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| | issue date = 12/10/1991 | | | issue date = 12/10/1991 |
| | title = Submits Info Re Revised 10CFR50.61 Requirements & Procedure for Calculating Reactor Vessel Matl Embrittlement. Implementation of Flux Reduction Program Underway at Surry 1.Values Re end-of-life PTS Revised | | | title = Submits Info Re Revised 10CFR50.61 Requirements & Procedure for Calculating Reactor Vessel Matl Embrittlement. Implementation of Flux Reduction Program Underway at Surry 1.Values Re end-of-life PTS Revised |
| | author name = STEWART W L | | | author name = Stewart W |
| | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:,. . ' e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1991 United States Nuclear Regulatory Commission Attention: | | {{#Wiki_filter:,. .' e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1991 United States Nuclear Regulatory Commission Serial No. 91-328 Attention: Document Control Desk NO/CGL:vlh R1 Washington, D. C. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen: |
| Document Control Desk Washington, D. C. 20555 Gentlemen: | | VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 REVISION TO 10 CFR 50.61 FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS In response to the revised 10 CFR 50.61 requirements and procedure for calculating reactor vessel material embrittlement, Virginia Electric and Power Company is providing the following information. |
| VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No. NO/CGL:vlh Docket Nos. License Nos. NORTH ANNA POWER STATION UNITS 1 AND 2 REVISION TO 10 CFR 50.61 FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS 91-328 R1 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 In response to the revised 1 O CFR 50.61 requirements and procedure for calculating reactor vessel material embrittlement, Virginia Electric and Power Company is providing the following information.
| | The Pressurized Thermal Shock (PTS) rule requires each PWR licensee to report the results of the calculations of predicted RTPTS values for each beltline material for the fluence at the time the report is submitted and the fluence at the expiration date of the operating license (EOL). The report should include the copper content, nickel content, fluence values, and assumptions about core loading patterns that were used in the calculations. The PTS rule further requires that if RTPTS for the controlling material is predicted to exceed the screening criterion before EOL, the licensee should submit plans and a schedule for flux reduction programs that are reasonably practicable to avoid reaching the screening criterion. Finally, the PTS rule requires licensees of plants that would reach the screening criterion before EOL despite the flux reduction program to submit a plant-specific safety analysis justifying operation beyond the screening criterion. |
| The Pressurized Thermal Shock (PTS) rule requires each PWR licensee to report the results of the calculations of predicted RTPTS values for each beltline material for the fluence at the time the report is submitted and the fluence at the expiration date of the operating license (EOL). The report should include the copper content, nickel content, fluence values, and assumptions about core loading patterns that were used in the calculations.
| | The recent revision to the 10 CFR. 50.61 PTS rule requires the PWR licensee to recalculate values of RTPTS for the limiting reactor vessel beltline materials. If the RTPTS for any of the materials is predicted to exceed the screening criterion prior to EOL, the licensee must resubmit to the NRC the RTPTS results for those materials prior to December 16, 1991. If RTPTS is not predicted to exceed the screening criterion prior to EOL, the assessment must be submitted with the next update to the pressure-temperature limits, or the next reactor vessel materials surveillance report, or within 5 years bf the effective date of the rule, whichever comes first. l\r~ * |
| The PTS rule further requires that if RTPTS for the controlling material is predicted to exceed the screening criterion before EOL, the licensee should submit plans and a schedule for flux reduction programs that are reasonably practicable to avoid reaching the screening criterion. | | :r n~: |
| Finally, the PTS rule requires licensees of plants that would reach the screening criterion before EOL despite the flux reduction program to submit a plant-specific safety analysis justifying operation beyond the screening criterion. | | p 21 1Rafil i~~ *** *'* rt' ', |
| The recent revision to the 1 O CFR. 50.61 PTS rule requires the PWR licensee to recalculate values of RTPTS for the limiting reactor vessel beltline materials. | | |
| If the RTPTS for any of the materials is predicted to exceed the screening criterion prior to EOL, the licensee must resubmit to the NRC the RTPTS results for those materials prior to December 16, 1991. If RTPTS is not predicted to exceed the screening criterion prior to EOL, the assessment must be submitted with the next update to the pressure-temperature limits, or the next reactor vessel materials surveillance report, or \r within 5 years bf the effective date of the rule, whichever comes first. l * :r n~: 21 1Rafil * * * * '* rt' ' , p | | We submitted PTS analysis reports to the NRC via letters dated April 30, 1987 and March 15, 1988 (Serial Nos. 86-8198 and 88-056) for Surry and North Anna, respectively. The Surry PTS analysis is documented in WCAP-11015, Revision 1 (C. |
| -------We submitted PTS analysis reports to the NRC via letters dated April 30, 1987 and March 15, 1988 (Serial Nos. 86-8198 and 88-056) for Surry and North Anna, respectively.
| | C. Heinecke, et al., "Surry Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," dated April, 1987). The North Anna PTS analysis is documented in WCAP-11016, Revision 3 (C. C. Heinecke, et al., "North Anna Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," dated January, 1988). These analyses utilized the method of 10 CFR 50.61 prior to the incorporation of the RG 1.99 Revision 2 methodology into the PTS rule. |
| The Surry PTS analysis is documented in WCAP-11015, Revision 1 (C. C. Heinecke, et al., "Surry Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," dated April, 1987). The North Anna PTS analysis is documented in WCAP-11016, Revision 3 (C. C. Heinecke, et al., "North Anna Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," dated January, 1988). These analyses utilized the method of 1 O CFR 50.61 prior to the incorporation of the RG 1.99 Revision 2 methodology into the PTS rule. We have calculated revised values of the EOL RTPTS for the controlling materials identified in the previous PTS submittals for both Surry and North Anna. We have concluded that none of the revised RTPTS values exceed the applicable screening criterion prior to end of license with the exception of that of the Surry Unit 1 Lower Shell Longitudinal Weld L2. Our calculations utilized the revised 1 O CFR 50.61 procedure, as well as the same copper nickel contents, EOL fluence, and core loading pattern assumptions as the previous PTS submittals. | | We have calculated revised values of the EOL RTPTS for the controlling materials identified in the previous PTS submittals for both Surry and North Anna. We have concluded that none of the revised RTPTS values exceed the applicable screening criterion prior to end of license with the exception of that of the Surry Unit 1 Lower Shell Longitudinal Weld L2. Our calculations utilized the revised 10 CFR 50.61 procedure, as well as the same copper nickel contents, EOL fluence, and core loading pattern assumptions as the previous PTS submittals. All assumptions reflect, or are conservative with respect to, the current plant configuration and the requirements of 10 CFR 50.61. |
| All assumptions reflect, or are conservative with respect to, the current plant configuration and the requirements of 1 O CFR 50.61. As indicated in previous correspondence (Letters Serial Nos.* 89-748 dated December 1, 1989, 90-335 dated July 30, 1990, and 91-374 dated July 8, 1991 ), we are in the process of implementing a flux reduction program at Surry 1. As noted in our July 8, 1991 letter, flux suppression inserts (FSls) are planned to be installed in Surry Unit 1 during Cycle 13. The target fluence in this program is well below that which could cause RTPTS to exceed the screening criterion at EOL. We consider this plan adequate to ensure that the requirements of 1 O CFR 50.61 will continue to be met throughout the operating life of the plant. The attachment presents the chemistry and fluence data, and the RTPTS values calculated for the limiting materials in the Surry and North Anna vessels. As required by the PTS rule, the appropriate information is included in the attachment for the Surry Unit 1 Lower Shell Longitudinal Weld L2, which is predicted to exceed the screening criteria at EOL in the absence of flux reduction. | | As indicated in previous correspondence (Letters Serial Nos.* 89-748 dated December 1, 1989, 90-335 dated July 30, 1990, and 91-374 dated July 8, 1991 ), we are in the process of implementing a flux reduction program at Surry 1. As noted in our July 8, 1991 letter, flux suppression inserts (FSls) are planned to be installed in Surry Unit 1 during Cycle 13. The target fluence in this program is well below that which could cause RTPTS to exceed the screening criterion at EOL. We consider this plan adequate to ensure that the requirements of 10 CFR 50.61 will continue to be met throughout the operating life of the plant. |
| Although 1 O CFR 50.61 does not require immediate submission of revised values of RTPTS for materials not predicted to exceed the screening criterion prior to EOL, the attachment also includes revised* RTPTS values for the limiting materials in the Surry and North Anna reactor vessels. If you have any questions or require additional information, please contact us. Very truly yours, wrf(ii;J W. L. Stewart Senior Vice President | | The attachment presents the chemistry and fluence data, and the RTPTS values calculated for the limiting materials in the Surry and North Anna vessels. As required by the PTS rule, the appropriate information is included in the attachment for the Surry Unit 1 Lower Shell Longitudinal Weld L2, which is predicted to exceed the screening criteria at EOL in the absence of flux reduction. Although 10 CFR 50.61 does not require immediate submission of revised values of RTPTS for materials not predicted to exceed the screening criterion prior to EOL, the attachment also includes revised* |
| -Nuclear Attachment | | RTPTS values for the limiting materials in the Surry and North Anna reactor vessels. |
| -Revised Current and EOL RT PTS Values cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. M. S. Lesser NRC Senior Resident Inspector North Anna Power Station REVISED CURRENT AND EOL RTpTs VALUES STATION UNIT WELD ID -N. Anna 1 Lower Shell 03 N. Anna 1 Lower She 11 03 N. Anna 1 Circ. Weld 04 N. Anna 1 Circ. Weld 04 N. Anna 2 Lower Shell 03 ~-Anna 2. Lower Shell 03 N; A~ha 2 Circ. Weld 04 N. Anna 2 Circ. Weld 04 Surry Surry Surry Surry 1 Circ. Weld 05 1 Circ. Weld 05 1 Long. Weld L2 1 Long. Weld L2 2 Circ. Weld 05 2 Circ. Weld 05 WT.% CU .15 .15 .11 .11 .13 .13 .065 .065 .21 .21 .35 .35 .19 .19 Surry Surry Surry Surry 2 Long. Welds Ll/L2 .29 2 Long. Welds Ll/L2 .29 WT% NI .80 .80 .086 .086 .83 .83 .044 .044 .58 .58 .67 .67 .56 .56 .55 .55 FLUENCE (1El9 NLSQ.CMl 6.79 1.88 6.79 1.88 6.96 1. 79 6.96 1. 79 5.55 2.07 .901 .335 5.69 2.07 .922 .336 RT(PTS) (DEG Fl 240 207 148 134 230 201 60 *49 Screen. Crit. (DEG Fl NOTES 270 EOL 270 Current 300 EOL 300 Current 270 EOL 270 Current 300 EOL 300 Current 295 * | | If you have any questions or require additional information, please contact us. |
| * 300 EOL 259 300 Current 282*/*
| | Very truly yours, wrf(ii;J W. L. Stewart Senior Vice President - Nuclear Attachment - Revised Current and EOL RT PTS Values |
| * 270 EOL 221 281 247 246 195 270 Current 300 EOL 300 Current 270 EOL 270 Current
| | |
| * Predicted to exceed screening criteria at EOL in the absence of flux reduction. | | cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. |
| * * | | Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. M. S. Lesser NRC Senior Resident Inspector North Anna Power Station |
| | |
| | REVISED CURRENT AND EOL RTpTs VALUES FLUENCE Screen. |
| | (1El9 RT(PTS) Crit. |
| | STATION UNIT WELD ID WT.% CU WT% NI NLSQ.CMl (DEG Fl (DEG Fl NOTES N. Anna 1 Lower Shell 03 .15 .80 6.79 240 270 EOL N. Anna 1 Lower She 11 03 .15 .80 1.88 207 270 Current N. Anna 1 Circ. Weld 04 .11 .086 6.79 148 300 EOL N. Anna 1 Circ. Weld 04 .11 .086 1.88 134 300 Current N. Anna 2 Lower Shell 03 .13 .83 6.96 230 270 EOL |
| | ~- Anna 2. Lower Shell 03 .13 .83 1. 79 201 270 Current N; A~ha 2 Circ. Weld 04 .065 .044 6.96 60 300 EOL N. Anna 2 Circ. Weld 04 .065 .044 1. 79 *49 300 Current Surry 1 Circ. Weld 05 .21 .58 5.55 295 * |
| | * 300 EOL Surry 1 Circ. Weld 05 .21 .58 2.07 259 300 Current Surry 1 Long. Weld L2 .35 .67 .901 282*/* |
| | * 270 EOL Surry 1 Long. Weld L2 .35 .67 .335 221 270 Current Surry 2 Circ. Weld 05 .19 .56 5.69 281 300 EOL Surry 2 Circ. Weld 05 .19 .56 2.07 247 300 Current Surry 2 Long. Welds Ll/L2 .29 .55 .922 246 270 EOL Surry 2 Long. Welds Ll/L2 .29 .55 .336 195 270 Current |
| | * Predicted to exceed screening criteria at EOL in the absence of flux reduction. |
| | * * |
| * Expected RTprs under flux reduction will be less than this value.}} | | * Expected RTprs under flux reduction will be less than this value.}} |
|
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 1999-09-08
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,. .' e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1991 United States Nuclear Regulatory Commission Serial No.91-328 Attention: Document Control Desk NO/CGL:vlh R1 Washington, D. C. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 REVISION TO 10 CFR 50.61 FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS In response to the revised 10 CFR 50.61 requirements and procedure for calculating reactor vessel material embrittlement, Virginia Electric and Power Company is providing the following information.
The Pressurized Thermal Shock (PTS) rule requires each PWR licensee to report the results of the calculations of predicted RTPTS values for each beltline material for the fluence at the time the report is submitted and the fluence at the expiration date of the operating license (EOL). The report should include the copper content, nickel content, fluence values, and assumptions about core loading patterns that were used in the calculations. The PTS rule further requires that if RTPTS for the controlling material is predicted to exceed the screening criterion before EOL, the licensee should submit plans and a schedule for flux reduction programs that are reasonably practicable to avoid reaching the screening criterion. Finally, the PTS rule requires licensees of plants that would reach the screening criterion before EOL despite the flux reduction program to submit a plant-specific safety analysis justifying operation beyond the screening criterion.
The recent revision to the 10 CFR. 50.61 PTS rule requires the PWR licensee to recalculate values of RTPTS for the limiting reactor vessel beltline materials. If the RTPTS for any of the materials is predicted to exceed the screening criterion prior to EOL, the licensee must resubmit to the NRC the RTPTS results for those materials prior to December 16, 1991. If RTPTS is not predicted to exceed the screening criterion prior to EOL, the assessment must be submitted with the next update to the pressure-temperature limits, or the next reactor vessel materials surveillance report, or within 5 years bf the effective date of the rule, whichever comes first. l\r~ *
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p 21 1Rafil i~~ *** *'* rt' ',
We submitted PTS analysis reports to the NRC via letters dated April 30, 1987 and March 15, 1988 (Serial Nos. 86-8198 and 88-056) for Surry and North Anna, respectively. The Surry PTS analysis is documented in WCAP-11015, Revision 1 (C.
C. Heinecke, et al., "Surry Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," dated April, 1987). The North Anna PTS analysis is documented in WCAP-11016, Revision 3 (C. C. Heinecke, et al., "North Anna Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," dated January, 1988). These analyses utilized the method of 10 CFR 50.61 prior to the incorporation of the RG 1.99 Revision 2 methodology into the PTS rule.
We have calculated revised values of the EOL RTPTS for the controlling materials identified in the previous PTS submittals for both Surry and North Anna. We have concluded that none of the revised RTPTS values exceed the applicable screening criterion prior to end of license with the exception of that of the Surry Unit 1 Lower Shell Longitudinal Weld L2. Our calculations utilized the revised 10 CFR 50.61 procedure, as well as the same copper nickel contents, EOL fluence, and core loading pattern assumptions as the previous PTS submittals. All assumptions reflect, or are conservative with respect to, the current plant configuration and the requirements of 10 CFR 50.61.
As indicated in previous correspondence (Letters Serial Nos.* 89-748 dated December 1, 1989,90-335 dated July 30, 1990, and 91-374 dated July 8, 1991 ), we are in the process of implementing a flux reduction program at Surry 1. As noted in our July 8, 1991 letter, flux suppression inserts (FSls) are planned to be installed in Surry Unit 1 during Cycle 13. The target fluence in this program is well below that which could cause RTPTS to exceed the screening criterion at EOL. We consider this plan adequate to ensure that the requirements of 10 CFR 50.61 will continue to be met throughout the operating life of the plant.
The attachment presents the chemistry and fluence data, and the RTPTS values calculated for the limiting materials in the Surry and North Anna vessels. As required by the PTS rule, the appropriate information is included in the attachment for the Surry Unit 1 Lower Shell Longitudinal Weld L2, which is predicted to exceed the screening criteria at EOL in the absence of flux reduction. Although 10 CFR 50.61 does not require immediate submission of revised values of RTPTS for materials not predicted to exceed the screening criterion prior to EOL, the attachment also includes revised*
RTPTS values for the limiting materials in the Surry and North Anna reactor vessels.
If you have any questions or require additional information, please contact us.
Very truly yours, wrf(ii;J W. L. Stewart Senior Vice President - Nuclear Attachment - Revised Current and EOL RT PTS Values
cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. M. S. Lesser NRC Senior Resident Inspector North Anna Power Station
REVISED CURRENT AND EOL RTpTs VALUES FLUENCE Screen.
(1El9 RT(PTS) Crit.
STATION UNIT WELD ID WT.% CU WT% NI NLSQ.CMl (DEG Fl (DEG Fl NOTES N. Anna 1 Lower Shell 03 .15 .80 6.79 240 270 EOL N. Anna 1 Lower She 11 03 .15 .80 1.88 207 270 Current N. Anna 1 Circ. Weld 04 .11 .086 6.79 148 300 EOL N. Anna 1 Circ. Weld 04 .11 .086 1.88 134 300 Current N. Anna 2 Lower Shell 03 .13 .83 6.96 230 270 EOL
~- Anna 2. Lower Shell 03 .13 .83 1. 79 201 270 Current N; A~ha 2 Circ. Weld 04 .065 .044 6.96 60 300 EOL N. Anna 2 Circ. Weld 04 .065 .044 1. 79 *49 300 Current Surry 1 Circ. Weld 05 .21 .58 5.55 295 *
- 300 EOL Surry 1 Circ. Weld 05 .21 .58 2.07 259 300 Current Surry 1 Long. Weld L2 .35 .67 .901 282*/*
- 270 EOL Surry 1 Long. Weld L2 .35 .67 .335 221 270 Current Surry 2 Circ. Weld 05 .19 .56 5.69 281 300 EOL Surry 2 Circ. Weld 05 .19 .56 2.07 247 300 Current Surry 2 Long. Welds Ll/L2 .29 .55 .922 246 270 EOL Surry 2 Long. Welds Ll/L2 .29 .55 .336 195 270 Current
- Predicted to exceed screening criteria at EOL in the absence of flux reduction.
- Expected RTprs under flux reduction will be less than this value.