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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198H5541997-12-29029 December 1997 SER Accepting Request for Approval of ASME Case N-498,rev 1, as an Alternative to Required Hydrostatic Pressure Test for Plant,Unit 2 ML20197K1541997-12-18018 December 1997 SER Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping for North Anna Power Station,Per Util 970919 Submittal ML20199L0501997-11-24024 November 1997 SER Accepting Inservice Insp Program Relief Request NDE-32 ML20199E4971997-11-14014 November 1997 Safety Evaluation Authorizing Proposed Alternative of Licensee Relief Requests NDE-35 & NDE-37,for Plant,Units 1 & 2 During Second 10 Yr Interval ML20217E0701997-09-24024 September 1997 Safety Evaluation Granting Licensee ASME Section XI Relief Request NDE-33 at Plant,Unit 1 ML20217E2411997-09-24024 September 1997 SER Accepting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Unit 1 ML20217E1871997-09-24024 September 1997 SER Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Units 1 & 2 ML20149L2001997-07-29029 July 1997 SER Granting Requests for Relief NDE-33,34 & 35 Re ISI Program,Per 10CFR50.55a(g)(6)(i) ML20149F1321997-07-17017 July 1997 Safety Evaluation Supporting Amends 205 & 186 to Licenses NPF-4 & NPF-7,respectively ML20148H1971997-06-0404 June 1997 Safety Evaluation Granting Licensee Relief Request NDE-31 Related to Inservice Insp Program ML20140F4811997-04-30030 April 1997 Safety Evaluation Accepting Licensee 951207 Proposed Alternative in Request for Relief SPT-16 Re Second 10-yr Interval Inservice Insp Program for Unit 2 ML20133G1561997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Relief Requests for Relief Numbers NDE-27,NDE-28 & NDE-29 ML20133G1911997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Interval Inservice Insp Plan Relief Request NDE-30 ML20138G1931996-10-16016 October 1996 SER Accepting Second 10-year Interval Inservice Insp Plan Request for Relief SPT-14,rev 1 Virginia Electric & Power Co North Anna Power Station,Unit 2 ML20128P1701996-10-10010 October 1996 Safety Evaluation Supporting Second 10-year Interval Inservice Insp Program Plan Requests for Relief NDE-23 Through NDE-30 for Plant Unit 2 ML20128F5981996-10-0101 October 1996 Safety Evaluation Authorizing Licensee Proposed Alternative to Examine Terminal End Welds on Lower Regenerative Heat Exchanger sub-vessels,per 10CFR50.55a(a)(3)(ii) ML20059M1181993-11-15015 November 1993 SER Accepting Category 3 Qualification in Lieu of Category 2 for Pressure Monitoring Instrumentation ML20057C0401993-09-17017 September 1993 Safety Evaluation Re Inservice Testting Program Requests for Relief ML20126C1221992-12-0404 December 1992 Safety Evaluation Authorizing Util to Continue Current Test Method for Interim Period,Based on Util Plans to Develop & Implement Use of non-intrusive Testing Techniques for Check Valves Following 1993 Unit 2 Refueling Outage ML20125B7251992-12-0303 December 1992 Safety Evaluation Granting Temporary Exemptions from Requirements of GDC-2 & 10CFR50.49 for Phase 1,stage 1 of Svc Water Sys Restoration Project ML20062C4441990-10-18018 October 1990 SER Re Station Blackout.Plant Does Not Conform W/Station Blackout Rule ML20247C2091989-09-0707 September 1989 Safety Evaluation Accepting Util 890512 Response to IE Bulletin 80-11, Masonry Wall Design ML20245J8401989-06-28028 June 1989 Safety Evaluation Supporting Restart of Unit 1 & Util 890528 Response to NRC Bulletin 89-001, Failure of Westinghouse Mechanical Steam Generator Tube Plugs ML20195J0061988-11-29029 November 1988 Safety Evaluation Supporting Licensee Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes, Subj to Util Adopting Addl Administrative Controls ML20207F1391988-08-12012 August 1988 Safety Evaluation Supporting Util Responses to IE Bulletin 80-11, Masonry Wall Design, W/Exception of One Open Item ML20196G9081988-03-0404 March 1988 SER Re Util 831104 & 850208 Responses to Generic Ltr 83-28, Item 2.2.1, Equipment Classification (Program for All Safety-Related Components. Responses Acceptable ML20149J9301988-02-18018 February 1988 Safety Evaluation Re Relief Request 6 of Inservice Testing Program for Pumps & Valves ML20154E8221987-12-11011 December 1987 Safety Evaluation Supporting Util Identification of Major Causal Factors Leading to 870715 Tube Rupture Event & Adequacy of Diagnostic & Corrective Measures Implemented in Order to Preclude Similar Events ML20237B5981987-12-11011 December 1987 Safety Evaluation Accepting Util 870915 & 0925 Responses to Steam Generator Tube Rupture on 870715.Util Has Adequately Demonstrated That Primary Failure Mechanism Leading to Event Caused by flow-induced Vibration ML20236F4971987-10-23023 October 1987 Safety Evaluation Re Util 870925 Request for Approval of Steam Generator Downcomer Flow Resistance Plate Mods & Increase in Calculated Offsite Dose Per 10CFR50.59.Mods Acceptable ML20235U8811987-07-13013 July 1987 Safety Evaluation Supporting Request for Relief from Certain Exam & Hydrostatic Test Requirements of ASME Code ML20213G8081987-05-11011 May 1987 SER Re Util 850208 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components. Program Acceptable ML20212K5111987-02-27027 February 1987 SER Accepting Licensee 831104 Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing ML20207Q0651987-01-0909 January 1987 Safety Evaluation Denying Util 850401 Request to Reduce Number of Thimbles Required for Monthly Surveillance Flux Mapping ML20215D0811986-09-30030 September 1986 Safety Evaluation Granting Util 860613 Request for Relief from Inservice Hydrostatic Test Requirements for Svc Water Spray Sys 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
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4 UNITED STATES g .]
P NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30M64001 k*..../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i REQUEST FOR APPROVAL TO REPAIR FLAWS IN ACCORDANCE WITH GENERIC LETTER 90-05 FOR ASME CODE CLASS 3 SERVICE WATER PIPING VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION. UNIT 1 QQCETNO.50338 1.0 JNTRODUCTION 10 CFR 50.55a(g) requires nuclear power facility piping and components to meet the applicable requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (hereafter referred to as the Code).Section XI of the Code specifies Code acceptable repair methods for flaws that exceed Code acceptance limits in piping that is in service. A Code repair is required to restore the structural integrity of flawed Code piping, independent of the operational mode of the plant when the flaw is detected. Those repairs not in compliance with Section XI of the Code are non Code repairs. However, the implementation of required Code (weld) repairs to ASME Code Class 1, 2 or 3 systems is often impractical for nuclear licensees since the repairs normally require an isoletion of the system requiring the repair, and often a shutdown of the nuclear power plant.
Alternatives to Code requirements may be used by nuclear licensees when authorized by the Director- of the Office of Nuclear Reactor Regulation if the proposed alternatives to the requirements are such that they are shown to :
provide an acceptable level of quality and safety in lieu of the Code :
requirements [10 CFR 50.55a(a)(3)(1)], or if compliance with the Code requirements would result in hardship or unusual difficulty without a compen ating increase in the level of quality and safety [10 CFR 50.55a(a)(3)(11)).
A licensee may also submit requests for relief from certain Code requirements when a licensee has determined that conformance with certain Code requirement; is imaractical for its facility (10 CFR 50.55a(g)(5)(114)]. Pursuant to 10 CFR 50.55a(g)(6)(1), the Commission will evaluate determinations of impracticality and may grant relief and may impose alternative requirements as it determines are authorized by law.
ENCLOSURE NR DO Ob33G P PDR
l l
. 1 2
Generic letter (GL) 90 05. "Guidai.ce for Performing Temporary Non Cade Repair of ASME Code Class 1. 2 and 3 Piping." dated June 15, 1990, provides guidance for the staff in evaluating relief requests submitted by licensees for temporary non Code repairs of Code Class 3 )iping. The staff uses the guidance in GL 90 05 as its criteria for macing its safety evaluation of relief requests for temporary non Code repairs of Code Class 3 piping.
2.0 BACKGROUND
On March 19, 1997, at the North Anna Power Station. Unit 1. Virginia Electric and Power Com)any (hereafter referred to as the licensee) identified five locations wit 1 evidence of ossible previous leakage. i.e., stains in a 4" line of the Service Water S stem (SWS),
By letter dated April 29. 1997, pursuant to 10 CFR 50.55a(g)(6)(1), the I licensee requested a relief from the ASME Code.Section XI replacement requirements for the period of March 19. 1997, through May 15.-1997 The licensee based its request for relief on the results of a "through wall flaw" evaluation that was performed in accordance with the guidelines and acceptance criteria contained in GL 90-05.
3.0 LICENSEE'S RELIEF REQUEST 3.1 Comoonents for Which Relief is Reauested Weld # line # Joint Tvoe 13 4"-WS F63 163 03 Butt Weld 16 4"-WS F63 163 03 Butt Weld '
61 4" WS F63-163 03 Butt Weld 64 4" WS F63-163 03 Butt Weld 66 4" WS F63 163 03- Butt Weld The above listed welds are ASME Code Class 3. moderate energy piping in the i SWS. The piping provides cooling water to the Unit 1 control room chillers.
Normal flow is 237 gpm at an operating pressure of 80 psig and operating temperature of 95*F. The design pressure is 150 psig and design temperature is 125'F.
3.2- Section XI Edition for North Anna 1 1983 Edition of the ASME Code.Section XI ucluding Summer 1983 Addenda.
3.3 ASME Section XI Code Reauirement The ASME Code Section XI requires that repairs or replacements of ASME Code Cla;s components be performed in accordance with rules found in Articles IWA-
-400) or IWA 7000, respectively. The intent of these rules serves to provide an sci.eptable means of restoring the structural integrity of a degraded Code Class system back to the original design requirements.
i 1 i 3 ,
3.4 Content of the Relief Reauest Relief is sought from performing a repair or replacement of the service water piping per the requirements of Article IWA 40')0 or IWA 7MO. respectively Relief is being sought for the period of March 19. 1997, throughMay15.i997.
because performing a Code repair dt. ring that period was determined to be not practical. The licensee had accomplished permanent Code repairs for all welds by the end of that period. .
3.5 Basis for Relief Request for relief has been submitted and alternatives to the Code requirements have been proposed by the licensee. The NRC staff reviewed the proposed alternatives for compliance with the )rovisions of 10 CFR '
50.55a(g)(6)(1). The licensee has evaluated tie flaws in accordance with the guidance provided in GL 90 05. Based upon the evaluation it was established that the discovered flaws- satisfy the criteria for non Code repair as described in GL 90 05 and performing permanent re) airs in accordance with the '
ASME Code during the period March 19. 1997 througi May 15. 1997 would have constituted an undue burden (create undue hardship) upon the licensee since the repairs would have necessitated the unnecessary isolation of portions of SWS that are structurally sound and thus reduce the margin of safety.
3.6 Licensee's Alternative Proaram ,
During the period March 19. 1997 through May 15. 1997.-the SWS with the identified possible through wall flaws was monitored by the licensee as ;
follows.
- 1. Weekly visual monitoring of through wall flaws and leakage. '
- 2. Radiographic examination of all welds.
4.0 STAFFEVALVATIONANDCONCLUS{QE 4.1 Doerability Determination. Root Cause Analysis
- and Structural Inteority Evaluation Based on the radiographic testing-(RT) examination data, the flaws were determined to be small voids surrounded by exfo11ation, which is typical of microbiological 1y induced corrosion (MIC). No other type of operationally caused defects were identified by the RT. However, because of the inability for either radiography or ultrasonic techniques to determine the extent of wall degradation the structural assessment considered each indication to be through wall. The licensee evaluated the structural integrity of the piping using.theguidanceofGL9005. Based upon the evaluation. it was determined that the fiawed piping satisfied the criteria of GL 90 05 and the integrity of the piping would be maintained.
4.2 Auamented Insoection To assess the overall ' degradation of the SWS. augmented radiographic and
.o 4
visual examinations were performed on five additional locations on lines having the same function. Three out of the five were also degraded by MIC.
Any indication was treated as a through-wall defect and analyzed for structural integrity in accordance with the guidance >rovided in GL 90 05.
All augmented weld locations were found to be accepta)le, 4.3 Proposed Temocrary Non Code Renair and Monitorina Provisions During the period March 19. 1997, through May 15, 1997, the licensee performed weekly visual monitoring of all areas with possible evidence of leakage. The areas met the criteria for flooding and spraying consequences and structural integrity.
4.4 Staff Conclus,1gns The staff has determined that the licensee's flaw evaluation has been consistent with the guidelines and acceptance criteria of GL 90-05. The staff therefore finds the licensee's structural integrity and operability assessments to be acceptable. During the period of March 19. 1997, through May 15, 1997, the welds were monitored by plant personnel and the flaws were repaired by May 15. 1997.
Furthermore, the staff finds that aerformance of an immediate Code repair during the period March 19, 1997 tirough May 15, 1997, would have resulted in hardship without a compensating increase in the level of quality and safety.
An immediate re) air would have necessitated the isolation of portions of the SWS that are otlerwise structurally sound and capable of aerforming their intended safety function, and would not have been in the 3est interest of plant safety, given the small magnitude of the flaw and the licensee's alternative program.
Accordingly, relief is authorized pursuant to 10 CFR 50.55(a)(3)(ii).
Principal Contributor: G. Georgiev Date: September 24, 1997