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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23061A0122023-05-0909 May 2023 Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 ML23082A1362023-03-23023 March 2023 License Amendment Request NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure Response to Request for Additional Information ML22339A1372022-12-0101 December 2022 License Amendment Request for NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure Supplemental Information ML22322A1822022-11-18018 November 2022 Proposed Emergency Plan Revision - Relocation of the Technical Support Center ML22312A5502022-11-0707 November 2022 Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML22227A1772022-08-15015 August 2022 License Amendment Request - Proposed Technical Specifications Change for New Fuel and Spent Fuel Storage Areas ML22172A1342022-06-20020 June 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability ML22171A0132022-06-20020 June 2022 Units, Units 1 and 2 - Proposed License Amendment Request Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML22146A0272022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant. ML22131A3102022-05-11011 May 2022 Proposed License Amendment Request Addition of Alternate Control Rod Position Monitoring Requirements ML22131A3512022-05-11011 May 2022 License Amendment Request for Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML22104A1252022-04-14014 April 2022 License Amendment Request for NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML21334A1692021-11-29029 November 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Additional Tank and Replacement of Containment Buffer Supplemental Information ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML20338A5422020-12-0303 December 2020 Proposed License Amendment Request, Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping ML20274A3292020-09-30030 September 2020 Proposed License Amendment Request: Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A, Revision 1 ML20105A2232020-04-14014 April 2020 Proposed License Amendment Request: One-Time Deferral of Surry Unit 2 Steam Generator B Inspection ML19343A0192019-12-0606 December 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19309D1962019-10-30030 October 2019 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) ML19309D1992019-10-30030 October 2019 Proposed License Amendment Request: Temporary, One Time 14-Day Allowed Outage Time for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F ML19042A1372019-01-29029 January 2019 Submittal of Supplement to Subsequent License Renewal Operating Licenses Application for Sufficiency Review Change Notice 1 ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18025B4852018-01-16016 January 2018 Isfsis, Surry, Units 1 and 2, and ISFSIs - Submittal of Proposed Consolidated Emergency Operations Facility ML18025B4882018-01-16016 January 2018 Attachments 1 to 4: Proposed Consolidated Emergency Operations Facility ML18025B4912018-01-16016 January 2018 Attachments 5 and 6: North Anna - Proposed Changed to Emergency Plan Pages and Marked-Up SPS Emergency Plan Page Changes ML18025B4932018-01-16016 January 2018 Attachments 7 & 8: Surry - Proposed Changed SPS Emergency Plan Pages and Offsite Response Agency Letters of Concurrence ML17317A4642017-11-0707 November 2017 Proposed License Amendment Request, Temporary, One Time 21-Day Allowed Outage Time for Replacement of Reserve Station Service Transformer C and Associated Cabling ML17150A3022017-05-23023 May 2017 Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01 ML17026A1742017-01-20020 January 2017 Surrey Power Station, Units 1 and 2 - Proposed License Amendment Request for Revision to Technical Specifications Residual Heat Removal Requirements and Component Cooling System Requirements & Addition of Surveillance Requirement ML16146A5402016-05-18018 May 2016 Proposed License Amendment Request Extension of TS 3.14 Service Water Flow Path Allowed Outage Times and Deletion of Expired Temporary Service Water Jumper Requirements ML14160A6072014-06-0303 June 2014 Proposed License Amendment Request Clarification of Reactor Coolant System Heatup and Cooldown Limitations Technical Specifications ML14112A0732014-04-11011 April 2014 Proposed License Amendment Request Relocation of Augmented Inspection Requirements from TS 4.2 and TS 4.15 to Technical Requirements Manual ML14079A0832014-03-13013 March 2014 Proposed License Amendment Request Regarding Relocation of Snubber Surveillance Requirements from Technical Specification 4.17 to Snubber Program - Correction ML13231A1702013-09-23023 September 2013 Issuance of Amendments Regarding Use of a Temporary Jumper for Providing Service Water ML13248A1072013-09-0303 September 2013 Proposed License Amendment Request Regarding Temporary Service Water Jumper to the Component Cooling Heat Exchangers Correction of Identified Discrepancy ML13232A0422013-08-12012 August 2013 Proposed License Amendment Request Permanent Fifteen-Year Type a Test Interval ML13179A0142013-06-26026 June 2013 Proposed License Amendment Request Addition of an Analytical Methodology to Core Operating Limits Reports and an Increase to Minimum Temperature for Criticality ML13179A0152013-05-31031 May 2013 Units I and 2, Qualification of the ABB-NV and Wlop CHF Correlations in the Dominion VIPRE-D Computer Code ML13137A3132013-05-13013 May 2013 Proposed License Amendment Request Regarding Relocation of Snubber Surveillance Requirements from Technical Specification 4.17 to Snubber Program ML12283A0692012-09-27027 September 2012 ISFSIs and Surry, Units 1 and 2 and ISFSIs Proposed Emergency Action Level Revisions ML12279A2822012-09-26026 September 2012 Proposed License Amendment Request Regarding Temporary Service Water Jumper to the Component Cooling Heat Exchangers 2024-09-03
[Table view] Category:Technical Specification
MONTHYEARML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML22322A1982022-11-18018 November 2022 Proposed License Amendment Request Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications Marked-up Technical Specifications Basis Page ML22278A1692022-10-0505 October 2022 Annual Submittal of Technical Bases Changes Pursuant to Technical Specification 6.4.J ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22131A3102022-05-11011 May 2022 Proposed License Amendment Request Addition of Alternate Control Rod Position Monitoring Requirements ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21279A2892021-10-0404 October 2021 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML20304A1592020-10-12012 October 2020 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML19309D1962019-10-30030 October 2019 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) ML19297D1472019-10-14014 October 2019 Annual Submittal of Technical Specifications (TS) Bases Changes Pursuant to TS 6.4.J ML19269B7752019-09-19019 September 2019 Proposed License Amendment Request: Update of Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures for Subsequent License Renewal ML18289A3962018-10-11011 October 2018 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML17317A4642017-11-0707 November 2017 Proposed License Amendment Request, Temporary, One Time 21-Day Allowed Outage Time for Replacement of Reserve Station Service Transformer C and Associated Cabling ML17293A0282017-10-16016 October 2017 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML17150A3022017-05-23023 May 2017 Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01 ML16134A0692016-05-10010 May 2016 Proposed License Amendment Request for Expansion of Primary Grade Water Lockout Requirements in TS 3.2.E ML15293A4962015-10-0707 October 2015 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 6.4.J ML13280A3112013-09-30030 September 2013 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML11297A1192011-10-13013 October 2011 Submittal of Annual Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML1029904232010-10-13013 October 2010 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML1009003912010-03-30030 March 2010 Proposed License Amendment Request Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirement to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML0928003582009-09-30030 September 2009 Proposed License Amendment Request One-time Alternate Repair Criteria for Steam Generator Tube Inspection/Repair for Units 1 & 2 ML0921504642009-07-28028 July 2009 Proposed License Amendment Request Permanent Alternate Repair Criteria for Steam Generator Tube Repair ML0907005522009-02-17017 February 2009 Page Correction for Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0828905292008-10-0909 October 2008 Proposed License Amendment Request, Removal of Main Control Room Bottled Air System Requirements ML0829004942008-10-0202 October 2008 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0728509092007-10-11011 October 2007 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0726811712007-09-25025 September 2007 Proposed Technical Specifications Change Supplement Re Operable Definition Modification for Air Handling Units While in Temporary 45-Day Allowed Outage Times ML0726810962007-09-19019 September 2007 Proposed Technical Specifications Change Revised Setting Limits and Overtemperature T/Overpower at T Time Constants. ML0709600372007-04-0505 April 2007 Proposed Technical Specifications Change Re Temporary 45-Day and 14-Day Allowed Outage Times to Replace Main Control Room and Emergency Switchgear Room Air Conditioning System Chilled Water Piping ML0709303712007-04-0202 April 2007 Technical Specifications Pages Re Main Control Room and Emergency Switchgear Room Air Conditioning System ML0706505242007-02-26026 February 2007 Proposed Technical Specifications Change Temporary 45-Day and 14-Day Allowed Outage Times to Replace Main Control Room and Emergency Switchgear Room Air Conditioning System Chilled Water Piping ML0628301702006-10-0909 October 2006 Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0600500262006-01-0303 January 2006 Technical Specification Pages Reactor Coolant System Pressure and Temperature Limits ML0520001542005-07-15015 July 2005 TS, Amd MC5034, Relocation of Inservice Inspection and Testing Requirements ML0515902872005-05-31031 May 2005 Technical Specifications Bases Changes Revision of References for Offsite Dose Limits ML0430905782004-11-0404 November 2004 Proposed Technical Specifications Change Request Relocation of Inservice Inspection and Testing Requirements ML0426002902004-09-15015 September 2004 Proposed Technical Specifications Change Administrative Controls Changes ML0426002962004-09-15015 September 2004 Proposed Technical Specifications Change Administrative Controls Changes, Attachment 2, Mark-Up of Technical Specifications. ML0424401692004-08-30030 August 2004 Proposed Technical Changes to Extend Inspection Interval for Reactor Coolant Pump Flywheels Using Consolidated Line Item Improvement Process ML0234701352002-12-10010 December 2002 Tech Spec Pages for Amendments 232 and 232 Surveillance Frequency for the Containment Spray and Recirculation Spray Nozzles ML0231802402002-11-0505 November 2002 Proposed Technical Specification Change Deletion of Fifteen Minute Degassed Beta & Gamma Activity Test & Semiannual Dose Equivalent I-131 Analysis ML0231802422002-11-0505 November 2002 Proposed Technical Specification Change, Deletion of Monthly Analog Rod Position Test ML0207203672002-03-0808 March 2002 Technical Specification Pages, Amendments 230 & 230 for Surry, Units 1 & 2 ML0205100092002-02-0808 February 2002 Technical Specification Basis Change, Alternate Source Term Implementation ML0600402721999-08-23023 August 1999 Technical Specifications Basis Change - Delete Tables for Reactor Vessel Toughness Data ML19094A4091977-10-26026 October 1977 Technical Assistance Request - Environmental Technical Specification Changes 2024-02-19
[Table view] Category:Bases Change
MONTHYEARML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML22322A1982022-11-18018 November 2022 Proposed License Amendment Request Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications Marked-up Technical Specifications Basis Page ML22278A1692022-10-0505 October 2022 Annual Submittal of Technical Bases Changes Pursuant to Technical Specification 6.4.J ML21279A2892021-10-0404 October 2021 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML20304A1592020-10-12012 October 2020 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML19297D1472019-10-14014 October 2019 Annual Submittal of Technical Specifications (TS) Bases Changes Pursuant to TS 6.4.J ML19269B7752019-09-19019 September 2019 Proposed License Amendment Request: Update of Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures for Subsequent License Renewal ML18289A3962018-10-11011 October 2018 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML17317A4642017-11-0707 November 2017 Proposed License Amendment Request, Temporary, One Time 21-Day Allowed Outage Time for Replacement of Reserve Station Service Transformer C and Associated Cabling ML17293A0282017-10-16016 October 2017 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML16134A0692016-05-10010 May 2016 Proposed License Amendment Request for Expansion of Primary Grade Water Lockout Requirements in TS 3.2.E ML15293A4962015-10-0707 October 2015 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 6.4.J ML13280A3112013-09-30030 September 2013 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML11297A1192011-10-13013 October 2011 Submittal of Annual Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML1029904232010-10-13013 October 2010 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0928003582009-09-30030 September 2009 Proposed License Amendment Request One-time Alternate Repair Criteria for Steam Generator Tube Inspection/Repair for Units 1 & 2 ML0907005522009-02-17017 February 2009 Page Correction for Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0829004942008-10-0202 October 2008 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0728509092007-10-11011 October 2007 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0628301702006-10-0909 October 2006 Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML0515902872005-05-31031 May 2005 Technical Specifications Bases Changes Revision of References for Offsite Dose Limits ML0430905782004-11-0404 November 2004 Proposed Technical Specifications Change Request Relocation of Inservice Inspection and Testing Requirements ML0424401692004-08-30030 August 2004 Proposed Technical Changes to Extend Inspection Interval for Reactor Coolant Pump Flywheels Using Consolidated Line Item Improvement Process ML0205100092002-02-0808 February 2002 Technical Specification Basis Change, Alternate Source Term Implementation ML0600402721999-08-23023 August 1999 Technical Specifications Basis Change - Delete Tables for Reactor Vessel Toughness Data ML19094A4091977-10-26026 October 1977 Technical Assistance Request - Environmental Technical Specification Changes ML19094A2261972-03-17017 March 1972 Technical Specifications 2024-10-07
[Table view] |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMoND, VIRGINIA 23261 August 23, 1999 U. S. Nuclear Regulatory Commission Serial No.99-404 Attention: Document Control Desk SPS-LIC/CGL, KLT RO Washington, D.C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 TECHNICAL SPECIFICATIONS BASIS CHANGE DELETE TABLES FOR REACTOR VESSEL TOUGHNESS DATA Virginia Electric and Power Company has approved a revision to the Basis for Technical Specification (TS) 3.11.B, "Heatup and Cooldown". This change deletes reactor vessel toughness data that is duplicated in the UFSAR. In addition to deletion of the redundant information, a reference to the applicable UFSAR section is included in the TS Basis. The TS Basis revision is provided for your information.
A UFSAR change associated with this TS Basis revision is currently being processed and will be included in the next scheduled UFSAR update. The UFSAR change updates the reactor vessel toughness data consistent with information previously provided to the NRC in a February 24, 1999 letter (Serial No.99-034).
The TS Basis revision has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that this change does not involve an unreviewed safety question as defined in 10 CFR 50.59. A discussion of the TS Basis change, the mark-up of the TS Basis change, and the revised TS Basis are provided in Attachments 1, 2, and 3, respectively.
Should you have any questions or require additional information, please contact us.
Very truly yours, David A. Christian Vice President - Nuclear Operations
Attachments:
- 1. Discussion of Change
- 2. Mark-up of Technical Specification Basis
- 3. Revised Technical Specification Basis Commitments made in this letter:
- 1. A UFSAR change associated with the revised reactor vessel toughness data provided to the NRC in response to Generic Letter 92-01, Supplement 1, Revision 1, is currently being processed, and will be included in the next scheduled UFSAR update.
cc: U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station Commissioner Department of Radiological Health Room 104A 1500 East Main Street Richmond, VA 23219
COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by David A. Christian, who is Vice President - Nuclear Operations, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this3 day of f1 19 q9.
My Commission Expires: A 31 /J2Pf .Ua (SEAL)
ATTACHMENT I DISCUSSION OF CHANGE VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2
DISCUSSION OF CHANGE INTRODUCTION Virginia Electric and Power Company (Virginia Power) is revising the Surry Technical Specification (TS) 3.1.B Basis to delete Tables 3.1-1 and 3.1-2 and instead reference identical information that is contained in the Surry Updated Final Safety Analysis Report (UFSAR). The revised TS Basis is necessary to prevent potential consistency concerns between the Surry Technical Specifications and the UFSAR.
BACKGROUND TS 3.11.B Basis Tables 3.1-1 and 3.1-2 of the Surry Technical Specifications currently contain information regarding Reactor Vessel Toughness Data that is identical to the information included in Surry UFSAR Tables 4.1-14 and 4.1-15. The data in these tables require update to reflect the latest information that was submitted to the NRC in a letter dated February 24,1999. Because the information is identical in both documents, and because it is referenced only by the Basis for Technical Specification (TS) 3.1.B, the Basis requires revision to delete the two tables and instead reference the updated tables in the UFSAR.
Licensing/Design Basis The Virginia Power response to Generic Letter 92-01, Revision 1, is documented in BAW-2222, 'Reactor Vessel Working Group Response to Closure Letters to NRC Generic Letter 92-01, Revision I," dated June 1994. A resultant TS change request was submitted to the NRC in a letter dated June 8, 1995 (Serial No.95-197) that included modifications to TS Tables 3.1-1 and 3.1-2 and was approved by the NRC in a letter dated December 28, 1995 (TS Amendments 207). Since the publication of BAW-2222 in June 1994, Framatome Technologies has published BAW-2313, Revision 1, 'B&WOG Reactor Vessel Working Group Reactor Vessel Materials and Surveillance Data Information, Volumes I and 2," dated December, 1998. After an evaluation of data contained in BAW-2313, Revision 1, Virginia Power submitted a supplemental letter to the NRC dated February 24, 1999, to incorporate the most recent reactor vessel materials information into our docketed response to Generic Letter 92-01, Revision 1, Supplement 1. This submittal included more recent values of "mean for the heat" chemical composition for Surry Units 1 and 2 reactor vessel beltline materials, which will be reflected in UFSAR Table 4.1-14 and Table 4.1-15. Therefore, deletion of Tables 3.1-1 and 3.1-2 from the TS 3.1.B Basis will eliminate inconsistencies between the two documents and simplify any future revisions to the data.
Page 1 of 3
SPECIFIC CHANGES As noted above, the revised TS Basis for TS 3.1.B deletes two tables that are redundant to existing UFSAR tables. The specific revisions are as follows:
- In the Basis of TS 3.1.B, under item 6), reference to Tables 3.1-1 and 3.1-2 is changed to, "UFSAR Section 4.1."
- At the end of the Basis for TS 3.11.B, a reference table is added to reflect UFSAR Section 4.1.
- TS Basis 3.1 Tables 3.1-1 and 3.1-2 are deleted.
SAFETY SIGNIFICANCE The revision to the Surry Technical Specification 3.11.B Basis deletes two tables that are redundant to existing UFSAR tables. Reference to the TS Basis tables that are being deleted is changed to reference the UFSAR instead. Deletion of the redundant information eliminates the possibility that the two sets of information could be updated inconsistently. The information will continue to be controlled and maintained up to date in the UFSAR, and any future changes to the UFSAR tables will be reviewed in accordance with the requirements of 10 CFR 50.59. Consequently, no change to the licensing basis results from this revision. There is no safety significance associated with this revised TS Basis, since it does not involve any plant modifications or changes in system operation, is consistent with the Surry licensing and design bases, and does not affect the existing accident analyses, which remain bounding. Furthermore, no change to the TS limiting conditions for operation is required.
Page 2 of 3
REFERENCES
- 1. BAW-2222, "Reactor Vessel Working Group Response to Closure Letters to NRC Generic Letter 92-01, Revision 1," dated June 1994.
- 2. Letter from J. P. O'Hanlon to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Request for Exemption - ASME Code Case N-514, Proposed Technical Specifications Change, Revised Pressure/Temperature Limits and LTOPS Setpoint," dated June 8, 1995 (Serial No.95-197).
- 3. Letter from B. C. Buckley (USNRC) to J. P. O'Hanlon, "Surry Units 1 and 2 -
Issuance of Amendments Re: Surry Units 1 and 2 Reactor Vessel Heatup and Cooldown Curves," dated December 28, 1995 (Serial No.96-020).
- 4. BAW-2313, Revision 1, "B&WOG Reactor Vessel Working Group Reactor Vessel Materials and Surveillance Data Information, Volumes 1 and 2," dated December 1998.
- 5. Letter from L. N. Hartz to USNRC, "Virginia Electric and Power Company, Surry Power Station Units I and 2, Supplement to Virginia Power Response to NRC Request for Additional Information (RAI) on Generic Letter 92-01 Revision 1, Supplement 1," dated February 24, 1999 (Serial No.99-034).
Page 3 of 3
ATTACHMENT 2 MARK-UP OF TECHNICAL SPECIFICATION BASIS VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2
TS 3.1-9 Heatup and cooldown limit curves are calculated using the most limiting value of the niltductility reference temperature. RTNDT, at the end of 28.8 Effective Full Power Years (EFPY) and 29.4 EFPY for Units I and 2, respectively. The most limiting value of RTNDT (228.41F) occurs at the 1/4-T, 0° azimuthal location in the Unit 1 intermediate-to-lower shell circumferential weld. The limiting RTNDT at the 114-T location in the core region is greater than the RTNDT Of the limiting unirradiated material.
This ensures that all components in the Reactor Coolant System will be operated conservatively in accordance with applicable Code requirements.
4fAP, 'SecAkonr.
The reactor vessel materials have been tested to de RTNDT; the results of thesetst; are presented in JZ "RespIns to Glesure 6ftters to NRC Gonorc Letto 02f01. R1vicsln 1.'
-dated juno, 104 94and ar roproducd in Tables 3. 1X2. and 3. 1 Reactor operation and resultant fast neutron (E greater than 1 MEV) irradiation can cause an increase in the RTNDT. Therefore, an adjusted reference temperature, based upon the copper and nickel content of the material and the fluence was calculated in accordance with the recommendations of Regulatory Guide 1.99, Revision 2 'Effects of Residual Elements on Predicted Radiation Damnage to Reactor Vessel Materials.' The heatup and cooldown limit curves of Figures 3.1-1 and 3.1-2 include predicted adjustments for this shift in RTNDT at the end of 28.8 EFPY and 29.4 EFPY for Units 1 and 2, respectively (as well as adjustments for location of the pressure sensing instrument).
Surveillance capsules will be removed in accordance with the requirements of ASTM E185-82 and 10 CFR 50, Appendix H. The surveillance specimen withdrawal schedule Is shown in the UFSAR. The heatup and cooldown curves must be recalculated when the ARTNDT determined from the surveillance capsule exceeds the calculated ARTNDT for the equivalent capsule radiation exposure, or when the service period exceeds 28.8 EFPY or 29.4 EFPY for Units I and 2, respectively, prior to a scheduled refueling outage.
Amendment Nos. 207 and 207 A.
TS 3.1-12
-t2&695 r ~ce-s (J) (4PSARI -Sec-6'on -44.1 s THIS PAGE HAS BEEN iTENTIONAY DEL D -
I Amendment Nos. A-nd-7--
TABLE 3.1-1 UNIT I REACTOR VESSEL TOUGHNESS DATA (UNIRRADIATED)(d)
NMWD(b)
UPPER SHELF HEAT OR MATERIAL Cu PA TNDT RTNJrT ENERGY MA1EML CODE NO. S9PEC. NO- LvD ibw head dome C4315-2 A53313 Cl. 1 .14 .59 0 0 75 Head flangeN FV-1894 A508 Cl. 2 .13 .64 10 Vessel flange FV-1870 A508 Cf. 2 .10 .65 10(a) 10 _ 74 Inlet nozule A508 CI. 2 .87 60(a) 64 Inlet nozzle Inlel nozzle 9-4787 9-4762 A508 Cl. 2 A508 Cl. 2
.84
.83 en(a) 60(a) 60 60 60 68 64 85 Qi FI Outlet nozzle Outlet nozzle 9-4788 .84 60(a) 60 72 Outlet nozzle 9-4825 .85 60(a) 60 68 X, Upper shel 122V109 A508 CI. 2 .74 40 40 83 fCL 3 Intermediate shell C432 A533B Cl. 1 .11 10 10 1 I5(c) f Intermediate shell 4326-2 A533B Cl. 1 .11 .55 0 94 C..
o Lower shell C4415-1 A533B Cl. 1 .11 .50 20 20 103(0)
Lower C4415-2 A5338 Cl. I .11 .50 0 83 In 123T338 A50B Cl. 2 .69 50 50 8B r% t_
,, nom head rg I' "
toI Bottom dorm C4315-3 A5338 Cl. I .14 .59 0 0 0
8T1554 & Lhds 80 tiux .18 .63 0(a) -5 Inter. & lower sthel vertical weld seam L1, L3. UL4
TABLE 3.1-1 (Contrinued)
UNIT 1 REACTOR VESSEL TOUGHNESS DATA (UNIRRADIATED)(d)
NMWD(b)
UPPER SHELF HEAT OR MATERIAL Cu TNDT ENERGY MATERIAL CODE No. ' SPEG NM .M L ,,
.35 .68 r
'-t'sbe vertical 2991.44 & Litl 80 flux -7 70/EMA(e) weld sea Inter. to lower 72445 & Linde 80 fhlx .21 0(a) -5 T7(8)/EMA(e) shell girth seam I I .4-Upper shell to Inter. 89 flux .10 0(a) 0 EMA(e) shell girth seam NOTES:
m
- 0. (a) Estimated per NRC standard review plan. NURE 00. Section MTEB i 0
m (b) Nommal to major working dredbn - estimat per NRC standard review plan, NUR Section MTEB 5-2 (c) Actual values a,
- 5 (d) Reactor Vessel FabricatorC Test Reports 0
(e) The approved equiva imargins analysis Inthe Topical Reports BAW-2192PA and BAW-2178PA demonstrates with the requirements 10 CFR 50, Appe 0.
0-4
TABLE 3.1-2 UNIT 2 REACTOR VESSEL TOUGHNESS DATA (UNIRRADIATED)
NMWD/b)
UPPER SHE HEAT OR MATERIAL Cu NI TNDT RTNDT ENERGY CODE=A SPEG ieNO, MI MI ca E COsur dome C4361-2 A5338 Cl. I *15 .52 20 7 He fta ZV-6475 A508 Cl. 2 .11 .60 ,10 (a) < 129 Vessel flange ZV-3476 A508 Cl. 2 .10 .64 6 5 .65 129 In9le norz 1 A508 Cl. 2 .87 60 66 Inlet norzzb 9-151104 \ A508 Cl. 2 - 0 ()60 73 Inl nozzl 9-5205 08 Cl. 2 / .86 60$a) 60 66 Outlet nozzle 9-4825 A50 .2 - .85 60 (a) 60 74 t Outlelnozzle 9-5086 A508 C - .86 60(s) 60 79 Outlet no~zzl 9-5086 A .2 \.87 60(s) 60 73 Uppershell 123V303 /A08 Cl. 2 .0 \ 73 30 30 104 ltemddlte shellC436 3 A533B Cl. 1 .12 -10 -10 84 Internediaeshe 72 f3ll AU330 Cl. I .11 .59 5
-20 83 v
Lower she/l o 855 C4208-2 530 A533B Cf. .15 39 94 Lower(shel 0 C4339-1 A5331 C(. .11 .54 -t0 105(C) 1Bo(1D50% 123T321 A508 Cl. 2 -892 .55 1 10 EMA~d)
°CD dome C4361-3 A5338 Cl. I .15 .52 -20 -15 80 \
Irntemoi~edashenl 72445tA Linde 80 fx .21 .59 - - 77(a)/EMA(d ver~tial wellsearns Lot 8579.
o L3 (i00%).LAI(01350Y.)*d L4 (D51/6t) 8T17B2 &Lince80 flux8597 .20 .55 -S EMA{d)
TABLE 3.1-2 (Continued)
UNIT 2REACTOR VESSEL TOUGHNESS DATA (UNIRRADIATED)
UPPER SHELF HEAT OR MATERIAL Cu N TNDT RTN ENERGY vertical K San L2 (I ) T1782 & Lhde 80flx 8597 .20 .55 -5 EMA(d)
Seam Li (1001% 8T1782 & Lhie 80 lux 8597 .20 .55 - .5 EMA(d)
Seam L2 (0T7%) 811782 & Lhde 80 flx 862 .20 -5 EMA(d)
Inter. to lower 0nG too FkxLW320 .19 .56 0(a) 0 90(c)E~MA(d) ;t stNll Mtseam Upper shetlto Inter. 4275 & F89/ .35 .10 0(a) 0 EMA(d) shiel ginl seam NOTES:
(a) Estimated per NRC standard review plan REG-0800. Section UTEB 5-2 (b) Normal to major workhi dredion stted per NRC standard review plan. NUR E ion MTEB 5-2 1 (c) Actual value based on ests normal to the major workg dkirction tance 0
? (d) The approved equ nt margins analysis Inthe Topical Reports BAW-2192PA and BAW-2178PA demo es compfiance with the requiremenis of
. 0t CFR 50, di G.\
0D /
1S.-.
CLI
/', /-\0
ATTACHMENT 3 REVISED TECHNICAL SPECIFICATION BASIS VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2
TS 3.1-9 Heatup and cooldown limit curves are calculated using the most limiting value of the nil-ductility reference temperature, RTNDT, at the end of 28.8 Effective Full Power Years (EFPY) and 29.4 EFPY for Units I and 2, respectively. The most limiting value of RTNDT (228.40 F) occurs at the 1/4-T, 00 azimuthal location in the Unit I intermediate-to-lower shell circumferential weld. The limiting RTNDT at the 1/4-T location in the core region is greater than the RTNDT of the limiting unirradiated material. This ensures that all components in the Reactor Coolant System will be operated conservatively in accordance with applicable Code requirements.
The reactor vessel materials have been tested to determine their initial RTNDT; the results are presented in UFSAR Section 4.1. Reactor operation and resultant fast neutron (E greater than I MEV) irradiation can cause an increase in the RTNDT. Therefore, an adjusted reference temperature, based upon the copper and nickel content of the material and the fluence was calculated in accordance with the recommendations of Regulatory Guide 1.99, Revision 2 "Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials." The heatup and cooldown limit curves of Figures 3.1-1 and 3.1-2 include predicted adjustments for this shift in RTNDT at the end of 28.8 EFPY and 29.4 EFPY for Units I and 2, respectively (as well as adjustments for location of the pressure sensing instrument).
Surveillance capsules will be removed in accordance with the requirements of ASTM E185-82 and 10 CFR 50, Appendix H. The surveillance specimen withdrawal schedule is shown in the UFSAR. The heatup and cooldown curves must be recalculated when the ARTNDT determined from the surveillance capsule exceeds the calculated ARTNDT for the equivalent capsule radiation exposure, or when the service period exceeds 28.8 EFPY or 29.4 EFPY for Units I and 2, respectively, prior to a scheduled refueling outage.
Amendment Nos.
TS 3.1-12 References (1) UFSAR, Section 4.1, Design Bases Amendment Nos.
TS 3.1-26 Pages TS 3.1-26 through TS 3.1-29 have been deleted.
Amendment Nos.