ML092990570

Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules

ML092990570
Person / Time
Site:	Surry
Issue date:	10/26/2009
From:	Price J Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
09-507
Download: ML092990570 (13)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 26, 2009 10 CFR 50 Appendix H U.S. Nuclear Regulatory Commission Serial No.09-507 Attention: Document Control Desk NL&OS/GDM RO Washington, DC 20555 Docket Nos. 50-280/281 License Nos. DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2 REVISED REACTOR VESSEL MATERIALS SURVEILLANCE CAPSULE WIITHDRAWAL SCHEDULES By letter dated May 29, 2001 (Serial No.01-282), Dominion submitted an Application for Renewed Operating Licenses for Surry Units 1 and 2 (and North Anna Units 1 and 2) that included a description of the Reactor Vessel Integrity Management Program (including the irradiation capsule surveillance activity) in Section B2.2.14. In response to an NRC request for additional information, Dominion provided information in a letter dated October 15, 2002 (Serial No.02-601) addressing Reactor Vessel Neutron Embrittlement including the Reactor Vessel Surveillance Program. As part of that response, Dominion informed the NRC of its intent to implement the recommendation of NUREG-1801, Generic Aging Lessons Learned (GALL) Report, for the withdrawal of the final plant-specific surveillance capsules. The NRC's Safety Evaluation Report for License Renewal of Surry Units 1 and 2 was documented in NUREG-1766 dated December 2002. Section 3.3.1.14 of NUREG-1766 addressed the Reactor Vessel Integrity Management Program and concluded that "the [NRC] staff finds that the program will adequately manage the reactor vessel neutron embrittlement in the beltline region ... [and] that the ... aging effect. .. will be adequately managed so that the intended functions will be maintained ... throughout the period of extended operation."

In subsequent correspondence dated March 27, 2003 (Serial No.03-195) associated with the evaluation of Surry Unit 2 Capsule Y data, and in correspondence dated June 13, 2006 (Serial No.06-434) that updated the Reactor Vessel Integrity Database, Dominion reiterated its intent to submit for NRC review and approval revised reactor vessel material surveillance capsule withdrawal schedules for Surry Units 1 and 2 that would be valid for the current 60-year operating license period and would incorporate the guidance of the GALL report.

Therefore, pursuant to 10 CFR 50 Appendix H, Section III.B.3, Dominion hereby submits for NRC review and approval the proposed reactor vessel material surveillance capsule withdrawal schedules for Surry Units 1 and 2. The proposed schedules were developed to accommodate the 60-year license period for Surry Units 1 and 2 and to satisfy the

Serial Number 09-507 Docket Nos. 50-280/281 Page 2 of 3 requirements and guidance of ASTM E-185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," dated July 1, 1982, and the GALL Report for surveillance capsule withdrawal and testing. The proposed schedules and their supporting technical justification are provided in the attachment. The revised schedules will be included in the Updated Final Safety Analysis Report (UFSAR) Tables 4.1-12 and 4.1-13 following receipt of NRC approval.

The current UFSAR Unit 2 surveillance capsule withdrawal schedule specifies withdrawal of Capsule U in 2008; however, this withdrawal did not occur in anticipation of implementation of GALL Report recommendations for surveillance capsule withdrawal schedules applicable to the 60-year license period. Also, to better reflect end-of-life fluence effects, Surry Unit 2 Capsule U is being relocated from the 65 degree reactor vessel capsule location to the 285 degree capsule location during the upcoming Surry Unit 2 fall 2009 refueling outage. This change will be incorporated into UFSAR Table 4.1-13 as part of the next scheduled revision of the UFSAR.

If you have any further questions regarding this submittal, please contact Mr. Gary D. Miller at (804) 273-2771.

Sincerely, AI;:4'wtJrice resident - Nuclear Engineering Commitments made in this letter: None

Attachment:

• Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules for Surry Units 1 and 2

Serial Number 09-507 Docket Nos. 50-280/281 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 NRC Senior Resident Inspector Surry Power Station Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 16E15 11555 Rockville Pike Rockville, Maryland 20852 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 H4A 11555 Rockville Pike Rockville, MD 20852-2738

Serial Number 09-507 Docket Nos. 50-280/281 ATTACHMENT Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules Surry Units 1 and 2 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

Serial Number 09-507 Docket Nos. 50-280/281 Attachment P~ge 1 of 9 Table of Contents 1.0 Introd uction 2.0 Background 3.0 Proposed Changes 4.0 Technical Evaluation 5.0 Affected UFSAR Sections 6.0 Conclusions 7.0 References Appendix A Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules for Surry Units 1 and 2

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 2 of 9 1.0 Introduction Virginia Electric and Power Company (Dominion) proposes changes to the reactor vessel materials surveillance capsule withdrawal schedules for Surry Power Station Units 1 and 2. The reactor vessel surveillance program was originally developed under ASTM E-185-73, and the current reactor vessel surveillance capsule withdrawal schedules were developed' under ASTM E-185-82 (References 1 and 2). The current reactor vessel materials surveillance capsule withdrawal schedules for the Surry reactor vessels are contained in the Surry UFSAR. However, the current reactor vessel materials surveillance capsule withdrawal schedules were developed and approved by the NRC prior to the renewal of the operating licenses at Surry (References 1 and 2).

Dominion subsequently provided the NRC with submittals supporting license renewal for Surry Units 1 and 2 (References 3 and 4) and received NRC approval and the renewed licenses for Surry (Reference 5). The proposed revised capsule withdrawal schedules for Surry incorporate the renewed license period (Le., 60-year license) corresponding to 48 Effective Full Power Years (EFPY) for Surry Units 1 and 2, as well as the requirements of ASTM E-185-82 (Reference 6) and the recommendations of the Generic Aging Lessons Learned (GALL) Report, NUREG-1801 (Reference 7).

2.0 Background

10 CFR 50 Appendix H defines the requirements for reactor vessel materials surveillance programs. Dominion's compliance with the requirements of Appendix H is documented for Surry Units 1 and 2 in References 8 and 9, respectively. Appendix H states that the purpose of the materials surveillance program' is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of light water nuclear power reactors resulting from exposure of these materials to neutron irradiation and the thermal environment. Fracture toughness data are obtained from material specimens exposed in surveillance capsules, which are withdrawn periodically from the reactor vessel. These data are used as described in Appendix G to 10 CFR 50.

Dominion has confirmed that the highest predicted nil~ductility transition temperature shift for Surry Unit 1 materials is greater than 200°F at the end of the 60-year license period. Because the limiting value is greater than 200°F, Surry Units 1 and 2 continue to qualify for a five-capsule surveillance program as described in ASTM E-185-82. Four capsules (of the five capsules cited in References 8 and 9) have already been withdrawn from each unit. The capsule withdrawals for both units were performed in a timeframe that was in compliance with Table 1 of ASTM E-185-82. For both Surry Units 1 and 2, a fifth surveillance capsule must be withdrawn to satisfy the requirements of Table 1 of ASTM E-185-82. ASTM E-185-82 requires that the fluences of the fifth capsules

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 3 of 9 must not be less than once or greater than twice the peak end of life (EOl) vessel fluence.

In addition to the requirements provided in ASTM E-185-82, the GALL Report (NUREG-1801)Section XI.M31 , "Reactor Vessel Surveillance," provides additional guidance regarding the withdrawal and testing of surveillance capsules for reactors that operate under a renewed license (Le., 60-year license). Both Item 5 and Item 6 from Section XI.M31 were considered in developing revised surveillance capsule withdrawal schedules for Surry Units 1 and 2.

Item 5 applies to capsules with fluences that will not reach 60-year fluence at the end of 40 years of operation. Item 5 recommends that a capsule be withdrawn during the period of extended operation (Le., between 40 and 60 years of operation).

Item 6 applies to capsules with fluences exceeding the 60-year fluence at the end of 40 years of operation. In addition, Item 6 requires that the capsule removed and tested to have a fluence that does not significantly exceed tl:le vessel fluence at an equivalent of 60 years of operation. Item 6 also allows for the irradiation of standby capsules to support potential additional license renewal efforts (e.g., 80-year operation).

3.0 Proposed Changes Changes to the Surry Units 1 and 2 reactor vessel materials surveillance capsule withdrawal schedules include:

(a) The fluence estimates for active and standby capsules used in the development of the revised surveillance capsule withdrawal schedules were obtained using the NRC approved methodology per AREVA's Topical Report BAW-2241-P-A (Reference 10). Note that the fluence estimates are unchanged from those that support the current material property basis (e.g., Reactor Vessel Integrity Database (RVID)), as described in Dominion's submittal to utilize AREVA Topical Report BAW-2308, Rev. 1-A (References 11 and 12).

(b) The estimated dates for the removal of the active fifth capsules have been revised to 2025 and 2027 for Surry Units 1 and 2, respectively, to reflect the 60-year license period for Surry Units 1 and 2 while satisfying the requirements and guidance of ASTM E-185-82 (Reference 6) and the GAll Report (Reference 7) for surveillance capsule withdrawal and testing.

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 4 of 9 4.0 Technical Evaluation Section III.B.3 of 10CFR 50 Appendix H requires a proposed surveillance capsule withdrawal schedule and its technical justification to be submitted to the NRC for review and approval prior to implementation. The evaluation that follows provides the technical justification for the proposed surveillance capsule withdrawal schedules.

4.1 Fluence Values The fluence values used in the proposed surveillance capsule withdrawal schedules were developed using the methodology given in Reference 10.

Reference 10 has been reviewed and approved by the NRC for use in licensing applications at Surry 1 and 2. The fluence values employed in the development of the revised surveillance capsule withdrawal schedules are unchanged from those used in the most recent updates to the NRC's Reactor Vessel Integrity Database (RVID) (References 11 and 12).

4.2 Revised Dates for the Removal of the Fifth Surveillance Capsules for Surry Units 1 and 2 According to the current capsule withdrawal schedules for Surry Units 1 and 2, Unit 1 has scheduled capsule Z for withdrawal in 2012 and Unit 2 had scheduled

. capsule U for withdrawal in 2008. However these current schedules are based upon 40-year operation. The dates for capsule withdrawal for Surry Units 1 and 2 must be changed in order to ensure that 60-:year operation is adequately bounded by the withdrawal and testing of the fifth capsule in each Surry unit.

Capsules Z and U are designated as the fifth capsules in Surry Units 1 and 2, respectively. Withdrawal of capsule Z in year 2025 for Surry Unit 1 and U in year 2027 for Surry Unit 2 will provide data that bounds the expected EOl fluence for 60-year operation. At the proposed revised removal dates, capsules Z in Surry Unit 1 and U in Surry Unit 2 will have experienced a fluence of at least once but not greater than twice the peak EOl vessel fluence in accordance with the requirements of ASTM E-185-82. In addition, the selected dates for testing and withdrawal of capsules Z and U in Surry Units 1 and 2, respectively, ensure that the capsule fluences do not significantly exceed the vessel fluence at an equivalent of 60 years of operation per the guidance of the GAll Report.

5.0 Affected UFSAR Sections Sections of the Surry Units 1 and 2 UFSAR will need to be revised to support implementation of the revised surveillance capsule withdrawal schedules described .

herein and provided in Appendix A. Following the receipt of NRC approval, a UFSAR revision will be made in accordance with the requirements of 10 CFR 50.71 (e).

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 5 of9 Dominion did not withdraw surveillance capsule U from the 65° location in the Surry Unit 2 reactor vessel in 2008 in anticipation of implementation of GALL Report recommendations, as previously described in References 4, 11, and 13. Dominion 0

plans to relocate surveillance capsule U from the 65° location to the 285 location during the upcoming Fall 2009 refueling outage. Under the proposed revised surveillance capsule withdrawal schedules, Capsule U will be withdrawn from Unit 2 at 45 EFPY, which is projected to occur in 2027. This change in location and schedule for withdrawal of Capsule U makes the Surry Unit 2 surveillance capsule withdrawal schedule consistent with ASTM E-185-82 and with GALL Report recommendations for the 60-year license period.

6.0 Conclusions Revised reactor vessel materials surveillance capsule withdrawal schedules have been developed for Surry Units 1 and 2 and are provided in Appendix A. These schedules meet the requirements of 10 CFR 50 Appendix H, ASTM E-185-82, and the guidance of the GALL Report, NUREG-1801. The proposed revised surveillance capsule schedules will ensure that the Surry Units 1 and 2 reactor vessel material surveillance programs will continue to meet the applicable regulatory requirements through the license period (i.e., 60-year operation).

7.0 References

1. L. S. Harbison, Master Integrated Reactor Vessel Surveillance Program, BAW-1543, Revision 4, dated February 1993. Also Supplement 1 dated February, 1993.

2. Letter from VEPCO to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Updated Final Safety Analysis Report, Revision 26," Serial No.96-170, dated April 23, 1996.

3. Letter from D. A. Christian to USNRC, 'Virginia Electric and Power Company, Surry and North Anna Power Stations Units 1 and 2, License Renewal Applications - Submittal," Serial No. 01 -282, dated May 29,2001.

4. Letter from L. N. Hartz to USNRC, "Virginia Electric and Power Company (Dominion), Surry and North Anna Power Stations Units 1 and 2, Response to Request for Supplemental Information License Renewal Applications," Serial No.02-601, dated October 15, 2002.

5. Letter from USNRC to D. A Christian, "License Renewal Safety Evaluation Report for North Anna, Units 1 and 2, and Surry, Units 1 and 2", Serial No.02-709, November 5, 2002.

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 6 of 9 7.0 References (cont'd)

6. ASTM E-185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," dated July 1, 1982.

7. NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," dated July 2001.

8. WCAP-7723, "Surry Unit 1 Reactor Vessel Radiation Surveillance Program,"

dated July 1971.

9. WCAP-8805, "Surry Unit 2 Reactor Vessel Radiation Surveillance Program,"

dated June 1973.

10. Framatome ANP Topical Report BAW-2241-P-A, Revision 1, "Fluence and Uncertainty Methodologies,"

11. Letter from E. S. Grecheck to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Update to NRC Reactor Vessel Integrity Database and Exception Request for Alternate Materials Properties Basis per 10CFR50.60(b)," Serial No.06-434, dated June 13, 2006.

12. Letter from USNRC to D. A. Christian, "Surry Power Station Units 1 and 2, Exception from the Requirements of 10CFR Part 50, Appendix G and 10CFR Part 50, Section 50.61, (TAC Nos. MD MD2337 and MD2338)," Serial No.07-498, dated June 27,2007.

13. Letter from Leslie N. Hartz to USNRC, "Virginia Electric Power Company Surry Power Station Unit 2 Evaluation of Surry Unit 2 Capsule Data", Serial Number 03-195, dated March 27,2003.

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 7 of 9 APPENDIX A Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules for Surry Units 1 and 2

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 8 of 9 TABLE 4.1-12 Surveillance Capsule Withdrawal Schedule a for Surry Unit 1 Capsule Capsule Withdrawal Insert Est. Capsule Ident. Location EFPYlYear EFPYlYear Fluence (X10 19) b TC 285 0 1.5/1974 NA 0.281 W C 55 0 3.0/1978 NA 0.431 VC 165 0 6.0/1986 NA 1.94 X 65 0 13.3/1994 NA 1.28 X 1650 NA 13.3/1994 NA XC 1650 15.8/1997 NA 1.60 Z 245 0 13.3/1994 NA 2.11 Z 285 0 NA 13.3/1994 NA ZC 285 0 43.2/2025 NA 6.31 U 45 0 13.3/1994 NA 0.95 U 65 0 NA 13.3/1994 NA Ud 65 0 NA NA 4.58 (48.0 EFPY)

S 295 0 43.2/2025 NA 5.02 S 285 0 NA 43.2/2025 NA Sd 285 0 NA NA 6.05 (48.0 EFPY)

Y 305 0 15.8/1997 NA 1.52 Y 1650 NA 15.8/1997 NA yd 165 0 NA NA 6.34 (48.0 EFPY)

a. Withdrawal schedule meets requirements of ASTM E 185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, dated July 1, 1982.

b. 48.0 EFPY corresponds to the estimated cumulative core burnup at the end of the 50-year license period. Fluence values for withdrawn capsules are obtained from capsule test reports.

c. These capsules are required to satisfy the requirements of ASTM E 185-82 during the license period.

d. Standby Capsules S, U, and Yare available to satisfy potential fluence monitoring requirements during the 20-year license renewal period.

Serial Number 09-507 Docket Nos. 50-280/281 Attachment Page 9 of 9 TABLE 4.1-13 Surveillance Capsule Withdrawal Schedulea for Surry Unit 2 Capsule Capsule Withdrawal Insert Est. Capsule Ident. Location EFPYNear EFPYNear Fluence (X1 0 19) b XC 285 0 1.2/1975 NA 0.297 W C 245 0 3.8/1979 NA 0.636 VC 1650 8.5/1986 NA 1.89 Y 295 0 13.7/1994 NA 1.97 Y 1650 NA 13.7/1994 NA y C 1650 19.7/2002 NA 3.14 U 65° 27.9/2009 NA 3.49 U 285 0 NA 27.9/2009 NA C 285 0 45.0/2027 NA 5.95 U

T 55 0 19.7/2002 NA 1.82 T 165 0 NA 19.7/2002 NA Td 165 0 NA NA 5.88 (48.0 EFPY)

Z 305 0 13.7/1994 NA 1.34 Z 245 0 NA 13.7/1994 NA Z 245 0 45.0/2027 NA 4.48 Z 285 0 NA 45.0/2027 NA Zd 285 0 NA NA 5.09 (48.0 EFPY)

S 45 0 15.0/1996 NA 1.07 W1 285 0 NA 10.9/1991 NA W1 e 285 0 . 16.4/1997 NA 0.690

a. Withdrawal schedule meets requirements of ASTM E 185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, dated July 1, 1982.

b. 48.0 EFPY corresponds to the estimated cumulative core burnup at the end of the 50-year license period. Fluence values for withdrawn capsules are obtained from capsule test reports.

c. These capsules are required to satisfy the requirements of ASTM E 185-82 during the license period.

d. Capsules T and Z are available to satisfy potential fluence monitoring requirements during the 20-year license renewal period,

e. Master Integrated Reactor Vessel Materials Surveillance Program capsule.