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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20210T0631997-08-29029 August 1997 Safety Evaluation Approving Application Re Proposed Restructuring of Enova Corp,Parent Company of San Diego Gas & Electric Co by Establishment of Holding Company W/Pacific Enterprises ML20128L7231996-10-0303 October 1996 Safety Evaluation Supporting Amend 158 to License DPR-13 ML20058B1241993-11-19019 November 1993 Safety Evaluation Accepting Proposal to Leak Rate Test SI Tank Outlet Check Valves by Using Leak Test Method Described in OM-10,Paragraph 4.2.2.3(c) ML20057G3071993-10-18018 October 1993 Safety Evaluation Granting Licensee 930616 Relief Request B-12 Re Hydrostatic Testing of Certain Welds in 4 Inch Line from Main Steam Header to Auxiliary Feedwater Pump ML20056E0851993-08-0202 August 1993 Safety Evaluation Accepting Licensee 890308,910301 & 911217 Responses to NRC Bulletin 88-011 Re C-E Owners Group Program for Evaluation of Pressurizer Surge Line Thermal Stratification ML20056D6421993-07-27027 July 1993 SER Approving Licensee 930305 Relief Requests B-10,B-11 & Code Case N-496 ML20128P8401993-02-17017 February 1993 Safety Evaluation Supporting Amend 153 to License DPR-13 ML20125A4341992-12-0303 December 1992 Safety Evaluation Accepting Alternative Exam Methods Per 10CFR50.55a(a)(3)(i) & Addl Info Re Auxiliary Feedwater Sys Lube Oil Cooling,Per ISI Relief Requests B-7,B-8 & B-9 & Code Case N-481 ML20055E3041988-02-12012 February 1988 Safety Evaluation Supporting Util 871223 & 880111 Proposed Changes to Tech Specs,Including Reducing Lower Limits of Detection for Liquid Radioactive Effluents ML20209H9551987-01-28028 January 1987 SER Re Tdi Diesel Generator Owners Group Findings & Recommendations for Operabilty/Reliabilty of Tdi Emergency Diesel Generators ML20214E4231986-11-19019 November 1986 SER Re Reliability & Operability of Tdi Diesel Engines as Source for Emergency Power.Engines Will Continue to Provide Reliable Svc Until Next Refueling Outage ML20195C8261986-05-16016 May 1986 Safety Evaluation Supporting Amends 47 & 36 to Licenses NPF-10 & NPF-15,respectively ML20207K2701985-11-22022 November 1985 Safety Evaluation Supporting Amends 38 & 27 to Licenses NPF-10 & NPF-15,respectively ML20138B0281985-09-25025 September 1985 Safety Evaluation Supporting Amends 35 & 24 to Licenses NPF-10 & NPF-15,respectively ML20126H0781984-11-30030 November 1984 Draft SER Supporting Return to Svc ML20136H1121982-08-31031 August 1982 Sser Supporting Fire Protection ML20136H0761981-02-0404 February 1981 Marked-up Sser 1 Supporting Fire Protection ML20136E0781981-01-19019 January 1981 Safety Evaluation Supporting Fire Protection Program, Providing Mods Are Made Before Fuel Loading ML20136D9691980-11-11011 November 1980 Safety Evaluation Re Fire Protection Sys.Licensee Proposed Mods Acceptable ML20148C4901978-10-16016 October 1978 Safety Evaluation Supporting Postponement of Permanent ECCS Single Failure Fixes at Facility.Postponement of Installation of Redundant Undervoltage Relays Unacceptable 1999-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 ML20198C3471998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Songs,Units 2 & 3 ML20195H2471998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Songs,Units 2 & 3 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20154M7921998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Songs,Units 2 & 3 ML20155F6081998-09-17017 September 1998 Non-proprietary Version of San Onofre 2 & 3 Replacement LP Rotors ML20151Z9851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Songs,Units 2 & 3 ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20237B8571998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Songs,Units 2 & 3 ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML20236R1031998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Songs,Units 2 & 3 ML20249A9431998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Songs,Units 2 & 3 ML20248B8981998-05-26026 May 1998 Updated SG Run Time Analysis Cycle 9 ML20248B9221998-04-30030 April 1998 Rev 0 to AES 98033327-1-1, Updated Probabilistic Operational Assessment for SONGS Unit 2,Second Mid Cycle Operating Period,Cycle 9 ML20247L5181998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Songs,Units 2 & 3 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003)1998-04-0606 April 1998 LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) ML20217Q6161998-04-0505 April 1998 Failure Analysis Rept 98-005,Failure Analysis of 2HV9305 Motor Starter ML20217A0141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Songs,Units 2 & 3 ML20217D4701998-03-0202 March 1998 Rev 1 to 90459, Failure Modes & Effects Analysis DG Cross- Tie,DCP7048.00SE ML20216J3551998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Songs,Units 2 & 3 ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20203K9141998-02-0303 February 1998 Rev 0 to ESFAS Radiation Monitor Single Failure Analysis. W/96 Foldout Drawings ML20202F9731998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Songs,Units 2 & 3 1999-09-30
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pucc e" 4 UNITED STATES g g NUCLEAR REGULATORY COMMISSION i
'C WASHINGTON, D.C. 20666-0001
,o SAFETY EVALUATION BY THE OFFICE % NUCLEAR REACTOR REGULATION RELATED TO RELIEF FROM CERTAIN RADIOGRAPHIC REQUIREMENTS SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION. UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
in a letter dated August 26,1998, Southern California Edison Company (SCE or the licensee) submitted a request for relief from certain radiographic image-quality requirements at San ,
Onofre Nuclear Generating Station (SONGS), Units 2 and 3. The licensee proposed an '
alternative to the plaque type penetrameters required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code). The proposed alternative is to use wire penetrameters in radiographic inspections. Penetrameters are image quality indicators (101) used to ensure that the desired sensitivity, definition, and contrast has been achieved in radiographic examination of materials.
2.0 BACKGROUND
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2 and 3 components (including supports) must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions of the Code and Addenda that become effective subsequent to the editions specified in paragraphs (g)(2) and (g)(3) of this section and that are incorporated by reference in paragraph (b) of this section, to the extent ,
practical within the limitations of design, geometry and materials of construction of the components.
2.1 Code Requirements The applicable edition of Section XI of the Code for SONGS Units 2 and 3, for the second 10-year inservice inspection (ISI) interval is the 1989 Edition with no addenda. In a submittal dated December 6,1994, SONGS proposed an alternative to the Code that was authorized in a letter from the NRC dated January 11,1995. Specifically, SONGS was authorized to use ASME Code Case N-416-1. This Code Case requires that non-destructive testing (NDE) of welds be performed in accordance with the applicable Subsection of the 1992 Edition of Section lli of the Code. This authorization extends until such time as the Code Case is published in a future revision of Regulatory Guide (RG) 1.147, " Inservice inspection Code Case Acceptability -
ASME Section XI, Division 1." If the licensee continues using the Code Case, the licensee is to follow all provisions in ASME Code Case N-416-1, with limitations issued in Regulatory Guide 1.147, if any.
l 9904210331 990419 l PDR ADOCK 05000361 P PDR I
The use of penetrameiers are contained in paragraphs NB-5111 and NC-5111 to Section 111 of the 1992 Edition of the Code, that state in part "... Radiographic examination shall be in accordance with Section V, Article 2, except that... the penetrameters of Table NB-5111-1 (and NC-5111-1) shall be used in lieu of those shown in Table T-276" of Section V.
2.2 Request for Relief J
Pursuant to 10 CFR 50.55a(a)(3) proposed alternatives to the requirements of paragraphs (c),
(d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The appilicant shall demonstrate that: ( i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The licensee requested relief from the penetrameter requirements in paragraphs NB-5111 and NC-5111 to Section 111 of the 1992 Edition of the Code.
2.3 Basis for Relief The licensee believes that plaque type penetrameters are difficult to use due to their physical placement and radiograph characteristics. The placement of flat plaques on curved surfaces of pipe components usually need some form of shimming. After positioning the plaque on test material and performing a radiographic examination, the recorded radiographic characteristics of the essential T hole is often obscured or distorted due to specimen anomalies, part geometry, or film artifacts outside the area of interest. These difficulties create re-shoot conditions. The remakes have a negative Al_ ARA impact due to the additional radiation exposure to the radiography crew.
The licensee believes that the use of wire type IQls are superior to plaque type 101 for nuclear I I
piping component applications. Wire IQls can be placed directly across the area of interest, thus encompassing the object's range of density and geometry. The one-inch minimum length of the essential 101 wire eliminates the problem of indicator loss due to distortion, anomalies, and part geometry. The wire type IQls provide the same function as the plaque tyoe penetrameters by indicating a change in thickness and spatial resolution of the image without the use of shim blocks and pipe standards.
Wire IQls have been shown to provide quality and sensitivity equivalent to plaque type penetrameters as documented in Table 4 of American Society for Testing and Materials (ASTM) E747-87 and ASME Section V, Article 22, Standard SE-747. Because of the equivalent sensitivity, the proposed testing attemative to use wire IQls provides equivalent testing results to the current plaque type IQls. Therefore, the quality of the inspection and resulting safety of the plant, based on the inspection results, are not impacted by this proposed change, thus providing an acceptable level of quality and safety.
't. 5 3.0 EVALUATION 3.1 Proposed Alternative Examination The licensee proposed applying the sen.divity level specified in Tables NB-5111-1 and NC-5111-1 to Section 111 of the 1992 Edition of the Code to the selection of the ap, priate wire type IQls from Table 4 to Standard SE-747 of Article 22 to Section V of the 199e Edition of the Code.
3.2 Discussion in Volume 17 of the Ninth Edition of the Metals Handbook, published in 1989, it states that wire-type penetrameters are widel used in Europe, and a standard design is used in the United Kingdom, Germany, the Neth lands, and Scandinavia and by the International Organization for Standardization and the Inter, tknal Institute of Welding. The handbook goes on to state that wire penetrameters specified n . .M E 747-87 are widely used in the United States. ASTM developed this specification using a public forum with approval by public consensus.
The ASTM Standard E747-87 referenced in the Metals Handbook is identical to the 1989 Edition of ASME's Standard SE-747-87. To assist in determining equivalence between wire and plaque (hole) type IQls, these two standards provide an equation for calculating equivalency. In the 1989 Edition with 1991 Addenda of the Code, the equivalency equatiewas changed with the revised standard being identified as ASME Standard SE-747. The licensee proposed using the criteria from Table 4 to ASME Standard SE-747 for wire penetrameters as an alternate for the plaque penetrameters required by Tables NB-5111-1 and NC-5111-1 to Section lli of the 1992 Edition of the Code.
Wire penetrameters were not included in Section 111 of Code until the 1992 Edition with 1993 Addenda. Although the1992 Edition with 1993 Addenda of the Code has not been endorsed yet by NRC, this later Addenda to the Code includes requirements on the use of wire and plaque penetrameters. The staff's review compared the licensee's proposed attemative against Table NB-5111-1 (NC-5111-1) from the 1992 Edition with 1993 Addenda of the Code. The staff assembled a table similar to Table NB-5111-1 (NC-5111-1) to Section ill of the 1992 Edition with 1993 Addenda of the Code by merging like data from Table 4 to SE 747 to Section V of the 1992 Edition with Table NB-5111-1 (NC-5111-1) to Section lli of the 1992 Edition. The penetrameters from the newly created wire / plaque table compared against the penetrameters from Table NB-5111-1 (NC-5111-1) to Section lli of the 1992 Edition with 1993 Addenda of the Code showed that the newly created table lists wire diameters equal to or smaller (more conservative) than those in Table NB-5111-1 (NC-5111-1) to Section ill of the 1992 Edition with 1993 Addenda of the Code. The licensee's proposed use of wire penetrameter values from Table 4 to Standard SE-747 of Section V of the 1992 Edition of the Code provide values equal to or more conservative than the values agreed to through the consensus building process used by Section 111 of the Code.
1 J With the licensee applying the sensitivity level specified in Table NB-5111-1 (NC-5111-1) to Section lli of the 1992 Edition of the Code and the wire diameters for penetrameters from Table 4 to Standard SE-747 to Section V of the 1992 Edition of the Code, the staff believes that the results from radiographic examinations will be comparable between wire and plaque penetrameter, thus providing and acceptable level of quality and safety.
4.0 CONCLUSION
Based on the evaluation of the information provided, the staff concludes that the proposed alternative provides an acceptable level of quality and safety. Therefore, the staff authorizes the use of the proposed alternative pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Contributor: David Naujock, NRR Date: April 19, 1999 l
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