SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also EnclML18152B538 |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML20236R2111998-07-15015 July 1998 SER Related to Request for Revised Exemption from 10CFR70.24(a) for Surry Power Station,Units 1 & 2 ML20249B8191998-06-19019 June 1998 Safety Evaluation Supporting Amends 215 & 215 to Licenses DPR-32 & DPR-37,respectively ML20249B8261998-06-19019 June 1998 Safety Evaluation Supporting Amends 214 & 214 to Licenses DPR-32 & DPR-37,respectively ML20248M0911998-06-11011 June 1998 Safety Evaluation Supporting Amends 213 & 213 to Licenses DPR-32 & DPR-37,respectively ML18152B8011998-05-0404 May 1998 Safety Evaluation Granting Third 10-year Interval Inservice Insp Plan Request for Relief SR-19 for Surry Power Station, Unit 1 ML18152B7881998-04-28028 April 1998 SER Accepting Request for Relief from ASME Code Requirements - Deferral of Repair to RHR Sys Piping ML18153A3011998-04-20020 April 1998 Safety Evaluation Denying Licensee Assessment of Reactor Vessel Structural Integrity ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A3841997-12-0303 December 1997 Safety Evaluation Accepting Licensee Structural Integrity & Operability Assessments ML20202B8751997-11-24024 November 1997 Safety Evaluation Denying Licensee Request for Exemption from Section III.G.2.f of App R to 10CFR50.Staff Concluded That Use of Combustible Radiant Energy Heat Shields Inside Containment at Surry & North Anna Unacceptable ML18153A4011997-11-24024 November 1997 Safety Evaluation Accepting Licensee Proposed Alternative to Perform Visual Exam of Reactor Vessel Closure Head Nuts in Lieu of Surface Exam ML18153A4471997-10-0101 October 1997 Safety Evaluation Re Relief from Implementation of 10CFR50.55a Requirements for Surry Power Station,Units 1 & 2 & North Anna Power Station,Units 1 & 2 ML20217P0951997-08-21021 August 1997 Safety Evaluation Accepting Licensee ,As Suppl by 970324 Request for Exemption from Requirements of 10CFR70.24(a) Re Criticality Monitors as Pertaining to Unirradiated Fuel & Other Forms of Special Nuclear Matls ML20149D8361997-07-15015 July 1997 Safety Evaluation Supporting Amends 211 & 211 to Licenses DPR-32 & DPR-37,respectively ML18153A1271997-04-11011 April 1997 Safety Evaluation Accepting Third 10-yr ISI Interval Requests for Relief Sr-14 - SR-17 for Plant,Unit 2 ML18153A0511996-08-30030 August 1996 SE Granting Third 10-yr Interval ISI Program Plan Requests for Relief SR-009 Through SR-017,subj to Requirement for Relief Request SR-014 ML20117M4281996-06-0707 June 1996 Safety Evaluation Supporting Amends 210 & 210 to Licenses DPR-32 & DPR-37 ML20108B3661996-04-29029 April 1996 Safety Evaluation Supporting Amends 209 & 209 to Licenses DPR-32 & DPR-37,respectively ML20107K0081996-04-18018 April 1996 Safety Evaluation Supporting Amends 208 & 208 to Licenses DPR-32 & DPR-37,respectively ML18153A6091996-04-16016 April 1996 Safety Evaluation Authorizing Third 10-yr Interval ISI Program Plan Requests for Relief to Use Code Cases N-522 & N-535 at Plant,Per 10CFR50.55a(a)(3)(i) ML20099M0071995-12-28028 December 1995 Safety Evaluation Supporting Amends 207 & 207 to Licenses DPR-32 & DPR-37,respectively ML18153A5631995-12-19019 December 1995 SER Recommending That Relief Requests SR-22 Through SR-26, Be Granted,Per 10CFR50.55a(g)(6)(i) ML18153A5541995-12-13013 December 1995 Safety Evaluation Accepting Change to Emergency Plan Augmentation Goals of Selected Responders from 30 Minutes to 45 Minutes for Plant ML20092G7381995-09-14014 September 1995 Safety Evaluation Supporting Amends 205 & 205 to Licenses DPR-32 & DPR-37 ML20092A3131995-09-0101 September 1995 Safety Evaluation Supporting Amend 204 to Licenses DPR-32 & DPR-37 ML18153A7511995-08-30030 August 1995 Safety Evaluation Granting Third 10-yr Interval Inservice Insp Program Plan,Rev 0 & Associated Requests for Relief ML20087B5731995-08-0303 August 1995 Safety Evaluation Supporting Amends 203 & 203 to Licenses DPR-32 & DPR-37,respectively ML20087A1791995-07-27027 July 1995 Safety Evaluation Supporting Amends 202 & 202 to Licenses DPR-32 & DPR-37,respectively ML18153A7261995-07-19019 July 1995 Safety Evaluation Re Third 10-yr Interval Inservice Insp Program Update & Associated Requests for Relief ML18153A7101995-07-19019 July 1995 Safety Evaluation Granting Requests for Relief RR-2,RR-6, RR-7,RR-8,RR-11,SR-002,SR-003,SR-004 & SR-006 ML20086J7611995-07-11011 July 1995 Safety Evaluation Supporting Amends 201 & 201 to Licenses DPR-32 & DPR-37,respectively ML18153A6951995-07-0606 July 1995 SER Denying Proposed Revisions to Decrease Effectiveness of Currently Approved Emergency Plan for Each Site ML20086E3221995-06-29029 June 1995 Safety Evaluation Supporting Amends 200 & 200 to Licenses DPR-32 & DPR-37,respectively ML18153A8511995-06-0808 June 1995 Safety Evaluation Granting Third Interval Inservice Insp Program Relief Requests from ASME Code Section XI for Plant, Unit 1 & 2 ML20091R3121995-05-31031 May 1995 Safety Evaluation Supporting Amend 199 to Licenses DPR-32 & DPR-37,respectively 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 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 05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed1999-10-0101 October 1999
- on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With ML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With1999-08-27027 August 1999
- on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed1999-08-27027 August 1999
- on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp 05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms1999-08-13013 August 1999
- on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP1999-07-30030 July 1999
- on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With1999-05-18018 May 1999
- on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With1999-04-28028 April 1999
- on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations 05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip1999-03-31031 March 1999
- on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 9902121999-03-29029 March 1999
- on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr1999-03-19019 March 1999
- on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements 05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable1999-01-21021 January 1999
- on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively 05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition1998-12-16016 December 1998
- on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With1998-12-0101 December 1998
- on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2 05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status1998-07-31031 July 1998
- on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
1999-09-30
[Table view] |
Text
e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE THIRD 10-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF
1.0 INTRODUCTION
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT 1 DOCKET NUMBER: 50-280 lnservice inspection 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 (B&PV) Code and applicable addenda as required by 1 O CFR 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to Title 1 O of the Code of Federal Regulations (1 O CFR) Section 50.55a(g)(6)(i). Section 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives 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 1 O 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 lnservice 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 Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the Surry Power Station, Unit 1 third 10-year inservice inspection (ISi) interval is the 1989 edition of Section XI of the ASME Boiler and Pressure Vessel Code.
By letter dated July 6, 1998, the licensee proposed alternatives to the Code contained in the Request for Relief for Surry Power Station, Unit 1.
Enclosure r---,;9;..;9;.,;:o;:;;2.:;1-;,e~o-;;;3~3a~9~9;;;-:o:.:-::2::-1=-6=----~---
1 PDR ADOCK 05000280 G
. PDR
The staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has evaluated the information provided by the licensee in support of the licensee-proposed alternative contained in its Request for Relief for Surry Power Station, Unit 1. Based on the results of the review, the staff adopts the contractor's conclusions and recommendations presented in the Technical Letter Report attached to this Safety Evaluation.
Request for Relief: This request for relief involves the use of Code Case N-498-1, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 SystemsSection XI, Division 1.
Section IWA-5000 requires pressure-retaining components within each system boundary to undergo system hydrostatic tests for Class 1, 2, and 3 systems under VT-2 visual examination in accordance with IWA-5240 to detect leakages. In accordance with 10 CFR 50.55a(a)(3), the licensee proposes to use Code Case N-498-1, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 SystemsSection XI, Division.1. Code Case N-498-1, in part, provides that for Class 1, 2, and 3 systems, prior to performing the VT-2 visual examination, the system shall be pressurized to nominal operating pressure for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated systems and 10 minutes for noninsulated systems, while maintaining nominal operating pressure during performance of the VT-2 examination.
Code Case N-498 is approved for general use in Regulatory Guide 1.14 7, Revision 11, for Class 1 and 2 systems. Code Case N-498-1 is the revision of Code Case N-498 to include requirements for Class 3 systems that are identical to the Code Case N-498 requirements for Class 2 components for Class 1 and 2 systems. In addition, Class 3 systems will receive inspections commensurate with the function and expected failure mechanisms. Thus, the proposed use of Code Case N-498-1 for Class 1, 2, and 3 systems will provide an acceptable level of quality and safety by providing an adequate means to detect leakage.
3.0 CONCLUSION
The staff evaluated the July 6, 1998, submittal and concludes that the licensee's proposed alternative will provide an acceptable level of quality and safety. Therefore, the licensee's proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the current interval or
0 e until such time as the revised Code Case has been accepted for general use within Regulatory Guide 1.14 7. At that time, if the licensee intends to continue to implement this Code Case, the licensee is to follow all provisions in Code Case N-498-1 with limitations issued in Regulatory Guide 1.147, if any.
Attachment:
Technical Letter Report Principal Contributor: G. Hatchett Date:
February 16, 1999
e TECHNICAL LETTER REPORT ON THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROPOSED ALTERNATIVE N-498-1
- 1.
INTRODUCTION FOR
- VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT 1 DOCKET NUMBER: 50-280 By letter dated July 6, 1998, the licensee, Virginia Electric and Power Company, submitted a proposed alternative to the requirements of the ASME Code,Section XI, for the Surry Power Station, Unit 1, third 10-year inservice inspection (ISi) interval. The Idaho National Engineering and Environmental Laboratory (INEEL) staff's evaluation of the subject request for relief is in the following section.
- 2.
EVALUATION The information provided by Virginia Electric and Power Company in support of the proposed alternative from Code requirements has been evaluated and the basis for disposition is documented below. The Code of record for the Surry Power Station, Unit 1, third 10-year ISi interval, which began October 14, 1993, is the 1989 Edition of Section XI of the ASME Boiler and Pressure Vessel Code.
Proposed Alternative N-498-1, Use of Code Case N-498-1, Alternate Rules for 1q Year Hydrostatic Pressure Testing for Class 1. 2. and 3 Systems.Section XI. Division 1 Code Requirement: Table IWB-2500-1, Examination Category B-P, Table IWC-2500-1, Examination Category C-H, and Table IWD-2500-1, Examination Categories D-A, D-B and D-C, require system hydrostatic testing of pressure-retaining components in accordance with IWA-5000 once each 10-year interval.
Licensee's Proposed Alternative: Pursuant to 10 CFR 50.55a(a)(3), the licensee has requested authorization to use Code Case N-498-1, Alternate Rules for 10-Year Hydrostatic Pressure Testing for Class 1, 2, and 3 Systems,Section XI, Division 1.
Licensee's Basis for Requesting Relief (as stated):
"Hydrostatic tests are historically difficult to perform. They frequently require extending the duration of the test while non-safety related issues, such as maintenance boundary valve isolation problems, are resolved. This increases the cumulative exposure of test personnel and extends the system tag-out duration. By taking advantage of Code Case N-498-1, increased testing flexibility is provided by permitting testing to be performed at nominal operating pressure. This significantly reduces the number of test blocks, system tag-outs, and corresponding boundary valves required to complete testing. This flexibility is accomplished while maintaining an acceptable level of quality and safety as determined by the ASME Code consensus process.
Attachment
\\;
- Evaluation: The Code requires a system hydrostatic test once per interval in accordance with the requirements of IWA-5000 for Class 1, 2, and 3 pressure-retaining systems. In lieu of the Code-required hydrostatic testing, the licensee has requested authorization to use Code Case N-498-1, Alternative Rules for 10-YearSystem Hydrostatic Testing for Class 1, 2, and 3 Systems, dated May 11, 1994.
The system hydrostatic test, as stipulated in Section XI, is not a test of the structural integrity of the system but rather an enhanced leakage test. 1 Hydrostatic testing only subjects the piping components to a small increase in pressure over the design pressure; therefore, piping dead weight, thermal expansion, and seismic loads present far greater challenges to the structural integrity of a system. Consequently, the Section XI hydrostatic pressure test is primarily regarded as a means to enhance leak detection during the examination of components under pressure, rather than as a method to determine the structural integrity of the components. In addition, the industry experience indicates that leaks are not being discovered as a result of hydrostatic test pressures causing a preexisting flaw to propagate through the wall. In most cases leaks are being found when the system is at normal operating pressure.
Code Case N-498, Alternative Rules for 10-Year System Hydrostatic Testing for Class 1 and 2 Systems, was previously approved for general use on Class 1 and 2 systems in Regulatory Guide 1.147, Rev. 9. For Class 3 systems, Revision N-498-1 specifies requirements identical to those for Class 2 components (for Class 1 and 2 systems, the alternative requirements in N-498-1 are unchanged from N-498). In lieu of 10-year hydrostatic pressure testing at or near the end of the 10-year interval, Code Case N;..498-1 requires a VT-2 visual examination at nominal operating pressure and temperature in conjunction with a system leakage test performed in accordance with paragraph IWA-5000 of the 1992 Edition of Section XI.
Class 3 systems do not normally receive the amount. and/or type of nondestructive examinations that Class 1 and 2 systems receive. While Class 1 and 2 system failures are 1 - S. H. Bush and R. R. Maccary, "Development of In-Service Inspection Safety Philosophy for U.S.A. Nuclear Power Plants," ASME, 1971
e
- relatively uncommon, Class 3.leaks occur more frequently and are caused by different failure mechanisms. Based on a review of Class 3 system failures requiring repair during the last 5 years,2 the most common causes of failure are erosion-corrosion (EC),
microbiologically-induced corrosion (MIC), and general corrosion. In general, licensees have implemented programs for the prevention, detection, and evaluation of EC and MIC; therefore, Class 3 systems receive inspection commensurate with their functions and expected failure mechanisms.
Considering that Code Case N-498 was found to be an acceptable alternative for Class 1 and 2 systems, and that Class 3 systems receive inspections commensurate with their function antj expected failure mechanisms, the licensee's proposed alternative, to use Code Case N-498-1, should provide an acceptable level of quality and safety.
- 3.
CONCLUSION The INEEL staff evaluated the July 6, 1998, submittal and concludes that the licensee's proposed alternative provides an acceptable level of quality and safety. Therefore, it is recommended that the licensee's proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of Code Case N-498-1 should be authorized for the current interval or until such time as the Code Case is pubHshed in a future revision of Regulatory Guide 1.147. At that time, if the licensee intends to continue to implement Code Case N-498-1, the licensee should follow all provisions in the Code Case with limitations issued in Regulatory Guide 1.147, if any.
2 - Documented in Licensee Event Reports and the Nuclear Plant Reliability Data System databases.