ML050960126

Vermont Yankee RAI - Extended Power Uprate

ML050960126
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	04/14/2005
From:	Richard Ennis NRC/NRR/DLPM/LPD1
To:	Kansler M Entergy Nuclear Operations
Ennis R, NRR/DLPM, 415-1420
References
TAC MC0761
Download: ML050960126 (12)

Text

April 14, 2005 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - EXTENDED POWER UPRATE, VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. MC0761)

Dear Mr. Kansler:

By letter dated September 10, 2003, as supplemented on October 1, and October 28 (2 letters),

2003, January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters), October 5, October 7 (2 letters), December 8, and December 9, 2004, and February 24, March 10, March 24, March 31, and April 5, 2005, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc., submitted a proposed license amendment to the U.S. Nuclear Regulatory Commission (NRC) for the Vermont Yankee Nuclear Power Station (VYNPS). The proposed amendment, Technical Specification Proposed Change No. 263, Extended Power Uprate would allow an increase in the maximum authorized power level for VYNPS from 1593 megawatts thermal (MWT) to 1912 MWT.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure.

We request that the additional information be provided by April 22, 2005. The response timeframe was discussed with Ms. Ronda Daflucas of your staff on April 12, 2005. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.

Sincerely,

/RA/

Richard B. Ennis, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosure:

As stated cc w/encl: See next page

Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - EXTENDED POWER UPRATE, VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. MC0761)

Dear Mr. Kansler:

By letter dated September 10, 2003, as supplemented on October 1, and October 28 (2 letters),

2003, January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters), October 5, October 7 (2 letters), December 8, and December 9, 2004, and February 24, March 10, March 24, March 31, and April 5, 2005, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc., submitted a proposed license amendment to the U.S. Nuclear Regulatory Commission (NRC) for the Vermont Yankee Nuclear Power Station (VYNPS). The proposed amendment, Technical Specification Proposed Change No. 263, Extended Power Uprate would allow an increase in the maximum authorized power level for VYNPS from 1593 megawatts thermal (MWT) to 1912 MWT.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure.

We request that the additional information be provided by April 22, 2005. The response timeframe was discussed with Ms. Ronda Daflucas of your staff on April 12, 2005. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.

Sincerely,

/RA/

Richard B. Ennis, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC TChan, EMCB-B JCai, IROB-B HWalker, SPSB-C PDI-2 Reading RDavis, EMCB-B JBongarra, IROB-B MHart, SPSB-C DRoberts LLund, EMCB-C AKugler, RLEP-C FAkstulewicz, SRXB-A REnnis KParczewski, EMCB-C SImboden, RLEP-C MRazzaque, SRXB-A JStang KManoly, EMEB-B SJones, SPLB-A LWard, SRXB-A CAnderson, RGN I CWu, EMEB-B DReddy, SPLB-A DTerao, EMEB-A EMarinos, EEIB-A TScarbrough, EMEB-A SWeerakkody, SPLB-B VBucci, OIG HGarg, EEIB-A DThatcher, IPSB-A RGallucci, SPLB-B BPoole,OGC RJenkins, EEIB-B RPettis, IPSB-A DHarrison, SPSB-A ZAbdullahi, SRXB-A NTrehan, EEIB-B SKlementowicz, IPSB-B MStutzke, SPSB-A JTatum, SPLB-A MMitchell, EMCB-A RPedersen, IPSB-B RDennig, SPSB-C CRaynor BElliot, EMCB-A DTrimble, IROB-B RLobel, SPSB-C ACCESSION NO.: ML050960126 OFFICE PDI-2/PM PDI-2/LA OGC PDI-2/SC NAME REnnis CRaynor BPoole DRoberts DATE 4/12/05 4/12/05 4/13/05 4/14/05 OFFICIAL RECORD COPY

Vermont Yankee Nuclear Power Station cc:

Regional Administrator, Region I Ms. Carla A. White, RRPT, CHP U. S. Nuclear Regulatory Commission Radiological Health 475 Allendale Road Vermont Department of Health King of Prussia, PA 19406-1415 P.O. Box 70, Drawer #43 108 Cherry Street Mr. David R. Lewis Burlington, VT 05402-0070 Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W. Mr. James M. DeVincentis Washington, DC 20037-1128 Manager, Licensing Vermont Yankee Nuclear Power Station Ms. Christine S. Salembier, Commissioner P.O. Box 0500 Vermont Department of Public Service 185 Old Ferry Road 112 State Street Brattleboro, VT 05302-0500 Montpelier, VT 05620-2601 Resident Inspector Mr. Michael H. Dworkin, Chairman Vermont Yankee Nuclear Power Station Public Service Board U. S. Nuclear Regulatory Commission State of Vermont P.O. Box 176 112 State Street Vernon, VT 05354 Montpelier, VT 05620-2701 Director, Massachusetts Emergency Chairman, Board of Selectmen Management Agency Town of Vernon ATTN: James Muckerheide P.O. Box 116 400 Worcester Rd.

Vernon, VT 05354-0116 Framingham, MA 01702-5399 Operating Experience Coordinator Jonathan M. Block, Esq.

Vermont Yankee Nuclear Power Station Main Street 320 Governor Hunt Road P.O. Box 566 Vernon, VT 05354 Putney, VT 05346-0566 G. Dana Bisbee, Esq. Mr. John F. McCann Deputy Attorney General Director, Nuclear Safety Assurance 33 Capitol Street Entergy Nuclear Operations, Inc.

Concord, NH 03301-6937 440 Hamilton Avenue White Plains, NY 10601 Chief, Safety Unit Office of the Attorney General Mr. Gary J. Taylor One Ashburton Place, 19th Floor Chief Executive Officer Boston, MA 02108 Entergy Operations 1340 Echelon Parkway Ms. Deborah B. Katz Jackson, MS 39213 Box 83 Shelburne Falls, MA 01370

Vermont Yankee Nuclear Power Station cc:

Mr. John T. Herron Mr. Ronald Toole Sr. VP and Chief Operating Officer 1282 Valley of Lakes Entergy Nuclear Operations, Inc. Box R-10 440 Hamilton Avenue Hazelton, PA 18202 White Plains, NY 10601 Ms. Stacey M. Lousteau Mr. Danny L. Pace Treasury Department Vice President, Engineering Entergy Services, Inc.

Entergy Nuclear Operations, Inc. 639 Loyola Avenue 440 Hamilton Avenue New Orleans, LA 70113 White Plains, NY 10601 Mr. Raymond Shadis Mr. Brian OGrady New England Coalition Vice President, Operations Support Post Office Box 98 Entergy Nuclear Operations, Inc. Edgecomb, ME 04556 440 Hamilton Avenue White Plains, NY 10601 Mr. James P. Matteau Executive Director Mr. Michael J. Colomb Windham Regional Commission Director of Oversight 139 Main Street, Suite 505 Entergy Nuclear Operations, Inc. Brattleboro, VT 05301 440 Hamilton Avenue White Plains, NY 10601 Mr. William K. Sherman Vermont Department of Public Service Mr. John M. Fulton 112 State Street Assistant General Counsel Drawer 20 Entergy Nuclear Operations, Inc. Montpelier, VT 05620-2601 440 Hamilton Avenue White Plains, NY 10601 Mr. Jay K. Thayer Site Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Mr. Kenneth L. Graesser 38832 N. Ashley Drive Lake Villa, IL 60046 Mr. James Sniezek 5486 Nithsdale Drive Salisbury, MD 21801

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT EXTENDED POWER UPRATE VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated September 10, 2003, as supplemented on October 1, and October 28 (2 letters),

2003, January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters), October 5, October 7 (2 letters), December 8, and December 9, 2004, and February 24, March 10, March 24, March 31, and April 5, 2005, (References 1 through 28), Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy or the licensee), submitted a proposed license amendment to the U.S. Nuclear Regulatory Commission (NRC) for the Vermont Yankee Nuclear Power Station (VYNPS). The proposed amendment, Technical Specification Proposed Change No. 263, Extended Power Uprate would allow an increase in the maximum authorized power level for VYNPS from 1593 megawatts thermal (MWT) to 1912 MWT.

The NRC staff is reviewing your Extended Power Uprate (EPU) amendment request and has determined that additional information is required to complete the review. The specific information requested is addressed below.

Plant Systems Branch (SPLB)

Balance of Plant Section (SPLB-A)

Reviewer: Devender Reddy

14. Spent Fuel Pool (SFP) Cooling and Cleanup System (Safety Evaluation (SE) Template Section 2.5.3.1)

The licensee's response to request for additional information (RAI) SPLB-A-11, in the supplement dated February 24, 2005, provided information that indicates that the plant licensing basis related to the standby fuel pool cooling subsystem (SFPCS) will change following implementation of the proposed EPU. In particular, Revision 18 of the Updated Final Safety Analysis Report (UFSAR) on page 10.5-9 it states: These

[SFPCS] heat exchangers are each sized to maintain the fuel pool water temperature below 150 EF after a normal refueling. Considering one train (one heat exchanger and one pump), this heat removal capability encompasses the normal maximum heat load from completely filling the pool with 3,353 spent fuel assemblies from the last normal discharge. The combined heat removal capability considering both trains (two heat exchangers and two pumps) operating encompasses a full core discharge heat load completely filling the pool with 3,353 spent fuel assemblies. This provides sufficient heat removal capacity to preclude any impact on plant operation due to insufficient spent fuel pool cooling. Additionally, on page 10.5-12 of the UFSAR it states: At six Enclosure

days decay, a single train of SFPCS is able to remove the decay heat load. For a full-core discharge (abnormal operation)....two trains of SFPCS can remove the decay heat load at 10 days.... These statements are also supported by the information provided in Table 10.5.1, "Heat Removal Capacities," Table 10.5.3, "Comparison of Heat Loads to Heat Removal Capacities with SFP at Capacity," and Table 10.5.4, "Fuel Pool Cooling and Demineralizer System - System Specifications." Based on a review of the February 24, 2005, response to RAI SPLB-A-11, VYNPS will not be able to satisfy the current plant licensing basis as described in the UFSAR (and referred to above) following the proposed EPU. Please describe the changes that are being made to the plant licensing basis in this regard, explain why NRC review and approval is not required pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59 requirements, and provide a markup of UFSAR Sections 10.5.5 and 10.5.6 and UFSAR Tables 10.5.1, 10.5.3 and 10.5.4, that reflect the changes that are being made.

15. Station Service Water System (SE Template Section 2.5.3.2)

The information that was provided in several supplements (e.g., response to RAI questions SPLB-A-9 and SPSB-C-29 in the supplement dated July 30, 2004) indicates that the maximum design-basis service water temperature limit is 85 EF, and this is the maximum temperature that is assumed in the accident analyses and decay heat removal calculations. However, UFSAR Section 10.6.5 describes a higher temperature limit of 88 EF under certain conditions. Explain how the evaluation supporting the UFSAR service water temperature limit of 88 EF was assessed for validity to EPU operation.

16. Reactor Auxiliary Cooling Water Systems (SE Template Section 2.5.3.3)

The cooling function of the alternate cooling system (ACS) is relied upon in the event that the service water system becomes unavailable due to a failure of the Vernon Dam, or due to a fire or flooding in the intake structure. With respect to the response to RAI SPLB-A-9(a), in the supplement dated July 30, 2004, additional information is needed in order to fully demonstrate the capability of the ACS to perform its function for EPU conditions:

a. Describe the extent of changes in the assumptions and methodology used to evaluate the ACS performance at EPU conditions relative to the existing design basis analysis.

b. Confirm that the limiting parameters that were originally assumed relative to cooling tower performance (temperature, humidity, wind, etc.) continue to be worst-case based on trending of the meteorological conditions that have existed at VYNPS.

17. Condensate and Feedwater System (CFS)

(SE Template Section 2.5.4.4)

Given the reduction in margin of the CFS for EPU conditions (e.g., use of three reactor feedwater pumps (RFPs) rather than two), explain what impact the EPU will have on the reliability of the CFS.

18. CFS (SE Template Section 2.5.4.4)

Describe the extent of post-modification testing that will be completed to demonstrate acceptable performance for the reactor recirculation system runback modification and the RFP suction pressure trip modification.

19. Emergency Diesel Engine Fuel Oil Storage and Transfer System (SE Template Section 2.5.6.1)

Explain how the limiting emergency diesel generator fuel oil consumption rate and duration that were established for the current licensed power level will remain bounding for EPU operation.

20. Power Ascension and Testing (SE Template Section 2.12)

The licensees response to RAI SPLB-A-10, in the supplement dated February 24, 2005, indicated that analyses of anticipated operational occurrences have been performed by General Electric for VYNPS using the NRC-approved ODYN code, which models the direct-cycle boiling-water reactor, including the turbine-generator system and the feedwater system functions. Additional information is required to explain in detail how the balance-of-plant (BOP) transient response to postulated events and anticipated operational occurrences was evaluated and determined, including:

a. a discussion of the BOP transient response criteria that are important for assuring reactor safety and for minimizing challenges to plant safety systems;

b. the nature, capability, applicability, accuracy, and sensitivity of the analytical modeling and methods that were used, including limitations and restrictions that apply, and sensitivities and uncertainties associated with extrapolating the use of these methods to encompass EPU conditions;

c. measures that have been taken to confirm and assure that the analytical models and methods accurately represent the BOP transient response and a description of how well predicted performance compares with actual performance, including to what extent analytical models and methods have been updated and corrected to reflect VYNPS behavior following plant transients that have occurred, the extent that BOP features are actually modeled and an explanation for why this is sufficient, and consideration of plant modifications and setpoint adjustments that have been made subsequent to plant transients that have occurred such that the effects of these changes are not represented by the existing plant response data;

d. the impact of plant modifications, setpoint adjustments and parameter changes that are planned on the validity, accuracy, sensitivity, and uncertainty of the analytical methods being used;

e. a comparison of the analytical results (as adjusted to account for uncertainties in the analytical modeling and analyses) to the acceptance criteria that have been established for BOP transient performance; and

f. measures that are included in the power ascension test program that will confirm the validity, accuracy, and sensitivity of the analytical results.

21. Power Ascension and Testing (SE Template Section 2.12)

As discussed in the licensees response to RAI SPLB-A-10, in the supplement dated February 24, 2005, the performance criteria that were established for the main steam isolation valve closure event and the turbine load reject and turbine trip without bypass both included: a) reactor pressure shall be maintained below 1230 psig; and b) maximum reactor pressure should be 35 psi below the first safety valve setpoint.

Additional information is required to demonstrate that these criteria will continue to be satisfied for EPU operation, including a discussion of how these determinations were made, uncertainties that are inherent in the analyses that were completed, and how these uncertainties were accounted for in demonstrating acceptable results.

22. Power Ascension and Testing (SE Template Section 2.12)

The licensee indicated in the response to RAI SPLB-A-10, in the supplement dated February 24, 2005, that: Operation of three RFPs at VYNPS during uprated conditions is addressed in FWLCS [feedwater level control system] operation to ensure the margins for vessel level overshoot are maintained. Additional information is required to explain specifically how FWLCS operation for uprated conditions will assure the margins for vessel level overshoot are maintained, including the need for any adjustments and how they were determined, and how FWLCS modeling and tuning for VYNPS differs from Dresden such that FWLCS performance in accordance with predictions is assured.

23. Internally Generated Missiles (SE Template Section 2.5.1.2.1)

The Vermont Yankee Notes - Matrix 5, for SE Section 2.5.1.2.1, Internally Generated Missiles (Outside Containment), in Supplement No. 4 dated January 31, 2004, indicate that the CPPU [constant pressure power uprate] will not result in increases in system pressures or configurations that would affect the impact of internally generated missiles on SSCs [structures, systems, and components] important to safety. The VYNPS CPPU does not result in any condition (system pressure increase or equipment overspeed) that could result in an increase in the generation of internally generated missiles. However, seemingly inconsistent with this conclusion, the high pressure feedwater heaters must be replaced in order to accommodate higher extraction

pressures and EPU operation will require increased feedwater system flow and possibly higher feedwater system pressure. Also, it is not clear to what extent transient conditions were considered in assessing the impact of the EPU on the likelihood and consequences of internally generated missiles. Please provide additional information to address these considerations. Note, if SSCs important to safety are not located within the missile strike zone of a particular missile hazard, specific analysis of these particular hazards are not required.

24. Liquid Waste Management Systems (SE Template Section 2.5.5.2)

The CPPU topical report indicates that review of liquid waste management systems should be completed on a plant-specific basis, and RS-001 includes additional review considerations that are not specifically recognized by the CPPU topical report. In order to fully address these considerations, additional information is required. Section 8.1 of the CPPU Safety Analysis Report (Attachment 6 to the application dated September 10, 2003) indicates that the total volume of liquid processed waste will not increase appreciably as a result of the EPU. Please explain how much liquid waste processing capacity is needed for EPU and how this determination was made relative to the VYNPS licensing basis criteria, and compare this capacity to the actual capacity that is available.

REFERENCES

1) Entergy letter (BVY 03-80) to NRC dated September 10, 2003, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Extended Power Uprate

2) Entergy letter (BVY 03-90) to NRC dated October 1, 2003, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 1, Extended Power Uprate -Technical Review Guidance

3) Entergy letter (BVY 03-95) to NRC dated October 28, 2003, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 2, Extended Power Uprate - Grid Impact Study

4) Entergy letter (BVY 03-98) to NRC dated October 28, 2003, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 3, Extended Power Uprate - Updated Information

5) Entergy letter (BVY 04-009) to NRC dated January 31, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 4, Extended Power Uprate - NRC Acceptance Review

6) Entergy letter (BVY 04-008) to NRC dated January 31, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 5, Extended Power Uprate - Response to Request for Additional Information

7) Entergy letter (BVY 04-025) to NRC dated March 4, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 6, Extended Power Uprate - Withholding Proprietary Information

8) Entergy letter (BVY 04-050) to NRC dated May 19, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 7, Extended Power Uprate - Confirmatory Results

9) Entergy letter (BVY 04-058) to NRC dated July 2, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 8, Extended Power Uprate - Response to Request for Additional Information

10) Entergy letter (BVY 04-071) to NRC dated July 27, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 9, Extended Power Uprate - Revised Containment Overpressure Envelope

11) Entergy letter (BVY 04-074) to NRC dated July 30, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 10, Extended Power Uprate - Response to Request for Additional Information

12) Entergy letter (BVY 04-081) to NRC dated August 12, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 11, Extended Power Uprate - Response to Request for Additional Information

13) Entergy letter (BVY 04-086) to NRC dated August 25, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 12, Extended Power Uprate - Revised Grid Impact Study

14) Entergy letter (BVY 04-097) to NRC dated September 14, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 13, Extended Power Uprate - Response to Steam Dryer Action Items

15) Entergy letter (BVY 04-098) to NRC dated September 15, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 14, Extended Power Uprate - Response to Request for Additional Information

16) Entergy letter (BVY 04-100) to NRC dated September 23, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 15, Extended Power Uprate - Response to Steam Dryer Action Item No. 2

17) Entergy letter (BVY 04-101) to NRC dated September 30, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 16, Extended Power Uprate - Additional Information Related to Request for Additional Information EMEB-B-5"

18) Entergy letter (BVY 04-107) to NRC dated September 30, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 17, Extended Power Uprate - Response to Request for Additional Information related to 10 CFR 50 Appendix R Timeline

19) Entergy letter (BVY 04-106) to NRC dated October 5, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 18, Extended Power Uprate - ECCS [emergency core cooling system] Pump Net Positive Suction Head Margin

20) Entergy letter (BVY 04-109) to NRC dated October 7, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 19, Extended Power Uprate - Initial Plant Test Program

21) Entergy letter (BVY 04-113) to NRC dated October 7, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 20, Extended Power Uprate - Meeting on Steam Dryer Analysis

22) Entergy letter (BVY 04-129) to NRC dated December 9, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 21, Extended Power Uprate - Steam Dryer Power Ascension Testing

23) Entergy letter (BVY 04-131) to NRC dated December 8, 2004, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 22, Extended Power Uprate - 10 CFR 50 Appendix R Timeline Verification

24) Entergy letter (BVY 05-017) to NRC dated February 24, 2005, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 23, Extended Power Uprate - Response to Request for Additional Information

25) Entergy letter (BVY 05-024) to NRC dated March 10, 2005, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 24, Extended Power Uprate - Response to Request for Additional Information

26) Entergy letter (BVY 05-030) to NRC dated March 24, 2005, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 25, Extended Power Uprate - Station Blackout and Appendix R Analyses

27) Entergy letter (BVY 05-034) to NRC dated March 31, 2005, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 26, Extended Power Uprate - Steam Dryer Analyses and Monitoring

28) Entergy letter (BVY 05-038) to NRC dated April 5, 2005, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263, Supplement No. 27, Extended Power Uprate - Dryer Acoustic Load Methodology Benchmark