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| number = ML081430682
| number = ML081430682
| issue date = 05/22/2008
| issue date = 05/22/2008
| title = 2008/05/22-Letter to Atomic Safety and Licensing Board Corrected Affidavit of Kenneth Chang (Exhibit 2) and Missing Page 4-43 to Staff Exhibit 1
| title = Letter to Atomic Safety and Licensing Board Corrected Affidavit of Kenneth Chang (Exhibit 2) and Missing Page 4-43 to Staff Exhibit 1
| author name = Subin L B
| author name = Subin L
| author affiliation = NRC/OGC
| author affiliation = NRC/OGC
| addressee name = Karlin A S, Reed W H, Wardwell R E
| addressee name = Karlin A, Reed W, Wardwell R
| addressee affiliation = NRC/ASLBP
| addressee affiliation = NRC/ASLBP
| docket = 05000271
| docket = 05000271
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:May 22, 2008  
{{#Wiki_filter:May 22, 2008 Alex S. Karlin, Esq., Chair                             Dr. William H. Reed Administrative Judge                                   Administrative Judge Atomic Safety and Licensing Board                       Atomic Safety and Licensing Board Mail Stop T-3 F23                                       1819 Edgewood Lane U.S. Nuclear Regulatory Commission                     Charlottesville, VA 22902 Washington, DC 20555-0001 Dr. Richard E. Wardwell Administrative Judge Atomic Safety and Licensing Board Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 In the Matter of ENTERGY NUCLEAR OPERATIONS, INC.
 
(Vermont Yankee Nuclear Power Station)
Alex S. Karlin, Esq., Chair   Dr. William H. Reed Administrative Judge     Administrative Judge Atomic Safety and Licensing Board   Atomic Safety and Licensing Board Mail Stop T-3 F23     1819 Edgewood Lane U.S. Nuclear Regulatory Commission Charlottesville, VA 22902 Washington, DC 20555-0001  
Docket No. 50-271-LR; ASLBP No. 06-849-03-LR
 
Dr. Richard E. Wardwell
 
Administrative Judge  
 
Atomic Safety and Licensing Board Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001  
 
In the Matter of ENTERGY NUCLEAR OPERATIONS, INC. (Vermont Yankee Nuclear Power Station) Docket No. 50-271-LR; ASLBP No. 06-849-03-LR


==Dear Administrative Judges:==
==Dear Administrative Judges:==
Line 32: Line 24:
It has come to the Staffs attention that testimony provided in Affidavit of Kenneth C.
It has come to the Staffs attention that testimony provided in Affidavit of Kenneth C.
Chang Concerning NEC Contentions 2A & 2B (Metal Fatigue) (Staff Exh. 2) contained errors.
Chang Concerning NEC Contentions 2A & 2B (Metal Fatigue) (Staff Exh. 2) contained errors.
Enclosed are Affidavit of Kenneth C. Chang dated May 21, 2008 and replacement pages for Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A & 2B.
Enclosed are Affidavit of Kenneth C. Chang dated May 21, 2008 and replacement pages for Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A & 2B.
 
It has also come to the Staffs attention that in Staff Exh. 1, the last page of Section 4.3 (page 4-43) was missing. Please find that page enclosed.
It has also come to the Staffs attention that in Staff Exh. 1, the last page of Section 4.3 (page 4-43) was missing. Please find that page enclosed.  
Sincerely,
 
                                                        /RA/
Sincerely,  
Lloyd B. Subin Counsel for NRC Staff
 
/RA/ Lloyd B. Subin Counsel for NRC Staff  


==Enclosures:==
==Enclosures:==
As Stated cc: Attached Service List UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
As Stated cc:     Attached Service List
 
In the Matter of    ) ) ENTERGY NUCLEAR VERMONT YANKEE, LLC    ) Docket No. 50-271-LR AND ENTERGY NUCLEAR OPERATIONS, INC. )  ) (Vermont Yankee Nuclear Power Station)  )
 
AFFIDAVIT OF KENNETH C. CHANG I, Kenneth C. Chang, do hereby declare under penalty of perjury as follows:  1. In A.4 on page 5, lines 11-12, of Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A & 2B (Metal Fatigue) (Staff Exh. 2) I in inadvertently wrote that "the FW nozzle is Vermont Yankee's most FAC-susceptible nozzle."  I intended to write that "the FW nozzle is Vermont Yankee's most limiting (i.e. nozzle with highest CUFen)."    2. Therefore, in A.4 on page 5 in line 12, the words "FAC-susceptible" should be stricken and replaced with the words "most limiting (i.e. nozzle with the highest CUFen)."
: 3. The sentence in A.11 on page 10 lines 1-7 of Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A &2B (Metal Fatigue) (Staff Exh. 2) is unclear and must be revised. 
: 4. The existing sentence should be replaced with the following: Error analysis is not necessary because conservatism is built into the design fatigue curves for carbon steel/stainless steel in the light water environment. As stated in NUREG/CR-6583 and NUREG/CG-5704, these design curves have been adjusted for uncertainties that are associated with material and loading conditions. 
 
4-43application using the specific software could underestimate the CUF, and therefore, cannot be enthe analysis of record. However, the updated analysis, whether using the maximum F or enappropriate Fs, yields CUFs lower than the Code allowable. The staff concludes that thisupdated analysis are the analysis of record for the FW nozzle. Based on the above discussion, the staff concludes that similar analysis should be performed for the CS and the RR outlet nozzles and that these analyses will be documented as the analyses of record for these two nozzles. On this basis, the staff finds that although the applicant has used a 2-dimensional axisymmetricmodel to handle thermal transient and pressure, it did consider the six stress components and use them to develop three principle stresses and the stress intensities. Therefore, the staff finds that for the updated analysis of the FW nozzle, the stress intensities and the CUFs are calculated in accordance with ASME Code requirements. The staff concluded that the updated FW analysis consistent with the rules of the ASME Code Section III yields lower EAF CUF values for the FW nozzle. In the letter dated February 21, 2008, the applicant stated that it considers the updated EAF analysis, submitted in the January 30, 2008 letter, as the analysis of record for the FW nozzle. The staffs concern expressed in RAI 4.3.3-2 is resolved. However, a license condition for performing the ASME Code analyses for the CS and the RR outlet nozzles will remain in effect until the applicant has completed and submitted those final analyses for NRC review and approval no later than two years prior to entering the PEO.4.3.3.3  UFSAR SupplementThe applicant provided a UFSAR Supplement summary description of its TLAA evaluation ofeffects of reactor water environment on fatigue life in LRA Section A.2.2.2.3. The staff reviewed the applicants Commitment No. 27 and concludes that implementation of thiscommitment prior to period of extended operation will address environmentally assisted fatigue for the seven components which have not been addressed.On the basis of its review of the UFSAR Supplement, the staff concludes that the summarydescription of the applicants actions to address effects of reactor water environment on fatigue life is adequate.4.3.3.4  ConclusionOn the basis of its review, and Commitment No. 27 as discussed above, the staff finds that theapplicant has demonstrated that, as required by 10 CFR 54.21(c)(1)(iii), the effects of aging on the intended function(s) will be adequately managed for the period of extended operation. The staff also concludes that the UFSAR Supplement contains an appropriate summary description of the TLAA evaluation, as required by 10 CFR 54.21(d).
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )  ) ENTERGY NUCLEAR VERMONT YANKEE, ) Docket No. 50-271-LR LLC, and ENTERGY NUCLEAR )
OPERATIONS, INC. ) ASLBP No. 06-849-03-LR
) (Vermont Yankee Nuclear Power Station) )
CERTIFICATE OF SERVICE
 
I hereby certify that copies of the NRC Staff letter dated May 22, 2008, transmitting corrected testimony and missing exhibit pages in the above-captioned proceeding have been served on the following by electronic mail with copies by deposit in the NRCs internal mail system or, as indicated by an asterisk, by electronic mail, with copies by U.S. mail, first class, this 22nd day of
 
May, 2008.
 
Alex S. Karlin, Chair Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC  20555-0001
 
E-mail: ask2@nrc.gov Office of the Secretary Attn: Rulemakings and Adjudications Staff Mail Stop: O-16G4 U.S. Nuclear Regulatory Commission Washington, DC  20555-0001
 
E-mail: hearingdocket@nrc.gov William H. Reed*
 
Administrative Judge Atomic Safety and Licensing Board 
 
1819 Edgewood Lane
 
Charlottesville, VA 22902 E-mail: whrcville@embarqmail.com Marcia Carpentier, Esq. Atomic Safety and Licensing Board Panel
 
Mail Stop: T-3F23 U.S. Nuclear Regulatory Commission Washington, DC  20555-0001 E-mail: mxc7@nrc.gov Richard E. Wardwell
 
Administrative Judge Atomic Safety and Licensing Board  U.S. Nuclear Regulatory Commission Washington, DC  20555-0001
 
E-mail: rew@nrc.gov Lauren Bregman, Law Clerk Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mail Stop: T-3 F23 Washington, D.C. 20555-0001
 
E-mail: Lauren.Bregman@nrc.gov Office of Commission Appellate
 
Adjudication Mail Stop: O-16G4 U.S. Nuclear Regulatory Commission Washington, DC  20555-0001
 
E-mail: OCAAmail@nrc.gov Peter C.L. Roth, Esq* Office of the Attorney General 33 Capitol Street Concord, NH  3301
 
E-mail: peter.roth@doj.nh.gov Ronald A. Shems, Esq.*
Karen Tyler, Esq.
Shems Dunkiel Kassel & Saunders, PLLC 91 College Street Burlington, VT  05401
 
E-mail: rshems@sdkslaw.com Ktyler@sdkslaw.com Anthony Z. Roisman, Esq.*  National Legal Scholars Law Firm 
 
84 East Thetford Rd. Lyme, NH  03768 E-mail: aroisman@nationallegalscholars.com David R. Lewis, Esq.*
Matias F. Travieso-Diaz, Esq Elina Teplinsky, Esq
 
Blake J. Nelson, Esq
 
Pillsbury Winthrop Shaw Pittman LLP
 
2300 N Street, NW Washington, DC  20037-1128 E-mail: david.lewis@pillsburylaw.com matias.travieso-diaz@pillsburylaw.com elina.teplinsky@pillsburylaw.com
 
b lake.nelson@pillsburylaw.com Sarah Hofmann, Esq.*  Director of Public Advocacy  Department of Public Service 112 State Street - Drawer 20


Montpelier, VT  05620-2601
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of                                        )
                                                        )
ENTERGY NUCLEAR VERMONT YANKEE, LLC                    )      Docket No. 50-271-LR AND ENTERGY NUCLEAR OPERATIONS, INC.                    )
                                                        )
(Vermont Yankee Nuclear Power Station)                  )
AFFIDAVIT OF KENNETH C. CHANG I, Kenneth C. Chang, do hereby declare under penalty of perjury as follows:
: 1.      In A.4 on page 5, lines 11-12, of Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A & 2B (Metal Fatigue) (Staff Exh. 2) I in inadvertently wrote that the FW nozzle is Vermont Yankees most FAC-susceptible nozzle. I intended to write that the FW nozzle is Vermont Yankees most limiting (i.e. nozzle with highest CUFen).
: 2.      Therefore, in A.4 on page 5 in line 12, the words FAC-susceptible should be stricken and replaced with the words most limiting (i.e. nozzle with the highest CUFen).
: 3.      The sentence in A.11 on page 10 lines 1-7 of Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A &2B (Metal Fatigue) (Staff Exh. 2) is unclear and must be revised.
: 4.      The existing sentence should be replaced with the following: Error analysis is not necessary because conservatism is built into the design fatigue curves for carbon steel/stainless steel in the light water environment. As stated in NUREG/CR-6583 and NUREG/CG-5704, these design curves have been adjusted for uncertainties that are associated with material and loading conditions.


E-mail: sarah.hofmann@state.vt.us Diane Curran* Harmon, Curran, Spielberg, & Eisenberg, LLP 1726 M Street N.W., Suite 600 Washington, D.C. 20036
application using the specific software could underestimate the CUF, and therefore, cannot be the analysis of record. However, the updated analysis, whether using the maximum Fen or appropriate Fen s, yields CUFs lower than the Code allowable. The staff concludes that this updated analysis are the analysis of record for the FW nozzle. Based on the above discussion, the staff concludes that similar analysis should be performed for the CS and the RR outlet nozzles and that these analyses will be documented as the analyses of record for these two nozzles.
On this basis, the staff finds that although the applicant has used a 2-dimensional axisymmetric model to handle thermal transient and pressure, it did consider the six stress components and use them to develop three principle stresses and the stress intensities. Therefore, the staff finds that for the updated analysis of the FW nozzle, the stress intensities and the CUFs are calculated in accordance with ASME Code requirements. The staff concluded that the updated FW analysis consistent with the rules of the ASME Code Section III yields lower EAF CUF values for the FW nozzle. In the letter dated February 21, 2008, the applicant stated that it considers the updated EAF analysis, submitted in the January 30, 2008 letter, as the analysis of record for the FW nozzle. The staffs concern expressed in RAI 4.3.3-2 is resolved. However, a license condition for performing the ASME Code analyses for the CS and the RR outlet nozzles will remain in effect until the applicant has completed and submitted those final analyses for NRC review and approval no later than two years prior to entering the PEO.
4.3.3.3 UFSAR Supplement The applicant provided a UFSAR Supplement summary description of its TLAA evaluation of effects of reactor water environment on fatigue life in LRA Section A.2.2.2.3.
The staff reviewed the applicants Commitment No. 27 and concludes that implementation of this commitment prior to period of extended operation will address environmentally assisted fatigue for the seven components which have not been addressed.
On the basis of its review of the UFSAR Supplement, the staff concludes that the summary description of the applicants actions to address effects of reactor water environment on fatigue life is adequate.
4.3.3.4 Conclusion On the basis of its review, and Commitment No. 27 as discussed above, the staff finds that the applicant has demonstrated that, as required by 10 CFR 54.21(c)(1)(iii), the effects of aging on the intended function(s) will be adequately managed for the period of extended operation. The staff also concludes that the UFSAR Supplement contains an appropriate summary description of the TLAA evaluation, as required by 10 CFR 54.21(d).
4-43


E-mail: dcurran@harmoncurran.com James R. Milkey* Assistant Attorney General, Chief Environmental Protection Division Office of the Attorney General One Ashburton Place, 18th Floor Boston, MA 02108 E-mail: jim.milkey@state.ma.us
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of                                  )
                                                  )
ENTERGY NUCLEAR VERMONT YANKEE,                  )    Docket No. 50-271-LR LLC, and ENTERGY NUCLEAR                      )
OPERATIONS, INC.                              )    ASLBP No. 06-849-03-LR
                                                  )
(Vermont Yankee Nuclear Power Station)            )
CERTIFICATE OF SERVICE I hereby certify that copies of the NRC Staff letter dated May 22, 2008, transmitting corrected testimony and missing exhibit pages in the above-captioned proceeding have been served on the following by electronic mail with copies by deposit in the NRCs internal mail system or, as indicated by an asterisk, by electronic mail, with copies by U.S. mail, first class, this 22nd day of May, 2008.
Alex S. Karlin, Chair                              Office of the Secretary Administrative Judge                                Attn: Rulemakings and Adjudications Staff Atomic Safety and Licensing Board                  Mail Stop: O-16G4 U.S. Nuclear Regulatory Commission                  U.S. Nuclear Regulatory Commission Washington, DC 20555-0001                          Washington, DC 20555-0001 E-mail: ask2@nrc.gov                                E-mail: hearingdocket@nrc.gov William H. Reed*                                    Marcia Carpentier, Esq.
Administrative Judge                                Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board                  Mail Stop: T-3F23 1819 Edgewood Lane                                  U.S. Nuclear Regulatory Commission Charlottesville, VA 22902                          Washington, DC 20555-0001 E-mail: whrcville@embarqmail.com                   E-mail: mxc7@nrc.gov Richard E. Wardwell                                Lauren Bregman, Law Clerk Administrative Judge                                Atomic Safety and Licensing Board Atomic Safety and Licensing Board                  U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission                  Mail Stop: T-3 F23 Washington, DC 20555-0001                          Washington, D.C. 20555-0001 E-mail: rew@nrc.gov                                E-mail: Lauren.Bregman@nrc.gov Office of Commission Appellate                      Peter C.L. Roth, Esq*
Adjudication                                    Office of the Attorney General Mail Stop: O-16G4                                  33 Capitol Street U.S. Nuclear Regulatory Commission                  Concord, NH 3301 Washington, DC 20555-0001                          E-mail: peter.roth@doj.nh.gov E-mail: OCAAmail@nrc.gov


   /RA/ _____________________________
Ronald A. Shems, Esq.*                        Anthony Z. Roisman, Esq.*
Karen Tyler, Esq.                              National Legal Scholars Law Firm Shems Dunkiel Kassel & Saunders, PLLC          84 East Thetford Rd.
91 College Street                              Lyme, NH 03768 Burlington, VT 05401                          E-mail: aroisman@nationallegalscholars.com E-mail: rshems@sdkslaw.com Ktyler@sdkslaw.com David R. Lewis, Esq.*                          Sarah Hofmann, Esq.*
Matias F. Travieso-Diaz, Esq                  Director of Public Advocacy Elina Teplinsky, Esq                          Department of Public Service Blake J. Nelson, Esq                          112 State Street - Drawer 20 Pillsbury Winthrop Shaw Pittman LLP            Montpelier, VT 05620-2601 2300 N Street, NW                              E-mail: sarah.hofmann@state.vt.us Washington, DC 20037-1128 E-mail: david.lewis@pillsburylaw.com matias.travieso-diaz@pillsburylaw.com elina.teplinsky@pillsburylaw.com blake.nelson@pillsburylaw.com Diane Curran*                                  James R. Milkey*
Harmon, Curran, Spielberg, & Eisenberg, LLP   Assistant Attorney General, Chief 1726 M Street N.W., Suite 600                  Environmental Protection Division Washington, D.C. 20036                        Office of the Attorney General E-mail: dcurran@harmoncurran.com              One Ashburton Place, 18th Floor Boston, MA 02108 E-mail: jim.milkey@state.ma.us
                                                  /RA/
Lloyd B. Subin Counsel for NRC Staff}}
Lloyd B. Subin Counsel for NRC Staff}}

Latest revision as of 01:44, 13 March 2020

Letter to Atomic Safety and Licensing Board Corrected Affidavit of Kenneth Chang (Exhibit 2) and Missing Page 4-43 to Staff Exhibit 1
ML081430682
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 05/22/2008
From: Subin L
NRC/OGC
To: Karlin A, Wendy Reed, Richard Wardwell
Atomic Safety and Licensing Board Panel
SECY RAS
References
50-271-LR, ASLBP 06-849-03-LR, RAS M-63
Download: ML081430682 (8)


Text

May 22, 2008 Alex S. Karlin, Esq., Chair Dr. William H. Reed Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board Mail Stop T-3 F23 1819 Edgewood Lane U.S. Nuclear Regulatory Commission Charlottesville, VA 22902 Washington, DC 20555-0001 Dr. Richard E. Wardwell Administrative Judge Atomic Safety and Licensing Board Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 In the Matter of ENTERGY NUCLEAR OPERATIONS, INC.

(Vermont Yankee Nuclear Power Station)

Docket No. 50-271-LR; ASLBP No. 06-849-03-LR

Dear Administrative Judges:

It has come to the Staffs attention that testimony provided in Affidavit of Kenneth C.

Chang Concerning NEC Contentions 2A & 2B (Metal Fatigue) (Staff Exh. 2) contained errors.

Enclosed are Affidavit of Kenneth C. Chang dated May 21, 2008 and replacement pages for Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A & 2B.

It has also come to the Staffs attention that in Staff Exh. 1, the last page of Section 4.3 (page 4-43) was missing. Please find that page enclosed.

Sincerely,

/RA/

Lloyd B. Subin Counsel for NRC Staff

Enclosures:

As Stated cc: Attached Service List

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

ENTERGY NUCLEAR VERMONT YANKEE, LLC ) Docket No. 50-271-LR AND ENTERGY NUCLEAR OPERATIONS, INC. )

)

(Vermont Yankee Nuclear Power Station) )

AFFIDAVIT OF KENNETH C. CHANG I, Kenneth C. Chang, do hereby declare under penalty of perjury as follows:

1. In A.4 on page 5, lines 11-12, of Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A & 2B (Metal Fatigue) (Staff Exh. 2) I in inadvertently wrote that the FW nozzle is Vermont Yankees most FAC-susceptible nozzle. I intended to write that the FW nozzle is Vermont Yankees most limiting (i.e. nozzle with highest CUFen).
2. Therefore, in A.4 on page 5 in line 12, the words FAC-susceptible should be stricken and replaced with the words most limiting (i.e. nozzle with the highest CUFen).
3. The sentence in A.11 on page 10 lines 1-7 of Affidavit of Kenneth C. Chang Concerning NEC Contentions 2A &2B (Metal Fatigue) (Staff Exh. 2) is unclear and must be revised.
4. The existing sentence should be replaced with the following: Error analysis is not necessary because conservatism is built into the design fatigue curves for carbon steel/stainless steel in the light water environment. As stated in NUREG/CR-6583 and NUREG/CG-5704, these design curves have been adjusted for uncertainties that are associated with material and loading conditions.

application using the specific software could underestimate the CUF, and therefore, cannot be the analysis of record. However, the updated analysis, whether using the maximum Fen or appropriate Fen s, yields CUFs lower than the Code allowable. The staff concludes that this updated analysis are the analysis of record for the FW nozzle. Based on the above discussion, the staff concludes that similar analysis should be performed for the CS and the RR outlet nozzles and that these analyses will be documented as the analyses of record for these two nozzles.

On this basis, the staff finds that although the applicant has used a 2-dimensional axisymmetric model to handle thermal transient and pressure, it did consider the six stress components and use them to develop three principle stresses and the stress intensities. Therefore, the staff finds that for the updated analysis of the FW nozzle, the stress intensities and the CUFs are calculated in accordance with ASME Code requirements. The staff concluded that the updated FW analysis consistent with the rules of the ASME Code Section III yields lower EAF CUF values for the FW nozzle. In the letter dated February 21, 2008, the applicant stated that it considers the updated EAF analysis, submitted in the January 30, 2008 letter, as the analysis of record for the FW nozzle. The staffs concern expressed in RAI 4.3.3-2 is resolved. However, a license condition for performing the ASME Code analyses for the CS and the RR outlet nozzles will remain in effect until the applicant has completed and submitted those final analyses for NRC review and approval no later than two years prior to entering the PEO.

4.3.3.3 UFSAR Supplement The applicant provided a UFSAR Supplement summary description of its TLAA evaluation of effects of reactor water environment on fatigue life in LRA Section A.2.2.2.3.

The staff reviewed the applicants Commitment No. 27 and concludes that implementation of this commitment prior to period of extended operation will address environmentally assisted fatigue for the seven components which have not been addressed.

On the basis of its review of the UFSAR Supplement, the staff concludes that the summary description of the applicants actions to address effects of reactor water environment on fatigue life is adequate.

4.3.3.4 Conclusion On the basis of its review, and Commitment No. 27 as discussed above, the staff finds that the applicant has demonstrated that, as required by 10 CFR 54.21(c)(1)(iii), the effects of aging on the intended function(s) will be adequately managed for the period of extended operation. The staff also concludes that the UFSAR Supplement contains an appropriate summary description of the TLAA evaluation, as required by 10 CFR 54.21(d).

4-43

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

ENTERGY NUCLEAR VERMONT YANKEE, ) Docket No. 50-271-LR LLC, and ENTERGY NUCLEAR )

OPERATIONS, INC. ) ASLBP No. 06-849-03-LR

)

(Vermont Yankee Nuclear Power Station) )

CERTIFICATE OF SERVICE I hereby certify that copies of the NRC Staff letter dated May 22, 2008, transmitting corrected testimony and missing exhibit pages in the above-captioned proceeding have been served on the following by electronic mail with copies by deposit in the NRCs internal mail system or, as indicated by an asterisk, by electronic mail, with copies by U.S. mail, first class, this 22nd day of May, 2008.

Alex S. Karlin, Chair Office of the Secretary Administrative Judge Attn: Rulemakings and Adjudications Staff Atomic Safety and Licensing Board Mail Stop: O-16G4 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Washington, DC 20555-0001 E-mail: ask2@nrc.gov E-mail: hearingdocket@nrc.gov William H. Reed* Marcia Carpentier, Esq.

Administrative Judge Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board Mail Stop: T-3F23 1819 Edgewood Lane U.S. Nuclear Regulatory Commission Charlottesville, VA 22902 Washington, DC 20555-0001 E-mail: whrcville@embarqmail.com E-mail: mxc7@nrc.gov Richard E. Wardwell Lauren Bregman, Law Clerk Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Mail Stop: T-3 F23 Washington, DC 20555-0001 Washington, D.C. 20555-0001 E-mail: rew@nrc.gov E-mail: Lauren.Bregman@nrc.gov Office of Commission Appellate Peter C.L. Roth, Esq*

Adjudication Office of the Attorney General Mail Stop: O-16G4 33 Capitol Street U.S. Nuclear Regulatory Commission Concord, NH 3301 Washington, DC 20555-0001 E-mail: peter.roth@doj.nh.gov E-mail: OCAAmail@nrc.gov

Ronald A. Shems, Esq.* Anthony Z. Roisman, Esq.*

Karen Tyler, Esq. National Legal Scholars Law Firm Shems Dunkiel Kassel & Saunders, PLLC 84 East Thetford Rd.

91 College Street Lyme, NH 03768 Burlington, VT 05401 E-mail: aroisman@nationallegalscholars.com E-mail: rshems@sdkslaw.com Ktyler@sdkslaw.com David R. Lewis, Esq.* Sarah Hofmann, Esq.*

Matias F. Travieso-Diaz, Esq Director of Public Advocacy Elina Teplinsky, Esq Department of Public Service Blake J. Nelson, Esq 112 State Street - Drawer 20 Pillsbury Winthrop Shaw Pittman LLP Montpelier, VT 05620-2601 2300 N Street, NW E-mail: sarah.hofmann@state.vt.us Washington, DC 20037-1128 E-mail: david.lewis@pillsburylaw.com matias.travieso-diaz@pillsburylaw.com elina.teplinsky@pillsburylaw.com blake.nelson@pillsburylaw.com Diane Curran* James R. Milkey*

Harmon, Curran, Spielberg, & Eisenberg, LLP Assistant Attorney General, Chief 1726 M Street N.W., Suite 600 Environmental Protection Division Washington, D.C. 20036 Office of the Attorney General E-mail: dcurran@harmoncurran.com One Ashburton Place, 18th Floor Boston, MA 02108 E-mail: jim.milkey@state.ma.us

/RA/

Lloyd B. Subin Counsel for NRC Staff