove 2-inch pipe welds and five 2-inch socket welds on four i separate feedwater lines, after feedwater system modification. The subject welds are on the reverse purge lines on the feedwater lines to the steam generators.
Licensee Basis for Relief The main feedwater system supplies water to the steam generators where it removes heat from the rcactor coolant system. Piping on Unit 2 feedwater (CF) .
system is to be modified in order to prevent a possible 2" line rupture due to insufficient weld size w1ere the concentric reducer attaches to the 2" piping.
Performing a hydrostatic test on tha feedwater piping would be impractical, extremely difficult, and very cost 1'y, due to the following reasons:
l 8609050046 860903 PDR ADOCK 05000369
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(a) Isolation and preparation of this system would result in considerable additional radiation exposure to personnel.
(b) Additional time required to gag safety relief valves.
(c) Additional time required to pin or block main steam constant support hangers.
(d) Potential damage due to static load on main steam system caused by water solid condition.
(e) Potential damage to steam generator tube bundle.
(f) Potential leakage through main steam isolation valves, feedwater isolation valves, and other valves in the system (inability to hold pressure).
(g) Potential damage to instrumentation, or considerable delay due to isolation / removal of instrumentation.
(h) Loss of steam generator hydro cycle.
In addition to these reasons, the alternative examinations propos~ed below are
- equal to or better than the required testing per the code. This area of the system falls into the same area as that for which reliefs from hydrostatic testing have previously been granted for McGuire.
Licensee Proposed Alternative Examination A 100% penetrant test of all boundary welds plus an additional inservice leak test with system at operating pressure will be perfomed. Also, a hydro will be performed at the ten-year inspection interval per Section XI of the ASME Code. These examinations, with the exception of the hydrostatic-test, will be conducted after the feedwater piping modification is complete and prior to the system being declared operable.
i Staff Evaluatior. and Conclusions t
Substantial manpower expenditure and occupational radiation exposure are i required to perfom the hydrostatic pressure tests. The licensee has proposed not to perform the hydrostatic tests after system modification. However, the licensee is committed to performing the nomally required hydrostatic tests during the ten-year inspection interval. A penetrant surface examination as I
proposed by the licensee is acceptable for assessing the integrity of socket r welds and small diameter piping welds. Furthermore, the additional inservice leak test as proposed will provide assurance of the integrity of the subject welds, i
l Based on the staff's evaluation and the licensee's discussion above, Code requirements are impractical. It is further concluded that the alternative examinations discussed above will provide necessary added assurance of the feedwater lines' structural reliability. The commission has determined to grant relief from the hydrostatic test requirements as requested based upon the conclusion that it is authorized bylaw, will not endanger life or property or the common defense and security, and is otherwise in the public interest.
l 3-t I 2. Class 3 Hydrostatic Pressure Test of Nuclear Service Water System Code Examination Requirement After repairs by welding on the pressure retaining boundary, a system hydrostatic test shall be performed in accordance with IWD-5000.
Code Relief Request Relief is requested from perfonning the hydrostatic pressure test on the inside and outside welds on two 18" slip-on flanges on the Nuclear Service Water System (RN) after system modification. The welds are numbered as 2RN2F2713, 2RN2F2714, 2RN132-4, and 2RN132-5 in Figure 1 in the licensee's submittal.
Licensee Basis for Relief An 84" section of carbon steel piping was removed from the RN system per NSM MG-20636 Rev. 1. An 84" section of stainless steel piping with flanged connections replaced the carbon steel section. The two subject slip-on flanges connect the stainless piping to the old carbon piping. The new stainless section contains the RN pump 2B flow element, and is located on the pump discharge header.
Hydrostatic testing of the subject welds would be impractical based on the following reasons:
(A) Section of piping containing subject welds cannot be adequately isolated for hydrostatic testing. Isolation valves are large butterfly valves ranging from 10" to 30" in sizes with a history of leakage.
(B) Attempts at hydrostatic testing between a blind flange and a Thaxton high pressure mechanical pipe plug failed. Irregularities on the inside surface of the RN piping due to corrosion, would not allow the plug to seat properly.
(C) Additional testing as specified below is better than required by ASME Class 3 requirements.
Licensee Proposed Alternative Test All welding was subject to MT examination. An inservice leak inspection was conducted per McGuire procedure MP/0/A/7650/76 at system pressure and temperature. All examinations have been done.
Staff Evaluation and Conclusions 1 The subject section of pipe cannot be isolated adequately for hydrostatic testing. Attempts to use a mechanical pipe plug for isolation failed.
However, the pipe plug held for RN Train A and that train was hydrostatically tested. This relief request is associated with RN Train B. A magnetic y,,.,,--.m- - , - _ . , . , . , . - , - - - - , , , - - . .e. , - _ , , . . _ _ . - - . - - , ,- _,a_n.n_, _ , , , - . - _ . _ . - . . - - . . , - . , - . - - - - ,,
3 I particle surface examination as proposed by the licensee is acceptable for assessing the integrity of subject Class 3 welds. Furthermore, the inservice leak test as proposed will provide assurance of the integrity of the subject welds.
Based on the staff's evaluation and the licensee's discussion above, Code requirements are impractical. It is further concluded that the alternative examinations discussed above will provide necessary added assurance of the Nuclear Service Water System's structural reliability. The Commision has de~
termined to grant relief from the hydrostatic test requirements as requested based upon the conclusion that it is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest.
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