BVY 06-018, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages

Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages

ML060590261
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	02/22/2006
From:	Thayer J Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
%dam200606, BVY 06-018, TAC MC0761
Download: ML060590261 (10)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Vermont Yankee P.O. Box 0500 A Entergy 185 Old Ferry Road Brattleboro, VT 05302-0500 Tel 802 257 5271 February 22, 2006 Docket No. 50-271 BVY 06-018 TAG No. MC0761 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 45 Extended Power Uprate - Revised Technical Specification PaqLis

Reference:

1) Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, License No. DPR-28 (Docket No. 50-271), Technical Specification Proposed Change No. 263, Extended Power Uprate," BVY 03-80, September 10, 2003

2) U.S. Nuclear Regulatory Commission (Richard B. Ennis) letter to Entergy (Michael Kansler), "Vermont Yankee Nuclear Power Station -

Issuance of Amendment 'Re: Implementation of ARTS/MELLLA (TAC No. MB8070), April 14, 20)04

3) Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, License No. DPR-28 (Docket No. 50-271), Technical Specification Proposed Change No. 257, Implementation of AFRTS/MELLLA at VYNPS, Supplemental Information and Proposed Allowable Value," BVY 03-115, December 11, 2003

4) Entergy letter to U.S. Nuclear Regulatory Commission, "Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263 - Supplement No. 44, Extended Power Uprate -

Revised License and Technical Specifications," BVY 06-001, January 10, 2006 This letter provides additional information regarding the application by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy) for a license amendment (Reference 1, as supplemented) to increase the maximum authorized powe'r level of the Vermont Yankee Nuclear Power Station (VYNPS) from 1593 megawatts thermal i:MWt) to 1912 MWt.

401

BVY 06-018 Docket No. 50-271 Page 2 of 3 In Reference 1, Entergy provided proposed changes to the VYNPS Technical Specifications (TS) to support the extended power uprate (EPU). Included among the TS changes were revisions to the Average Power Range Monitor (APRM) flow-biased flux scram trip settings in TS 2.1.A.1.a and Table 3.1.1 (the trip settings are the same in both TS sections). The trip settings that were provided in Reference I for this function of the reactor protection system are EPU analytical limits.

Subsequent to Entergy's submittal of its EPU license amendment request, the NRC granted in Reference 2 (License Amendment No. 219) its approval of a separate Entergy application to implement the APRM, Rod Block Monitor rs / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA) improvement program. Reference 2 accepted a revised setpoint methodology and the limited application of instrumentation allowable values (AVs) in the TS. Entergy's ARTS/MELLLA license amendment request (LAR) had indicated that the revised methodology and use of AVs for limiting safety system settings would also be applicable to the EPU LAR (Reference 3). to Reference 3 provided a copy of Entergy calculation VYC-0693A, "APRM Neutron Monitoring Trip Loops," which contains the APRM flow-biased flux scram trip setting AVs for ARTS/MELLLA, as well as the trip setting AVs for the same trip function for EPU. (See Table 10 on page 17 of 29.) The analytical limits in calculation VYC-0693A have been used as appropriate in the EPU safety analyses. However, through an administrative oversight, Entergy did not update the analytical limits set forth in Reference 1 with AVs in accordance with the changes implemented by Reference 3. Reference 4, which provided camera-ready, revised TS pages also did not change the subject APRM trip settings to AVs. To correct this oversight, Entergy is providing as Attachments 1 and 2 to this letter the marked-up TS pages and the re-typed TS pages, respectively, for the trip setting AVs applicable to the APRM flow-biased flux scram. Entergy apologizes for any inconvenience that this oversight may have caused.

This supplement to the license amendment request provides additional information regarding Entergy's application for a license amendment and does not change the scope or Conclusions in the original application, nor does it change Entergy's determination of no significant hazards consideration. There are no new regulatory commitments contained in this submittal.

If you have any questions or require additional information, please contact Mr. James DeVincentis at (802) 258-4236.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on February2(, 2006.

Sincerely, aye. hayer

(% Vice President Vermont Yankee Nuclear Power Station

BVY 06-018 Docket No. 50-271 Page 3 of 3 Attachments (2) cc: Mr. Samuel J. Collins (w/o attachment)

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Richard B. Ennis, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0 8 B1 Washington, DC 20555 USNRC Resident Inspector (w/o attachment)

Entergy Nuclear Vermont Yankee, Ll C P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601

BVY 06-018 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement NoD. 45 Extended Power Uprate Marked-Up Technical Specifications Pages Total number of pages in Attachment 1 l (excluding this cover sheet) is 3. l

VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEN SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEt CLADDING INTEGR1lY Applicability: Applicability:

Applies to the interrelated Applies to trip setting of the variable associated with fuel instruments and devices which are thermal behavior. provided to prevent the nuclear system safety limits from being exceeded.

Objective: Objective:

To establish limits below which the To define the level of the process integrity of the fuel cladding is variable at which automatic preserved. protective action is Initiated.

Specification: Specification:

A. Bundle Safety Limit (Reactor A. Trip Settings Pressure >800 psia and Core Flow

>10% of Rated) The limiting safety system trip settings shall be as specified When the reactor pressure is below:

>800 psia and the core flow is greater than 10% of rated: 1. Neutron Flux Trip Settings

1. A Minimum Critical Power Ratio a. APRM Flux Scram (MCPR) of less than 1.07 (1.09 Allowable Value .

for Single Loop Operation) (Run Mode) shall constitute violation of the Fuel Cladding Integrity When the mode switch is Safety Limit (FCISL). in the RUN position, the APRM flux scram Allowable Value shall be:

Twloop operatiK /

S5 0.33W+ 53.7 for 01 < W < .9%

5S 1.07W+ 30 for 30.91 < w 66.1l S* 0.55W+ .5% for 66.71 < W < 99.0%

With a m imum of 120.00% pow for W >

99.0%

NW.

Si e 1oop operation:

e~o)---In S 0.33W+ 51.1% for < W 39.1%

S 1.07W+ 22.2% for 39AW < W S 61.7%

SS 0.55W+ 54.3% for .7% < W < 119.4%

With a maximum of 1.0% power for W >

119.4%/

wwere:

S = setting in percent of rated thermal power (1912 MWt) I Amendment No. -t&, 4;, 44, 4, -4, 449-, 150 1594, A4-, 217 24 66

VYNPS TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS Required ACTIONS When Modes in Which Minimum Number Minimum Functions Must be Operati ng Operating Conditions Instrument For Operation Channels Per Are Not Trip Function Trip Settings Refuel (1) Startup(12) Run Trip System (2) Satisfied (3)

1. Mode Switch in Shutdown (5A-S1) x X 1 A

'C X

2. Manual Scram x X 1 A (5A-S3A/B)

3. IRM (7-41(A-F))

High Flux <120/125 x X 2 A INOP X X 2 A

4. APRM (APRM A-F)

High Flux X 2 A or B (flow bias) /

High Flux 2 A

<15% X X (reduced)

INOP X X 2(5) A or B

5. High Reactor <1055 psig X X 2 A Pressure

• (PT-2-3-55(A-D)

(M)

Amendment No. ;4., 44, 4;4, 44, 44,

46 i , -, O4, -94, 44, .4;, 187., 2192 21

INSERT TO MARKED-UP TECHNICAL SPECIFICATION PAGES Two loop operation:

S*5 0.33W+ 50.45% for 0% < W < 30.9%

S<* 1.07W+ 27.23% for 30.9% < W <W66.7%

S5 0.55W+ 62.34 for 66.7% < W *599.0%

With a maximum of 117.0% power for W > 99.0%

Single loop operation:

S< 0.33W+ 48.00 for 0% < W < 39.1 %

S* 1.07W+ 19.01 for 39.1% <W *561.7%

S< 0.55W+ 51.22 for 61.7% < W *5119.4%

With a maximum of 117.0% power for W > 119.4%

BVY 06-018 Docket No. 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 45 Extended Power Uprate Re-Typed Technical Specifications Pages Total number of pages in Attachment 2 l (excluding this cover sheet) is 2.

'VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Applicability: Applicability:

Applies to the interrelated Applies to trip setting of the variable associated with fuel instruments and devices which are thermal behavior. provided to prevent the nuclear system safety limits from being exceeded.

Objective: Objective:

To establish limits below which the To define the level of the process integrity of the fuel cladding is variable at which automatic preserved. protective action is initiated.

Specification: Specification:

A. Bundle Safety Limit (Reactor A. Trip Settings Pressure >800 psia and Core Flow

>10% of Rated) The limiting safety system trip settings shall be as When the reactor pressure is specified below:

>800 psia and the core flow is greater than 10% of rated: 1. Neutron Flux Trip Settings

1. A Minimum Critical Power Ratio a. APRM Flux Scram (MCPR) of less than 1.07 (1.09 Allowable Value for Single Loop Operation) (Run Mode) shall constitute violation of the Fuel Cladding Integrity When the mode switch Safety Limit (FCISL). is in the RUN position, the APRM flux scram Allowable Value shall be:

Two loop operation:

SS 0.33W+ 50.45% for D% < W S 30.9%

so 1.07W+ 27.23% for 30.9% < W S 66.7%

SS 0.55W+ 62.34% for 66.7% < W S 99.0%

With a maximum of 117.0% power for W >

99.0%

Single loop operation:

SS 0.33W+ 48.00% for 0% < W S 39.1%

SS 1.07W+ 19.01% for 39.1% < W S 61.7%

SS 0.55W+ 51.22% for 61.7% < W S 119.4%

With a maximum of 117.0% power for W >

119.4%

where:

S - setting in percent of rated thermal power (1912 fWt) I Amendment No. AS, 4:*, 4+, 96, 94, EMS, 444, 1594,S 2-16 6

VYNPS TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS Required ACTIONS When Modes in Which Minimum Number Minimum Functions Must be Operating Operating Conditions Instrument For Operation Channels Per Are Not Trip Function Trip Settings Refuel (1) Startup(12) Run Trip System (2) Satisfied (3)

1. Mode Switch in Shutdown (5A-S1) X X X 1 A

2. Manual Scram X X X 1 A (SA-S3A/B)

3. IRM (7-41(A-F))

High Flux <120/125 x X 2 A INOP X X 2 A

4. APRM (APRM A-F)

High Flux Two loop operation: (4) X 2 A or B (flow bias) S5 0.33W+ 50.45% for 0% < w. S 30.9%

Ss 1.07W+ 27.23% for 30.9% < w 5 66.7%

SS 0.55t+ 62.34t for 66.7% < W s 99.0%

With a maximum of 117.0% pover for w >

99.0%

Single looP operation: (4)

S% 0.33W+ 48.00% for 0% < w S 39.1%

SS 1.07W+ 19.01% for 39.1% < W S 61.7%

Ss 0.55W+ 51.22% for 61.7%t< W 5 119.4%

with a maximum of 117.0t power for w >

119.4t High Flux X X 2 A

<15%

(reduced)

INOP X X 2(5) A or B

5. High Reactor <1055 psig X X X 2 A Pressure (PT-2-3-55(A-D)

(M)

Amendment No. i-, 44, 6.4, "t 44, :I8, 49, 00, 04, 444, s., 4.., 24142 21