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| | number = ML20217K846 | | | number = ML20217K846 |
| | issue date = 04/24/1998 | | | issue date = 04/24/1998 |
| | title = Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of Rg 1.147 | | | title = Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 |
| | author name = | | | author name = |
| | author affiliation = NRC (Affiliation Not Assigned) | | | author affiliation = NRC (Affiliation Not Assigned) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 ML20198J0921997-09-18018 September 1997 Safety Evaluation Authorizing Licensee & Suppls & 16 Request for Approval of Alternative Reactor Vessel Weld Exam,Per 10CFR50.55a(g)(6)(ii)(A)(5) for Plant, Unit 2 for Next 2 Operating Cycles ML20198H2351997-09-0808 September 1997 Safety Evaluation Approving Licensee 970311 Request for Use of ASME Code Case N-509 & Relief from ASME Code Section IX Requirements for Exam of Hpcip Studs for Plant,Units 1 & 2 ML20137A4831997-03-18018 March 1997 SER Re CP&L Review of Power Uprate Process & Commitment Preventing Operation at Uprated Power Levels for Plant, Units 1 & 2 ML20129E0821996-09-26026 September 1996 Safety Evaluation Supporting Request to Use Certain Portions of Later Edition of ASME Code for Inservice Leakage Testing Valves for Brunswick Steam Electric Plant Units 1 & 2 ML20056D6761993-07-28028 July 1993 Safety Evaluation Concluding That Interior Masonry Walls May Be Downgraded to non-fire Related ML20128K7711993-02-11011 February 1993 Safety Evaluation Granting Relief from Certain Inservice Testing Program Requirements for Several Pumps & Valves ML20198E5081992-11-23023 November 1992 Safety Evaluation Accepting Licensee 120-day Response to Suppl 1 to GL 87-02 ML20246D6811989-08-18018 August 1989 Safety Evaluation Supporting Installation & Design of Nitrogen Pneumatic Sys,Per Generic Ltr 84-09,by Adding New Check Valves to Existing Drywell Noninterruptible Instrument Air Lines ML20246C4201989-06-27027 June 1989 SER Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Operating Reactors ML20247P6201989-06-0101 June 1989 Safety Evaluation Supporting Util SAFER/GESTR-LOCA Analysis ML20247M1911989-05-25025 May 1989 Safety Evaluation Re Denial of Amend Request to Licenses DPR-71 & DPR-62 ML20246P9401989-05-10010 May 1989 Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp Program ML20246J5531989-05-0909 May 1989 Safety Evaluation Concluding That Plant Can Be Safely Operated for Another 18-month Fuel Cycle in Configuration Following Reload 5,per Improvements,Insps & Repairs to Plant IGSCC ML20245D3761989-04-25025 April 1989 Safety Evaluation Supporting Licensee IGSCC Program for Refuel 7 Outage ML20236D5481989-03-17017 March 1989 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability ML20236D5381989-03-17017 March 1989 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety-related Components ML20236D4641989-03-15015 March 1989 Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Concerning Equipment Classification & Vendor Interface for Reactor Trip Sys Components ML20235Z2841989-03-0808 March 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2 ML20235Z3451989-03-0808 March 1989 Safety Evaluation Supporting Util Compliance W/Atws Rule, 10CFR50.62 Re Power Testability Features of Alternate Rod Insertion Sys & Recirculating Pump Trip Design ML20235M5771989-02-16016 February 1989 Safety Evaluation Supporting Control Room Habitability Sys of Plant & Acceptability of Existing Tech Spec Re Control Room Pressurization Requirement ML20147G0661988-03-0202 March 1988 Safety Evaluation Supporting Proposed Functional Testing Plan for Snubbers ML20236D1311987-10-22022 October 1987 Safety Evaluation Re Util Request for Relief from Schedular Requirements for Performance of Visual Insp & Hydrostatic Test of CRD Withdrawal & Insert Lines.Granting of Request Recommended ML20235A7331987-09-18018 September 1987 Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable NUREG-0661, Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved1987-05-0707 May 1987 Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved ML20212H5671987-01-16016 January 1987 Safety Evaluation Supporting Util Response to Generic Ltr 83-08 Re Restoring Safety Margins of Vacuum Breakers by Replacing Critical Parts W/Adequate Matls ML20207A8531986-11-0505 November 1986 Safety Evaluation Supporting Operation for Full Fuel Cycle W/O mid-cycle Insp for Crack Growth ML20215N3771986-10-30030 October 1986 Safety Evaluation Re Util 860320 Response to Generic Ltr 84-09, Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii). Licensee Should Remove All Potential Oxygen Sources from Containments ML20203N0081986-09-17017 September 1986 Safety Evaluation Supporting Util 850919 Request for Relief from Installing Excess Flow Switch & Automatic Shutoff Valve in Diesel Fire Pump Fuel Line to Provide Protection in Event of Fuel Line Rupture ML20212N0201986-08-22022 August 1986 Safety Evaluation Denying Util 860325 Request for Relief from Inservice Insp Requirements of ASME Code Section XI, Table IWC-2500-1 for Volumetric Exam of HPCI Pump Studs ML20211G6081986-06-12012 June 1986 Safety Evaluation Supporting IGSCC Insp,Repair & Replacement Program During Dec 1985 Refueling Outage ML20205S2541986-06-0404 June 1986 Safety Evaluation Accepting Rev 2 to Nuclear Const Issues Group Spec 1, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants, for non-ASME Code Welds ML20211A8281986-06-0303 June 1986 Safety Evaluation Re Rev 4 to Offsite Dose Calculation Manual.Rev Acceptable ML20198S7281986-05-29029 May 1986 Safety Evaluation Supporting 851203 Proposal to Modify Tech Spec 3/4.5.3 to Clarify Min Amount of Condensate Storage Tank Water Required to Ensure Operability of Core Spray Sys During Operating Conditions 4 or 5.Rev to Tech Specs Encl ML20133N4141985-10-23023 October 1985 Safety Evaluation Re Util 831107 & 850828 Responses to Generic Ltr 83-28,Items 3.1.2 & 3.2.1 & 850701 Request for Addl Info.Responses Re Vendor & Engineering Test Guidance & Testing Requirements After Maint Acceptable ML20134P5211985-08-28028 August 1985 Safety Evaluation Approving Use of ASME Code Case N-411 for Damping Curves ML20128M2911985-07-16016 July 1985 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28, Salem ATWS Event, Items 3.1.3 & 3.2.3 Re post-maint Testing 1999-08-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied BSEP-99-0005, Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0231, Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0218, Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with BSEP-98-0210, Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired1998-10-30030 October 1998 Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 BSEP-98-0202, Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151Y6211998-09-14014 September 1998 BSEP Rept Describing Changes,Tests & Experiments, for Bsep,Units 1 & 2 ML20151Y6371998-09-14014 September 1998 Changes to QA Program, for Bsep,Units 1 & 2 BSEP-98-0185, Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151T5021998-08-0505 August 1998 Project Implementation Plan, Ngg Yr 2000 Readiness Program, Rev 2 BSEP-98-0164, Monthly Operating Repts for July 1998 for BSEP Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for BSEP Units 1 & 2 ML20236T1961998-07-0101 July 1998 Rev 1 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr ML20236T1921998-07-0101 July 1998 Rev 1 to 1B21-0537, Brunswick Unit 1,Cycle 12 Colr BSEP-98-0142, Monthly Operating Repts for June 1998 for BSEP Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for BSEP Units 1 & 2 ML20236T1971998-06-30030 June 1998 Rev 2 to 24A5412, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13 ML20249B9691998-06-11011 June 1998 Rev 1 to VC44.F02, Brunswick Steam Electric Plant,Units 1 & 2,ECCS Suction Strainers Replacement Project,Nrc Bulletin 96-003 Final Rept BSEP-98-0129, Monthly Operating Repts for May 1998 for Bsep,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Bsep,Units 1 & 2 ML20151S9041998-05-31031 May 1998 Revised Pages to Monthly Operating Rept for May 1998 for Brunswick Steam Electric Plant,Unit 1 BSEP-98-0104, Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 2 ML20151S8991998-04-30030 April 1998 Revised Pages to Monthly Operating Rept for Apr 1998 for Brunswick Steam Electric Plant,Unit 1 ML20247N7501998-04-30030 April 1998 Rev 0 to BSEP Unit 1,Cycle 12 Colr ML20247N7721998-04-30030 April 1998 Rev 0 to J1103244SRLR, Supplemental Reload Licensing Rept for BSEP Unit 1,Reload 11,Cycle 12 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) BSEP-98-0080, Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 2 ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 1999-09-30
[Table view] |
Text
pur4 9 g k UNITED STATES s* Ijt NUCLEAR RESULATORY COMMISSION WASHINGTON, D.C. Me66 0001 l l
+9***** ,
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON USE OF ASME CODE CASE N-535 '
RELIEF REQUEST SERIAL NO. BSEP 97-0459 BRUNSWICK STEAM Ft FCTRIC PLANT UNIT NOS.1 AND 2 CAROLINA POWER & LIGHT COMPANY QQCKET NOS: 50-325 AND 50-324
1.0 INTRODUCTION
l The Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Unit Nos 1 and 2, state that the inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 components shall be performed in accordance with '
Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). 10 CFR 50.55a(a)(3) states that attematives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed attematives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of the ASME Code,Section XI, incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ASME Code,Section XI, for Brunswick Units 1 and 2, during the second 10-year inservice inspection (ISI) interval is the 1980 Edition through the Winter 1981 Addenda. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
Pursuant to 10 CFR 50.55a(a)(3), by [[letter::BSEP-97-0459, Requests Approval to Use Alternative Requirements for ISI Delineated in ASME Section XI Code Case N-535.Alternative Is Needed to Extend Third Period of Second ten-yr ISI Interval to Coincide W/End of Bsep,Unit 1,refueling Outage 11|letter dated November 17,1997]], Carolina Power & Light Company (CP&L or the licensee) requested approval for implementing the attemative rules of ASME Section XI Code Cas N-SSS, "Altemative Requirements for Inservice inspection Enclosure 9805040160 990424 PDR ADOCK 05000324 P PDR
l l . .
Intervals,Section XI, Division 1," to be applied to the ISI program for Brunswick Units 1 and 2. l For Brunswick Unit 1, Code Case N-535 will be applied to the third period of the second 10-year i l inspection interval. The staff's review and evaluation of the licensee's request and supporting i information is noted below.
l 2.0 DISCUSSION l Code Case N-535. Altamative Reauirements for Inservice Insnardian intervals 1 l
Component identification ASME Code Class 1, 2, and 3 components and their supports for Brunswick Units 1 and 2. l Code Requirement The ASME Code,Section XI,1980 Edition with Winter 1981 Addenda, Paragraph l IWB-2412(b) states; "The inspection period specified in (a) above may be decreased or l extended by as much as 1 year to enable an inspection to coincide with a plam outage, within j the limitations of IWA-2400(c)."
The Paragraph IWA-2400(c) states; "Each inspection interval may be decreased or extended
' (but not cumulatively) by as much as 1 year. For power units that are out of service l continuously for 6 months or more, the inspection interval during which the outage occurred 1 may be extended for a period equivalent to the outage."
l- Licensee's Basis for Relief l
l The second 10-year inservice inspection interval for Brunswick Units 1 and 2, ends May 10,1998. The Unit 1 refueling outage is scheduled to begin on April 25,1998. The short time period between the start of the refueling outage and end of the inspection interval is not sufficient to complete the remaining second 10-year interval Code examinations. Therefore, the third inspection period of the inspection interval needs to be extended to coincide with the end of Brunswick Unit 1 Refueling Outage 11.
The ASME Code,Section XI allows extending the inspection interval by as much as 1 year to enable an inspection to coincide with a plant outage. However, extending the end date of the second 10-year interval extends the start date of the third 10-year interval. The altamat've r
requirements of ASME Code Case N-535 have been reviewed by CP&L, and it was determined that the use of this Code Case would provide an acceptable level of quality and safety.
Proposed Altemative CP&L proposes to extend the third inspection period of the second 10-year inspection interval for Brunswick Units 1 and 2 (without affecting the start date of the successive interval) as allowed by ASME Code Case N-535. The attemative provisions of Code Case N-535 allow CP&L to extend the third period of the second 10-year inspection inteNai to coincide with the end of BSEP Unit No,1 Refueling Outage 11. Therefore, approval to use Code Case N-535 is I
i
being requested for the remainder of the second 10-year inspection interval. Approval for Unit q
No. 2 is requested solely to permit use of a common interval closure date in plant procedures and documentation for the second 10-year inspection interval. There are no scheduled Unit 2 inspection activities that require use of Code Case N-535.
3.0 EVALUATION 1
The staff has reviewed the attemative requirements for inservice inspection intervals as provided in Code Case N-535, and has determined that the implementation of the Code Case neither require any change to the start and the end date, nor the inservice inspection program for the successive interval. This, therefore, will maintain the inspection intervals more closely to the original pattem of intervals than that of the ASME Code,Section XI. However, Code Case N-535 has provisions for reducing or extending an inspection interval by as much as 1 year as does the ASME Code Further, the Code Case specifies that an examination performed to satisfy requirements of either the extended interval or the successive interval shall not be credited to both intervals. Hence, the extent of examination coverage for each component i remains unchanged for a given inspection interval. Moreover, the implementation of the Code Case would require that the inspection interval during which an examination is performed, must be identified on examination records. Thus, the use of the Code Case requires explicit documentation of changes to scope of examination during an inservice inspection interval. The staff has, therefore, determined that the use of Code Case N-535 on Unit 1 would provide an acceptable level of quality and safety equivalent to the applicable ASME Code,Section XI. We do not authorize the use of Code Case N-535 at Unit 2, as there are no scheduled Unit 2 inspection activities that require the use of Code Case N-535.
4.0 CONCLUSION
Based on the above discussions, the staff concludes that the licensee's proposed use of Code Case N-535 Unit 1 would provide an acceptable level of quality and safety equivalent to the provisions of the ASME Code,Section XI,1980 Edition including the Winter 1981 Addendum.
Therefore, the licerisee's proposed attemative to use Code Case N-535 at Brunswick Unit 1 during the second 10-year interval, is authorized pursuant to 10 CFR 50.55a(c)(3)(i). The licensee is authorized to use Code Case N-535 until such time as the Code Case is included in a future revision of Regulatory Guide 1.147. At that time the licensee should follow all provisions and any limitations that may be described in the Regulatory Guide 1.147 conceming the use of Code Case N-535.
Principal Contributor: P. Patnaik, ECGB Date: April 24, 1998 e