BVY 09-006, License Renewal Application Amendment 37

License Renewal Application Amendment 37

ML090230678
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/15/2009
From:	Michael Colomb Vermont Yankee
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 09-006
Download: ML090230678 (8)

Text

Entergy Entergy Nuclear Operations, Inc.Vermont Yankee P.O. Box 0250 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 January 15, 2009 BVY 09-006 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Reference

Subject:

1. Letter, Entergy to USNRC, "Vermont Yankee Nuclear Power Station, License No. DPR-28, License Renewal Application," BVY 06-009, dated January 25, 2006.2. Letter, Entergy to USNRC, "Vermont Yankee Nuclear Power Station, license No. DPR-28, License Renewal Application, Amendment 34, BVY 08-002, dated January 30, 2008.3. NUREG-1 907, Volumes 1 and 2, "Safety Evaluation Report Related to the License Renewal of Vermont Yankee Power Station," dated May 2008.4. Atomic Safety and Licensing Board, Partial Initial Decision, ASLBP No.06-849-03-LR, dated November 24, 2008.Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)License Renewal Application Amendment 37

Dear Sir or Madam,

On January 25, 2006, Entergy Nuclear Operations, Inc. and Entergy Nuclear Vermont Yankee, LLC (Entergy) submitted the License Renewal Application (LRA) for the Vermont Yankee Nuclear Power Station as indicated by Reference 1.In Reference (2), Entergy provided the analysis for the feedwater nozzles. In Reference (3), the NRC, in License Condition 4, established the requirement for Entergy to submit the analysis for the recirculation outlet nozzle and core spray nozzle at least two years prior to the period of extended operation.

In Reference (4), the Atomic Safety and Licensing Board (ASLB) ordered Entergy to submit the results of the analysis for the core spray and recirculation outlet nozzles prior to a final ruling of Contentions 2A and 2B.This supplement provides required information that demonstrates acceptable results for the core spray and recirculation outlet nozzles as required by References (3) and (4)above.There are no new regulatory-commitments being made in this letter.Should you have any questions or require additional information concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.A ( 1-ocJR BVY 09-006 / page 2 of 3 I declare under penalty of perjury, that the foregoing is true and accurate.

Executed on January 15, 2009 Site Vice President Vermont Yankee Nuclear Power Station Attachment (1)cc listing (next page)

BVY 09-006 / page 3 of 3 cc: Mr. James Dyer, Director U.S. Nuclear Regulatory Commission Office 05E7 Washington, DC 20555-00001 Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Jack Strosnider, Director U.S. Nuclear Regulatory Commission Office T8A23 Washington, DC 20555-00001 Mr. Jonathan Rowley, Senior Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike MS-O-1 1 F1 Rockville, MD 20853 Mr. Mike Modes USNRC RI 475 Allendale Rd, King of Prussia, PA 19406 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 (for mail delivery)Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street -Drawer 20 Montpelier, Vermont 05620-2601 Diane Curran, Esq.Harmon, Curran, Spielberg

& Eisenberg, LLP 1726 M Street, N.W., Suite 600 Washington, D.C. 20036 BVY 09-006 / Attachment 1 Page 1 of 5 Attachment 1 Vermont Yankee Nuclear Power Station Licensing Renewal Application Submittal of Results for the Core Spray Outlet Nozzles Vermont Yankee Recirculation Outlet and Core Spray Nozzle Analysis Results On January 30, 2008, Entergy Nuclear Vermont Yankee (Entergy) submitted the results[1] of confirmatory analysis of the Vermont Yankee Nuclear Power Station (VY)feedwater nozzles to the Staff. The feedwater nozzle confirmatory analysis [2 -4]utilized ASME Code,Section III, Subsection NB-3200 [5] methodology using six stress components to develop three principle stresses and stress intensities to demonstrate acceptable nozzle fatigue usage factors, including environmentally assisted fatigue effects, for 60 years of plant operation.

The NRC Staff published its Safety Evaluation Report (SER) [6] on VY's license renewal application in May, 2008. The SER included a proposed license condition that "... VY perform and submit to NRC for review and approval, a ASME Code analysis of the recirculation outlet nozzle and core spray nozzle Entergy has completed confirmatory fatigue analyses of the VY recirculation outlet and core spray nozzles to satisfy the proposed license condition included in the SER. These confirmatory analyses [7 -12] are the analyses of record for the recirculation outlet and core spray nozzles. The confirmatory analyses have been performed consistent with the methodology used in the confirmatory analysis of the VY feedwater nozzle, and contain no significantly different technical or scientific judgments from those used in the VY feedwater nozzle confirmatory analysis.Discussion The following items summarize the methods used in the confirmatory analyses of the VY recirculation outlet and core spray nozzles [7 -12]: 1. The confirmatory analyses for the recirculation outlet and core spray nozzles are detailed ASME Code,Section III, Subsection NB-3200 [5] fatigue calculations.

The same ANSYS finite element models (FEMs) were used as were used for the previous environmental fatigue analyses [13, 16]. The same number and severity of design transients and the same water chemistry inputs were used as those for the previous environmental fatigue analyses [14, 15, 17, 18]. Thermal transient stresses were calculated directly using the FEMs for all transients.

2. The same transient definitions and cycle counts for 60 years of operation, as defined in Reference

[19] and used for the previous analyses [13 -18], were used for computation of cumulative usage factor (CUF) in the confirmatory analyses.

BVY 09-006 / Attachment 1 Page 2 of 5 3. The same limiting cross-sections previously evaluated for the recirculation and core spray nozzles (blend radius and safe end) were evaluated.

4. Primary plus secondary and total stress ranges for all events were calculated and a correction for elastic-plastic analysis (i.e., Ke) was applied, where appropriate.

Total stress intensities for each transient pair based on principal stress differences were calculated in accordance with ASME Code,Section III, Subparagraph NB- 3216.2[5]. Stress ranges for primary plus secondary and primary plus secondary plus peak stress were calculated using all six components of stress (3 direct and 3 shear stresses).

When more than one load set was defined for either of the event pair loadings, the stress differences were determined for all of the possible loading combinations, and the pair producing the largest alternating total stress intensity (including the effects of Ke) was used.5. For the CUF calculation, stress intensities for the event pairs were re-ordered in order of decreasing primary plus secondary plus peak stress intensity, including a correction for the ratio of modulus of elasticity (E) from the fatigue curve divided by E from the analysis.

A fatigue table was created to determine the number of cycles available for each of the events of an event pair, and to determine CUF per ASME Code,Section III, Subparagraph NB-3222.4e

[5]. For each load set pair in the fatigue table, the allowable number of cycles was determined from the alternating stress, which is half of the corrected total stress intensity range, using the appropriate ASME Code,Section III [5] fatigue curve.6. Per Section X.M1 of the GALL Report [20], environmental fatigue multipliers were calculated using the Fen relationships from NUREG/CR-6583

[21] for carbon and low alloy steels and NUREG/CR-5704

[22] for stainless steels. As was done for the feedwater nozzle confirmatory analysis, bounding Fen factors were applied for the safe end locations, and bounding Fen factors for each transient pair based on the highest temperature of each transient stress pair were applied for the blend radius locations.

The results of the confirmatory analyses and the final environmentally adjusted CUF (CUFen) results from the previous analyses for the recirculation outlet and core spray nozzles are shown in Table 1 below.

BVY 09-006 / Attachment 1 Page 3 of 5 Table 1 -VY Recirculation Outlet and Core Spray Nozzle 60-year CUF Results Including Environmental Effects Location Analysis CUFen / Allowable Recirculation Outlet Previous EAF Analysis [15] 0.0175 / 1.0 Safe End Confirmatory Analysis [9] 0.0037/1.0 Recirculation Outlet Previous Analysis [15] 0.084 /1.0 Blend Radius Confirmatory Analysis [9] 0.119 / 1.0 Core Spray Previous Analysis [18] 0.0593 / 1.0 Safe End Confirmatory Analysis [12] 0.0003/1.0 Core Spray Previous Analysis [18] 0.167/1.0 Blend Radius Confirmatory Analysis [12] 0.140 / 1.0 Conclusions Entergy has completed confirmatory analyses of the VY recirculation outlet and core spray nozzles [7 -12]. The confirmatory analyses use ASME Code,Section III, Subsection NB-3200 [5] methodology consistent with the confirmatory analysis of the VY feedwater nozzles [2 -4], and contain no significantly different technical or scientific judgments from those usedin that analysis.For the bounding locations shown in Table 1 for both nozzles, the CUF results, including environmental effects, for both the previous analyses and the confirmatory analyses show that the CUFen values are all less than the allowable value of 1.0 for 60 years of VY operation.

References

1. Letter Entergy to USNRC, "Vermont Yankee Nuclear Power Station, License No.DPR-28 (Docket No. 52-71), License Renewal Application, Amendment 34," BVY 08-002, January 30, 2008.2. Structural Integrity Associates Calculation No. VY-19Q-301, Revision 0, "Design Inputs and Methodology for ASME Code Confirmatory Fatigue Usage Analysis of Reactor Feedwater Nozzle." 3. Structural Integrity Associates Calculation No. VY-1 9Q-302, Revision 0, "ASME Code Confirmatory Fatigue Evaluation of Reactor Feedwater Nozzle." 4. Structural Integrity Associates Calculation No. VY-19Q-303, Revision 0,"Feedwater Nozzle Environmental Fatigue Evaluation."

BVY 09-006 / Attachment 1 Page 4 of 5 5. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section III, Rules for Construction of Nuclear Power Plant Components, Division 1- Subsection NB, Class 1 Components, 1998 Edition including 2000 Addenda.6. NUREG-1 907, Volume 1 and Volume 2, "Safety Evaluation Report Related to the License Renewal of Vermont Yankee Power Station," dated May 2008.7. Structural Integrity Associates Calculation No. 0801038.304, Revision 0, "Design Inputs and Methodology for ASME Code Fatigue Usage Analysis of Reactor Recirculation Outlet Nozzle." 8. Structural Integrity Associates Calculation No. 0801038.305, Revision 0, "Stress Analysis of Reactor Recirculation Outlet Nozzle." 9. Structural Integrity Associates Calculation No. 0801038.306, Revision 0, "Fatigue Analysis of Recirculation Outlet Nozzle." 10. Structural Integrity Associates Calculation No. 0801038.301, Revision 0, "Design Inputs and Methodology for ASME Code Fatigue Usage Analysis of Reactor Core Spray Nozzle." 11. Structural Integrity Associates Calculation No. 0801038.302, Revision 0, "Stress Analysis of Reactor Core Spray Nozzle." 12. Structural Integrity Associates Calculation No. 0801038.303, Revision 0, "Fatigue Analysis of Core Spray Nozzle." 13. Structural Integrity Associates Calculation No. VY-16Q-304, Revision 0,"Recirculation Outlet Nozzle Finite Element Model." 14. Structural Integrity Associates Calculation No. VY-16Q-305, Revision 0,"Recirculation Outlet Nozzle Stress History Development for Nozzle Green Function." 15. Structural Integrity Associates Calculation No. VY-16Q-306, Revision 0, "Fatigue Analysis of Recirculation Outlet Nozzle." 16. Structural Integrity Associates Calculation No. VY-16Q-308, Revision 0, "Core Spray Nozzle Finite Element Model." 17. Structural Integrity Associates Calculation No. VY-16Q-309, Revision 1, "Core Spray Nozzle Green's Function." 18. Structural Integrity Associates Calculation No. VY-1 6Q-310, Revision 1, "Fatigue Analysis of Core Spray Nozzle."

BVY 09-006 / Attachment 1 Page 5 of 5 19. Entergy Design Input Record (DIR) Rev. 1, EC No. 1773, Revision 0,"Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07.20. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U.S. Nuclear Regulatory Commission, September 2005.21. NUREG/CR-6583 (ANL-97/18), "Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels," March 1998.22. NUREG/CR-5704 (ANL-98/31), "Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels," April 1999.