L-13-036, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules: Difference between revisions

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{{Adams
#REDIRECT [[ML13151A060]]
| number = ML13151A058
| issue date = 05/28/2013
| title = Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules
| author name = Larson E A
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000334, 05000412
| license number = DPR-066, NPF-073
| contact person =
| case reference number = L-13-036
| document type = Letter type:L, Report, Miscellaneous
| page count = 12
}}
 
=Text=
{{#Wiki_filter:FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Eric A. Larson 724-682-5234 Site .Vice President Fax: 724-643-8069 May 28, 2013 L-1 3-036 10 CFR 50, Appendix H ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
 
==Subject:==
Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules As required.
by 10 CFR 50, Appendix H, FirstEnergy Nuclear Operating Company (FENOC) hereby submits a request for Nuclear Regulatory Commission (NRC)approval of a revision to the Beaver Valley Power Station, Unit Nos. 1 and 2 reactor vessel (RV) surveillance capsule withdrawal schedules.
The proposed changes to the surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials Standard Practice E185-82, "Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessel." The FENOC evaluation of the proposed changes is provided in Enclosure A. The RV surveillance capsule withdrawal schedules would be revised to be consistent with the recommendations included in Section 8 of WCAP-15571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," Supplement 1, Revision 2, dated September 2011 and Section 8 of WCAP-16527-NP, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," Supplement 1, Revision 1, dated September 2011. WCAP-1 5571 and WCAP-16527-NP are provided in Enclosures B and C, respectively.
To allow for normal NRC processing, FENOC requests approval of the proposed schedule changes by May 31, 2014.
Beaver Valley Power Station, Unit Nos. 1 and 2 L-1 3-036 Page 2 There are no regulatory commitments contained in this submittal.
If there are any questions or if additional information is required, please contact Mr. Thomas A.Lentz, Manager -Fleet Licensing, at (330) 315-6810.Sincerely, Eric A. Larson
 
==Enclosures:==
 
A FENOC Evaluation of the Proposed Changes B WCAP-1 5571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," Supplement 1, Revision 2, dated September 2011 C WCAP-16527-NP, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," Supplement 1, Revision 1, dated September 2011 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative 2'Enclosure A L-1 3-036 FENOC Evaluation of the Proposed Changes (9 Pages Follow)
FENOC Evaluation of the Proposed Changes
 
==Subject:==
Request Approval for Changes to the Beaver Valley Power Station, Unit Nos. 1 and 2 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table of Contents 1.0
 
==SUMMARY==
DESCRIPTION
...........................................................................
2 2.0 R E Q U IR E M E N T S ...........................................................................................
2
 
==3.0 PROPOSED CHANGE==
S ................................................................................
3 4.0 TECHNICAL EVALUATION
............................................................................
7 5 .0 C O N C L U S IO N .............................................................................................
..8 6 .0 R E F E R E N C E S ..............................................................................................
..9 FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 2 of 9 1.0
 
==SUMMARY==
DESCRIPTION FirstEnergy Nuclear Operating Company (FENOC) is requesting approval of proposed changes to the Beaver Valley Power Station, Unit Nos. 1 (BVPS-1) and 2 (BVPS-2) reactor pressure vessel (RPV) material irradiation surveillance capsule withdrawal schedules.
The proposed changes are submitted pursuant to 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements," Section III.B.3, which requires that: 1) withdrawal schedules be submitted with a technical justification as specified in 10 CFR 50.4, "Written Communications," and 2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation.
NRC approval of the proposed schedule would satisfy a BVPS-1 and a BVPS-2 license condition regarding the capsule withdrawal schedule that states: For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E185-82 [Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels] to the extent practicable for the configuration of the specimens in the capsule.Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
Additionally, the nuclear industry has developed a Coordinated Pressurized Water Reactor (PWR) Reactor Vessel Surveillance Program (CRVSP), which is documented in "Material Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326)." The purpose of the CRVSP is to increase the fluence levels of future surveillance capsules at withdrawal while maintaining compliance with 10 CFR 50 Appendix H and consistent with the guidance of NUREG-1 801, Revision 2, "Generic Aging Lessons Learned (GALL)Report." The CRVSP will help generate high fluence PWR surveillance data in support of extended life operations.
The proposed changes to the RPV surveillance capsule withdrawal schedules are consistent with the recommendations specified in ASTM E185-82, as referenced by the requirements of 10 CFR 50, Appendix H.2.0 REQUIREMENTS 10 CFR 50, Appendix H, requires nuclear power plant licensees to implement RPV surveillance programs to "monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region.. .which result from the exposure of these materials to neutron irradiation and the thermal environment." 10 CFR 50, Appendix H, Section III.B.1 states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 3 of 9 ASTM E185 that is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to which the RPV was purchased.
The rule permits the use of later editions of ASTM El 85, but including only those editions through 1982 (that is, ASTM E185-82).10 CFR 50, Appendix H, Section III.B.3, requires prior NRC approval of RPV surveillance capsule withdrawal schedule changes. Further, NRC Administrative Letter 97-04, "NRC Staff Approval for Changes to 10 CFR 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules," dated September 30, 1997, specifies that changes to RPV surveillance capsule withdrawal schedules that do not conform to ASTM E185 require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance.
The proposed changes to the BVPS-1 and BVPS-2 surveillance capsule withdrawal schedules conform to ASTM E185-82, and therefore, a license amendment is not required for these proposed changes.
 
==3.0 PROPOSED CHANGE==
S The purpose of the proposed changes is to revise the BVPS-1 and BVPS-2 RPV surveillance capsule withdrawal schedules due to updated neutron fluence projections.
Additionally, the proposed BVPS-2 RPV surveillance capsule withdrawal schedule implements the MRP-326 recommendation regarding Capsule A. The current surveillance capsule withdrawal schedules and the proposed revised schedules are provided below.The current BVPS-1 Updated Final Safety Analysis Report (UFSAR) Table 4.5-3,"Reactor Vessel Material Irradiation Surveillance Schedule," is as follows: Capsule Vessel Lead Withdrawal Fluence Location Factor (a) EFPY [effective full (n/cm 2 , E > 1.0 MeV)(a)(deg) power years] (b)V 165 1.60 1.16 (removed) 3.23 x 1018 (c)U 65 1.05 3.59 (removed 6.46x 10TM (c)W 245 1.09 5.89 (removed) 9.86 x 1018 (c)Y 295 1.22 14.3 (removed) 2.15 x 1019 (c)X 285 1.76 25.9 5.87 x 10T (f)T 55 (d) Standby Z 305 (e) Standby S 45 0.63 (g) Standby (a) Updated in Capsule Y dosimetry analysis.(b) Effective full power years from plant startup. Changes to this column will require prior NRC approval, (except to indicate that capsules have been removed), as specified in Section III.B.3, Appendix H of 10 CFR 50.(c) Actual fluence, calculated from plant evaluation.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 4 of 9 (d) Capsule T was moved to the Capsule U location at the end of Cycle 10 (10.8 EFPY). The lead factor was approximately 0.77 through the first 10 cycles.The average lead factor for Cycle 11 and higher is 0.95.(e) Capsule Z was moved to the Capsule V location at the end of Cycle 10 (10.8 EFPY). The lead factor was approximately 0.77 through the first 10 cycles.The average lead factor for Cycle 11 and higher is 1.11.(f) Reactor Vessel Clad/Base Metal interface at 45 EFPY.(g) Capsule S was moved to the Capsule Y location at the end of Cycle 19.NOTE: This information was obtained from Section 4.5 [WCAP-15571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," November 2000], except for Capsule X removal time and fluence which were subsequently updated to reflect power uprate to 2900 MWt [megawatts thermal].
Note that the 1 R1 9 movement of Capsule S was a result of the need to move this capsule to a location with a higher lead factor.The following recommended BVPS-1 surveillance capsule withdrawal schedule, is consistent with WCAP-15571, Supplement 1, Revision 2, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," and meets the requirements of ASTM El 85-82.Capsule Current (Original)
Lead Withdrawal Fluence, fa)Capsule Location Factor(a)
EFPY(b) [n/cm 2 , E > 1.0 MeV]V 1650 1.61 1.16 2.99 x 10" U 650 1.06 3.59 6.04 x 1018 W 2450 1.11 5.89 9.30 x 101'Y 2950 1.2 14.29 2.05 x 1019 X(c) 2850 1.72 26.5(c) 5.01 x 1019(c)T(d 65° (550) 0.99 Standby(d)
S(e) 2950 (450) 0.64 Standby(e)
Z__ _ 1650 (305 0) 1.24 36.6(') ---Notes: a) Updated in WCAP-15571, Supplement 1, Revision 2 b) Effective full power years (EFPY) from plant startup.c) Capsule X is planned to be withdrawn at the end of Cycle 22, which corresponds to 26.5 EFPY. This capsule will meet the requirements of ASTM El 85-82 for the fifth capsule to be withdrawn for the 40-year end-of-life (EOL).d) Capsule T was moved to the Capsule U location at the end of Cycle 10. In order to achieve higher fluence data for this capsule, Capsule T should be relocated to the current Capsule Z location when Capsule Z is withdrawn from the vessel [see footnote (f)].
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 5 of 9 e) Capsule S was moved to the Capsule Y location at the end of Cycle 19. In order to achieve higher fluence data for this capsule, Capsule S should be relocated to the Capsule X location when Capsule X is withdrawn from the vessel at 26.5 EFPY.f) Capsule Z was moved to the original Capsule V location at the end of Cycle 10.Based on the current information, Capsule Z should be withdrawn after 36.6 EFPY, which corresponds to the peak vessel fluence at 60-year EOL (50 EFPY), 5.58 x 1019 n/cm 2 (E > 1.0 MeV).NOTE: For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
The current BVPS-2 UFSAR Table 5.3-6, "Reactor Vessel Material Irradiation Surveillance Schedule," is as follows: Capsule Current Location Lead Withdrawal Fluence (degree) Factor(a)
EFPY(b) (n/cm 2 , E > 1.0 MeV)U 343 3.17 1.24 6.08 x 10 5 (c)V 107 3.64 5.98 2.63 x 1019(c)W 110 3.29 9.77 3.625 x 1019(c)X 287 3.71 14 5.837 x 1T'9 (d)Y 290 3.29 Standby Z 340 3.29 Standby Notes: (a) Updated in Capsule W dosimetry analysis.(b) Effective Full Power Years (EFPY) from plant startup. Changes to this column will require prior NRC approval as specified in Section III.B.3, Appendix H, of 10 CFR 50.(c) Fluence calculated by plant-specific evaluation.(d) Approximately equal to the projected peak vessel fluence at 48 EFPY, not less than once or greater than twice the maximum EOL (32 EFPY) inner vessel wall fluence.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 6 of 9 The following recommended BVPS-2 surveillance capsule withdrawal schedule is consistent with WCAP-16527-NP, Supplement 1, Revision 1, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," and meets the requirements of ASTM E185-82.Capsule Current (Original)
Lead Withdrawal Fluence, f(a)Capsule Location Factor(a)
EFPY(b) [n/cm 2 , E > 1.0 MeV]U 3430 3.17 1.25 6.15 x 10 1 8 V 1070 3.64 5.99 2.64 x 1019 W 1100 3.25 9.84 3.61 x 1019 X 2870 3.69 14.00 5.63 x 10'9 y(C) 2900 3.17 (c)Z(c) 3400 3.17 (c) ---A_(d) 1070 3.58 32(d) ---Notes: a) Updated in WCAP-16527-NP, Supplement 1, Revision 1.b) Effective full power years (EFPY) from plant startup.c) It is recommended that one of these capsules be pulled at a time when the capsule fluence exceeds one times the projected peak 80-year EOL fluence, but before the capsule fluence reaches two times the projected 60-year EOL fluence. Therefore, based on the current information, Capsule Y or Z should be withdrawn between 20.5 EFPY and 32.4 EFPY. In order to be consistent with NUREG-1929, "Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2," this capsule should be pulled at the refueling outage closest to 26.1 EFPY, which corresponds with a peak vessel fluence level of 8.5 x 1019 n/cm 2 (E > 1.0 MeV). The second capsule will remain in the vessel to provide fluence monitoring or future testing. The withdrawal of this capsule will be revisited at a later time.d) Supplemental Capsule A contains BVPS-1 initially unirradiated material specimens, as well as previously irradiated material specimens from BVPS-1, St. Lucie, and Fort Calhoun. Supplemental Capsule A was inserted in the vacant Capsule V location at the end of Cycle 8. In order to be consistent with the "Materials Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326)" recommendation, Capsule A is to be removed and tested when it reaches a fluence value equivalent to the peak 80-year vessel fluence for BVPS-1. This is expected to occur at approximately 32 EFPY.NOTE: For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 7 of 9 4.0 TECHNICAL EVALUATION BVPS-1 This request proposes to revise the BVPS-1 RPV surveillance capsule withdrawal schedule to account for updated neutron fluence projections based on the results of the latest surveillance Capsule Y evaluation, sister plant surveillance data (St. Lucie Unit 1 and Fort Calhoun), and the implementation of the extended power uprate program.Calculations were performed for end-of-license extension (EOLE) at 50 EFPY.The surveillance capsules are used to monitor changes in the toughness properties of ferritic materials in the RPV beltline.
The surveillance capsules are located closer to the core than the reactor vessel beltline materials, so that fracture toughness testing can be used to determine the nil-ductility transition temperature of the vessels at a later time in life. The current BVPS-1 Pressure -Temperature (P-T)limit curves were developed in accordance with 10 CFR 50, Appendix G, "Fracture Toughness Requirements," through 30 EFPY. These limits are based on the limiting beltline material adjusted reference temperature (ART) values, that is, lower shell plate B6903-1. The proposed change in the capsule withdrawal schedule does not adversely affect the validity of the existing P-T limit curves for the 30 EFPY term.The proposed change to the surveillance capsule schedule is based on the requirements of the 1982 Edition of ASTM E185 as provided in 10 CFR 50, Appendix H. Since the reference temperature nil-ductility transition shift (ARTNDT)projected at EOLE is greater than 2000 F (222.10 F), ASTM E185-82, Table 1,"Minimum Recommended Number of Surveillance Capsules and Their Withdrawal Schedule (Schedule in Terms of Effective Full-Power Years of the Reactor Vessel)," requires the withdrawal of a minimum of five capsules.
Four of the eight BVPS-1 reactor vessel surveillance capsules have been withdrawn and tested. At the end of Cycle 22, a fifth surveillance capsule (Capsule X) is planned to be withdrawn from the reactor vessel. In accordance with ASTM El 85-82, Table 1, note E, the fifth capsule is to be removed at, "Not less than once or greater than twice the peak EOL vessel fluence..." Withdrawal of Capsule X would meet the requirements of ASTM El 85-82 for the fifth capsule to be withdrawn for the 40-year EOL. Additionally, Capsule Z should be withdrawn after 36.6 EFPY, which corresponds to the peak vessel fluence at 60-year EOL (50 EFPY), 5.58 x 1019 n/cm 2 (E > 1.0 MeV).Capsule T and Capsule S could be utilized for 80-year EOL data.In summary, the proposed revision to the BVPS-1 RPV surveillance capsule withdrawal schedule is based on the analysis of the latest surveillance capsule removed (Capsule Y) and complies with the requirements provide in ASTM E185-82.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 8 of 9 BVPS-2 This request proposes to revise the BVPS-2 RPV surveillance capsule withdrawal schedule to account for updated neutron fluence projections based on the results of the latest surveillance Capsule X evaluation and the implementation of the extended power uprate program. Calculations were performed for EOLE at 54 EFPY.The surveillance capsules are used to monitor changes in the toughness properties of ferritic materials in the RPV beltline.
The surveillance capsules are located closer to the core than the reactor vessel beltline materials, so that fracture toughness testing can be used to determine the nil-ductility transition temperature of the vessels at a later time in life. The BVPS-2 P-T limit curves were developed in accordance with 10 CFR 50, Appendix G, for 22 EFPY, 30 EFPY, 40 EFPY, and 54 EFPY. BVPS-2 is operating to the 22 EFPY P-T limit curves. These limits are based on the limiting beltline material ART values, that is, intermediate shell plate B9004-1. The proposed change in the capsule withdrawal schedule does not adversely affect the validity of the existing P-T limit curves for the 22 EFPY term.The proposed change to the surveillance capsule schedule is based on the requirements of the 1982 Edition of ASTM E185 as provided in 10 CFR 50, Appendix H. Since the ARTNDT is less than 100' F (72.40 F), ASTM E185-82, Table 1 requires the withdrawal of a minimum of three capsules.
Four of the six BVPS-2 reactor vessel surveillance capsules have been withdrawn and tested. Per ASTM El 85-82, Table 1, note E, the third capsule is to be removed at, "Not less than once or greater than twice the peak EOL vessel fluence..." Withdrawal of Capsule X meets the requirements of ASTM E185-82, as Capsule X was the fourth capsule to be withdrawn for the 40-year EOL.To satisfy requirements for a 60-year as well as a potential 80-year capsule, either capsule Y or Z should be withdrawn between 20.5 EFPY and 32.4 EFPY. In order to be consistent with NUREG-1 929, this capsule should be pulled at the refueling outage closest to 26.1 EFPY, which corresponds with a peak vessel fluence level of 8.5 x 1019 n/cm 2 (E > 1.0 MeV). The remaining capsule is considered a standby capsule and would remain in the vessel for fluence monitoring or future testing.
 
==5.0 CONCLUSION==
 
The proposed BVPS-1 and BVPS-2 RPV surveillance capsule withdrawal schedules will continue to meet the RPV surveillance capsule withdrawal schedule criteria in ASTM E185-82 as required by 10 CFR 50.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 9 of 9
 
==6.0 REFERENCES==
: 1. WCAP-1 5571, Supplement 1, Revision 2, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," September 2011.2. WCAP-16527-NP, Supplement 1, Revision 1, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," September 2011.3. Electric Power Research Institute, "Materials Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326)," 2011.}}

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