ML12338A236

Issuance of Amendment Change to Inspection Frequency for Steam Dryer

ML12338A236
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/19/2012
From:	Richard Guzman Plant Licensing Branch 1
To:	Entergy Nuclear Operations
Guzman R NRR/DORL/LPL1-1 301-415-1030
References
TAC ME7733
Download: ML12338A236 (15)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2012 Site Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION -ISSUANCE OF AMENDMENT TO RENEWED FACILITY OPERATING LICENSE RE: CHANGE TO INSPECTION FREQUENCY FOR STEAM DRYER (TAC NO. ME7733)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 252 to Renewed Facility Operating License (FOL) DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated December 22, 2011, as supplemented on October 3,2012.

The licensee's application for the proposed amendment would revise paragraph 3.S of the Renewed FOL to allow Boiling Water Reactor Vessel and Internals Project (BWRVIP}-139-A, "BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines," to be the basis for future steam dryer monitoring and inspections on an inspection interval of at least every third refueling outage.

A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

~~

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. Amendment No. 252 to License No. DPR-28

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 252 License No. DPR-28

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee) dated December 22,2011, as supplemented by letter dated October 3,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2.

Accordingly, the license is amended as indicated in the attachment to this license amendment, and paragraph 3.8 of the Renewed Facility Operating License No. DPR-28 is hereby amended to read as follows:

(8)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

Further, the license is amended as indicated in the attachment to this license amendment, and paragraph 3.8 of the Renewed Facility Operating License No.

DPR-28 is hereby amended to read as follows:

S.

Steam Dryer License Condition Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. shall perform and implement the continuous parameter monitoring, moisture content monitoring, and visual inspections of the steam dryer described in 8WRVIP-139-A, Final Report, dated July 2009, with the additional requirements included in the license condition specified herein.

1. The licensee shall inspect the steam dryer during refueling outage (RFO) 31. If the steam dryer inspection results from RFO 31 demonstrate that (a) any new cracking due to either fatigue or intergranular stress-corrosion cracking (IGSCC) is not significant (Le.,

is evaluated to be acceptable without repair), and (b) all previously identified indications (including the new indication identified in RFO

27) show no crack growth requiring repair, the licensee shall initiate a program to perform steam dryer inspections at least every third refueling outage.

2. If the steam dryer inspection during RFO 31 or any subsequent steam dryer inspection reveals new cracking due to either fatigue or IGSCC that requires repair, or any growth of existing cracking that requires repair, the licensee shall inspect the steam dryer during each refueling outage.

3. The steam dryer inspection during RFO 31 and all future steam dryer inspections shall meet the guidelines in 8WRVIP-139-A with the exception of the inspection interval specified in 8WRVIP-139-A. The results of the steam dryer inspection beginning with RFO 31 and continuing for all future inspections shall be submitted to the NRC within 6 months of each steam dryer inspection completion.

4. This license condition shall continue for the full term of the period of extended operation unless duly amended.

- 3

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION George A. Wilson, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License Date of Issuance: December 19. 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 252 RENEWED FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Renewed Facility Operating License with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Page 3 Page 3 Page 14 Page 14

- 3 D. Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any Byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components.

E. Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. Maximum Power Level Entergy Nuclear Operations, Inc. is authorized to operate the facility at reactor core power levels not to exceed 1912 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252 are hereby incorporated in the license. Entergy Nuclear Operations, Inc. shall operate the facility in accordance with the Technical Specifications.

C. Reports Entergy Nuclear Operations, Inc. shall make reports in accordance with the requirements of the Technical Specifications.

D. This paragraph deleted by Amendment No. 226.

E. Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27, 1973, the following conditions for the protection of the environment are incorporated herein:

1.

This paragraph deleted by Amendment No. 206, October 22, 2001.

2.

This paragraph deleted by Amendment 131, 10107/91.

Renewed Facility Operating License No. DPR-28 Amendment No. 254, 252

- 14 S.

Steam Dryer License Condition Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc.

shall perform and implement the continuous parameter monitoring, moisture content monitoring, and visual inspections of the steam dryer described in BWRVIP-139-A, Final Report, dated July 2009, with the additional requirements included in the license condition specified herein.

1. The licensee shall inspect the steam dryer during refueling outage (RFO) 31.

If the steam dryer inspection results from RFO 31 demonstrate that (a) any new cracking due to either fatigue or intergranular stress-corrosion cracking (lGSCC) is not significant (Le., is evaluated to be acceptable without repair),

and (b) all previously identified indications (including the new indication identified in RFO 27) show no crack growth requiring repair, the licensee shall initiate a program to perform steam dryer inspections at least every third refueling outage.

2. If the steam dryer inspection during RFO 31 or any subsequent steam dryer inspection reveals new cracking due to either fatigue or IGSCC that requires repair, or any growth of existing cracking that requires repair, the licensee shall inspect the steam dryer during each refueling outage.

3. The steam dryer inspection during RFO 31 and all future steam dryer inspections shall meet the guidelines in BWRVIP-139-A with the exception of the inspection interval specified in BWRVI P-139-A. The results of the steam dryer inspection beginning with RFO 31 and continuing for all future inspections shall be submitted to the NRC within 6 months of each steam dryer inspection completion.

4. This license condition shall continue for the full term of the period of extended operation unless duly amended.

4.

This renewed operating license is effective as of the date of issuance and shall expire at midnight on March 21, 2032.

FOR THE NUCLEAR REGULATORY COMMISSION IRA!

Eric J. Leeds, Director Office of Nuclear Reactor Regulation

Enclosures:

Appendix A - Technical Specifications Date of Issuance: March 21, 2011 Renewed Facility Operating License No. DPR-28 Amendment No. 252

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 252 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-28 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.

VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

1.0 INTRODUCTION

By letter dated December 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11363A049), as supplemented by letter dated October 3, 2012 (ADAMS Accession No. ML12284A478), Entergy Nuclear Operations, Inc. (the licensee),

submitted a license amendment request to change a license condition for periodic inspection of the steam dryer at Vermont Yankee Nuclear Power Station (VY). Specifically, the amendment would revise the Operating License Condition (LC) 3.S. to allow Boiling Water Reactor Vessel and Internals Project (BWRVIP)-139-A, "BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines," to be the basis for future steam dryer monitoring and inspections on an inspection interval of at least every third refueling outage.

The supplemental letter dated October 3, 2012, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no Significant hazards consideration determination as published in the Federal Register on April 3, 2012 (77 FR 20073).

2.0 REGULATORY EVALUATION

The regulatory requirements and guidance which the NRC staff considered in assessing the proposed LC change are as follows:

Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix A. includes the general design criterion (GDC) for nuclear power plants. General Design Criterion (GDC) 1, "Quality standards and records," requires, in part, that "structures, systems and components important for safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Where generally recognized codes and standards are used, they shall be identified and evaluated to determine

- 2 their applicability, adequacy, and sufficiency, and shall be supplemented or modified as necessary to assure a quality product in keeping with the required safety function."

Boiling Water Reactor (BWR) Vessel and Internals Project (BWRVIP) Technical Report (TR)

BWRVIP-139-A TR, "BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines," provides inspection guidelines that the NRC staff finds acceptable for use as part of the licensee's aging management program for the steam dryer.

General Electric (GE) Nuclear Energy Service Information Letter (SIL) 644, "BWRl3 steam dryer failure," issued on August 21,2002, and supplemented on September 5,2003, provides monitoring and inspection recommendations for BWR plants that are operating, or plan to operate, at power levels greater than the original license thermal power.

3.0 TECHNICAL EVALUATION

3.1 Background

On December 22, 2011, the licensee requested a license amendment that included an LC change requesting the usage of the inspection requirements allowed by the BWRVI P-139-A TR for the steam dryer at the VY nuclear power plant. LC 3.S was imposed on VY by Atomic Safety and Licensing Board Order LBP-08-25, dated November 24, 2008, notwithstanding any other provisions of the license, as issued in the Vermont Yankee renewed license on March 21, 2011 (ADAMS Accession No. ML092110050). Previously, on March 2,2006, the NRC staff issued License Amendment No. 229 which allowed VY to operate at extended power uprate (EPU) conditions (ADAMS Accession No. ML060050022).

LC 3.S requires that the licensee continue to perform and implement continuous parameter monitoring, moisture carryover (MCO) monitoring, and visual inspections of the steam dryer at intervals specified in GE SIL 644, Revision 2, which requires steam dryer re-inspection at every second RFO cycle. LC 3.S requires that the inspections, continuous parameter monitoring, and monitoring of MCO content shall continue for the full term of the period of extended operation unless this provision is duly amended.

In addition to GE SIL 644, Revision 2, BWRVIP-139-A TR provides inspection guidelines which are to be used by the licensee as part of its aging management program for the steam dryer.

BWRVIP-139-A TR allows subsequent steam dryer inspections at every seven RFO cycles (based on 18-month cycle). The scope of the steam dryer inspections would include all key locations and 10 percent sampling of other locations slated in the baseline inspection guidelines.

3.2 Licensee Evaluation Consistent with the provisions in GE SIL 644, Revision 2, as required by the current LC 3.S, the licensee performed baseline inspections of the steam dryer during the three consecutive RFOs beginning in 2007: RFO 26, followed by RFOs 27 and 28. The licensee stated that visual inspections of the accessible areas in the steam dryer at VY did not identify any unacceptable fatigue induced structural flaws; however, it observed IGSCC. Based on these inspection results, in the December 22, 2011, submittal, the licensee proposed to comply with guidelines specified in Section 5.3.4 of the BWRVIP-139-A TR, which allows subsequent steam dryer inspections at every seven RFO cycles (based on an 18-month cycle). The scope of the steam

-3 dryer inspections would include all key locations and 10 percent sampling of other locations slated in the baseline inspection guidelines.

The licensee's proposal for implementing future steam dryer inspections per the BWRVIP-139-A TR in lieu of GE Sil 644, Revision 2, is based on the following technical justification:

(1) successive inspections confirmed that IGSCC crack growth was arrested and no fatigue cracking was observed; (2) the licensee is meeting the provision specified in Appendix D in GE Sil 644, Revision 2, which sets a limit for the MCO for EPU operating conditions (the licensee established a conservative MCO limit which provides extra margin with respect to the steam dryer's integrity); and (3) the licensee is monitoring changes in steam line pressure, feedwater flow, reactor water level, and feedwater temperature. The licensee considers these measures to be consistent with the BWRVIP-139-A TR guidelines and, therefore, would satisfy the proposed lC 3.S.

3.3

NRC Staff Evaluation

The NRC staff reviewed the December 22,2011, submittal from the licensee, and determined that additional review of the inspection results of the steam dryer that were obtained during RFOs 26, 27 and 28 was necessary. On May 9, 2012, the NRC staff reviewed the proprietary General Electric-Hitachi (GEH) inspection results and its evaluation of the steam dryer at a vendor facility. The NRC staff noted that new cracks were identified during the RFO 26 and 27 inspections, and GEH's disposition indicated that these cracks were to be monitored during the next RFO inspections. The presence of new cracks that were identified during the RFO 26 and 27 inspections prompted the NRC staff to issue a request for additional information (RAI) on May 31, 2012 (ADAMS Accession No. Ml121520304). The NRC staff requested that the licensee provide: (1) the location of the indications - grouped by regions of the steam dryer; (2) distribution of the indications, i.e., random, concentrated at high stress locations, or in the heat affected zone (HAZ); (3) length of the indications; (4) characterization of the indications (i.e., likely damage mechanism, suspected rate of growth, and consequences of failure); and (5) engineering disposition of the relevant indications.

By letter dated October 3,2012, in response to the NRC staffs RAI, the licensee provided a technical justification for a revised request of the re-inspection frequency which would require steam dryer inspections at every three RFO cycles. This new proposal would replace the current re-inspection frequency required by lC 3.S of inspections at every second RFO cycle.

The licensee further stated that it performed pre-emptive modifications on the steam dryer to preclude the fatigue failures that have been experienced at EPU conditions at other nuclear power plants. Post-EPU inspection results of the VY steam dryer, conducted during RFOs 26, 27 and 28, were used to justify the proposed modification of the inspection frequency. The following paragraphs address the licensee's evaluation of the aforementioned issues followed by the NRC staff evaluation.

As addressed above, the preemptive modifications include installation of new hardware with low carbon stainless steel base material (304U316l) and low-carbon stainless steel weld material (308l), which are more resistant to IGSCC than non-low-carbon stainless steel base metal/weld

-4 metal. The modifications were performed on the following items: (1) vertical and horizontal plates on each of the two outer hoods; (2) four diagonal braces inside the outer hoods (removal); (3) horizontal cover plates adjacent to steam outlet nozzles; (4) the tie bars with support gussets on the outer tie bars (replacement by eight tie bars with support gussets); (5) behind the li'fting lug near the outer plenum vertical welds; and (6) some weld locations with crack indication (repair). The licensee asserted that these modifications resulted in: (1) lowering of actual stresses through uniform load distribution; (2) reduction in IGSCC susceptibility; (3) increased structural integrity of the steam dryer; and (4) minimization in the generation of loose parts.

Prior to EPU operation during the RFO 24 inspections, cracks were observed in the HAZ area in the drain channel (OC-V4C) weld of the VY steam dryer, and these cracks were identified as IGSCC. No discernible change in the crack growth was observed in the drain channel during the RFO 25 and 26 steam dryer inspections. The steam dryer inspection conducted with higher quality inspection tooling during RFO 27 identified new flaws and a slight increase in crack growth. However, the subsequent inspection during RFO 28 exhibited a horizontal indication in the drain channel to the support ring weld. Review of the previous visual inspection videos indicated that this was a pre-existing crack. The flaw in the drain channel welds was limiting, and, therefore, the licensee performed re-inspection of the drain channel during the RFO 29 inspection (only the drain channel was inspected) which revealed that the cracks did not grow.

Based on this observation, the licensee concluded that the existing cracks will not have the potential to grow in the drain channel resulting in the creation of loose parts.

Other parts of the steam dryer that exhibited cracks identified during the RFO 27 and 28 inspections were: (1) lifting lugs; (2) dryer leveling screws; (3) the steam dam; and (4) the unit end plate. The indications were evaluated by GEH and the licensee, and they were accepted for continued operation with no weld repair.

The following items provide the technical bases for the licensee's conclusion:

(1) Preemptive modifications were performed by using stainless steel base and weld metals that are resistant to IGSCC. These modifications were implemented to minimize the occurrence of fatigue as a result of EPU operation; (2) Five successive inspections during RFOs 24,25,26,27, and 28 and an additional inspection of the drain channel weld during RFO 29 showed that IGSCC crack growth was arrested. Thus far, the inspection criteria addressed in GE SIL 644, Revision 2, and the BWRVIP-139-A TR has been met. Additionally, no fatigue-induced flaws were observed after the implementation of the EPU; (3) No through-wall cracking nor any structural damage was observed; (4) The existing flaws would not cause any detrimental effect on the functionality and structural integrity of the steam dryer; (5) Acoustic monitoring of the main steam system was performed during and after commencement of EPU operation, and no detrimental effect due to acoustic issues has been identified; and

- 5 (6) Monitoring of the main steam system MCO is performed, and to date, no abnormal moisture carryover has been noted.

Based on the aforementioned technical bases, the licensee proposes that performing steam dryer inspections every third RFO in lieu of every second RFO provides an adequate level of safety and quality. Based on its steam dryer evaluation, the licensee stated that it will not perform an inspection of the steam dryer during RFO 30. However, it will perform a baseline inspection during RFO 31 in accordance with the BWRVIP-139-A TR guidance. Thereafter, the licensee proposes to perform steam dryer re-inspections every third RFO cycle in lieu of every second RFO cycle. Hence, the licensee requested that the existing LC 3.S be changed to specify steam dryer inspections every third RFO. The NRC staff reviewed the licensee's technical bases submitted on October 3,2012, and the following paragraphs describe its evaluation.

The successive steam dryer inspections indicated that the majority of cracks that were identified in the drain channel weld in the steam dryer were due to IGSCC. These cracks were characterized as IGSCC due to their appearance (intermittent and jagged), and their location near HAZ areas. The licensee determined that these cracks originated at cold worked areas due to grinding. The licensee also observed cracking in lifting lugs, dryer leveling screws, the steam dam plate, and a unit end plate. For new cracks found during steam dryer inspections, the NRC staff verified that GEH and the licensee performed evaluations to support continued operation of the steam dryer without repair. The visual inspections conducted during RFOs 28 and 29 confirmed that all previously identified indications have not grown, further supporting the GEH and licensee evaluations.

The licensee performed preemptive modifications in which it used IGSCC resistant austenitic stainless steel base and weld metals, which reduce the possibility of IGSCC occurrence. Since no IGSCC has been observed in the modified areas, it can be concluded that thus far, the aging degradation due to IGSCC has been adequately contained in these areas.

Historically, it was recognized that implementation of an EPU might result in cracking due to fatigue in steam dryer components. The fact that no fatigue crack has been found during these inspections indicates that thus far, there is no active aging degradation due to fatigue in the VY steam dryer. Hence, the NRC staff agrees with the licensee that the preemptive modifications that were performed on the steam dryer reduced the stresses through a more uniform load distribution.

The absence of IGSCC crack growth and any new fatigue cracking after the EPU implementation in May 2006 provides technical justification for the licensee to skip a steam dryer inspection during RFO 30. Based on steam dryer inspection results and analyses over several operating cycles, the licensee will not inspect the steam dryer during RFO 30, but will inspect the steam dryer during RFO 31. Further, based on the monitoring of all previously identified indications since 2004 during RFOs 24,25,26,27,28, and 29, which showed no crack growth, the NRC staff concludes that the proposed performance of steam dryer inspections at every third RFO cycle is acceptable with a condition requiring the licensee to inspect the steam dryer during RFO 31 and to provide all future inspection results, including those from RFO 31, demonstrating that the inspection results and evaluations are consistent with those from RFO 24 to RFO 29.

- 6 As a replacement for the current LC 3.S, issued in VY License Amendment 229, the licensee shall implement the following revised License Condition 3.S. for the full term of the period of extended operation unless duly amended:

S. Steam Dryer License Condition Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. shall perform and implement the continuous parameter monitoring, moisture content monitoring, and visual inspections of the steam dryer described in BWRVIP-139-A, Final Report, dated July 2009, with the additional requirements included in the license condition specified herein.

1.

The licensee shall inspect the steam dryer during refueling outage (RFO) 31. If the steam dryer inspection results from RFO 31 demonstrate that (a) any new cracking due to either fatigue or intergranular stress-corrosion cracking (lGSCC) is not significant (i.e., is evaluated to be acceptable without repair), and (b) all previously identified indications (including the new indication identified in RFO

27) show no crack growth requiring repair, the licensee shall initiate a program to perform steam dryer inspections at least every third refueling outage.

2.

If the steam dryer inspection during RFO 31 or any subsequent steam dryer inspection reveals new cracking due to either fatigue or IGSCC that requires repair, or any growth of existing cracking that requires repair, the licensee shall inspect the steam dryer during each refueling outage.

3.

The steam dryer inspection during RFO 31 and all future steam dryer inspections shall meet the guidelines in BWRVI P-139-A with the exception of the inspection interval specified in BWRVI P-139-A. The results of the steam dryer inspection beginning with RFO 31 and continuing for all future inspections shall be submitted to the NRC within 6 months of each steam dryer inspection completion.

4.

This license condition shall continue for the full term of the period of extended operation unless duly amended.

The steam dryer inspection during RFO 31 will provide information on steam dryer performance over two operating cycles in support of an extension of the steam dryer inspection interval to every third RFO. If the steam dryer inspection during RFO 31 or a later steam dryer inspection every third RFO identifies unacceptable indications, the above license condition will require the licensee to inspect the steam dryer every RFO to determine the cause and rate of growth of the unacceptable indications until the licensee can develop justification to extend the inspection interval beyond each RFO. Based on that evaluation, the licensee may submit a future license amendment to extend the steam dryer inspection interval beyond every RFO.

- 7

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Vermont State official was notified of the proposed issuance of the amendment. The State official provided comments from the Vermont Department of Public Service (ADAMS Accession No. ML12352A130), and the comments were considered in the staff's review of the licensee's application. The NRC staff's response can be viewed in ADAMS (Accession No. ML123540455).

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in amounts, and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (77 FR 20073). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b}, no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: G. Cheruvenki, NRR/DE/EVIB S. Sheng, NRRIDE/EVIB Date: December 19,2012

December 19, 2012 Vice President, Operations Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION -ISSUANCE OF AMENDMENT TO RENEWED FACILITY OPERATING LICENSE RE: CHANGE TO INSPECTION FREQUENCY FOR STEAM DRYER (TAC NO. ME7733)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 252 to Renewed Facility Operating License (FOL) DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated December 22,2011, as supplemented on October 3,2012.

The licensee's application for the proposed amendment would revise paragraph 3. S of the Renewed FOL to allow Boiling Water Reactor Vessel and Internals Project (BWRVIP)-139-A, "BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines," to be the basis for future steam dryer monitoring and inspections on an inspection interval of at least every third refueling outage.

A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA!

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. Amendment No. 252 to License No. DPR-28

2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsRgn1 MailCenter RidsNrrDorlLpl1-1 Resource RidsNrrLAKGoldstein RidsNrrDeEvib Resource RidsNrrDorlDpr Resource R. Bellamy, RI RidsNrrPMVermontYankee RidsNrrDirsltsb Resource G. Cheruvenki, NRR RidsOgcRp Resource RidsAcrsAcnw_MailCenter Resource S. Sheng, NRR Accession No. ML12338A236

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