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{{#Wiki_filter:AS -DOCKETED USNRC July 16, 2008 (8:00am)OFFICE OF SECRETARY UNITED STATES RULEMAKINGS AND NUCLEAR REGULATORY COMMISSION ADJUDICATIONS' STAFF ATOMIC SAFETY AND LICENSING BOARD In the Matter of ))ENTERGY NUCLEAR VERMONT YANKEE, LLC ) Docket No. 50-271-LR and ENTERGY NUCLEAR OPERATIONS, INC. ) ASLBP No. 06-849-03-LR | {{#Wiki_filter:AS -DOCKETED USNRC July 16, 2008 (8:00am) | ||
)(Vermont Yankee Nuclear Power Station) )NEW ENGLAND COALITION, INC.SUPPLEMENTAL PREHEARING REPLY BRIEF New England Coalition, Inc. ("NEC") submits this supplemental prehearing reply brief pursuant to the Board's Order of June 27, 2008.1 I. ISSUES JA AND 1B In Entergy's and the NRC Staffs view of the License Renewal process, an applicant need never include an analysis to project a TLAA to the end of the period of extended operation in the License Renewal Application (LRA), pursuant to 10 CFR ¶ 54.21 (c)(1)(ii). | OFFICE OF SECRETARY UNITED STATES RULEMAKINGS AND NUCLEAR REGULATORY COMMISSION ADJUDICATIONS' STAFF ATOMIC SAFETY AND LICENSING BOARD In the Matter of ) | ||
The licensee may instead make a generally stated "commitment" to perform this analysis as an aging management plan pursuant to 10 CFR 5 54.21 (c)(1)(iii) after license renewal is approved. | ) | ||
This commitment to project the TLAA need not specify details of the methodology the applicant will employ, and can constitute the applicant's entire proposed "aging management plan." There is no place for public participation or the Atomic Safety and Licensing Board in this process; the NRC Staff will perform all substantive review of the analysis that may fully constitute a licensee's"aging management plan" after the close of any Board proceedings. | ENTERGY NUCLEAR VERMONT YANKEE, LLC ) Docket No. 50-271-LR and ENTERGY NUCLEAR OPERATIONS, INC. ) ASLBP No. 06-849-03-LR | ||
Moreover, the NRC Staff does not consider "commitments" legally binding or enforceable under 10 CFR 2.206. As the I Licensing Board Order (Regarding the Briefing of Certain Legal Issues) (June 27, 2008). | ) | ||
(State of Vermont has aptly observed, the Staff does not propose to eliminate review of safety analyses; it just wants to eliminate the role of the public and the Board in that review.-The Atomic Energy Act (AEA) mandates the public participation Entergy and the NRC Staff would foreclose; the NRC may not exclude a material public-safety related issue from consideration by the Atomic Safety and Licensing Board at the request of an interested person.S)See, Union of | (Vermont Yankee Nuclear Power Station) ) | ||
NEW ENGLAND COALITION, INC. | |||
Entergy's CUFen analyses are a TLAA demonstration meant to substitute for the management of aging due to metal fatigue through inspection, repair and replacement of components; as such, it must be included in the license renewal application (LRA) pursuant to 10 CFR 54.2 1 (c)(1)(ii). | SUPPLEMENTAL PREHEARING REPLY BRIEF New England Coalition, Inc. ("NEC") submits this supplemental prehearing reply brief pursuant to the Board's Order of June 27, 2008.1 I. ISSUES JA AND 1B In Entergy's and the NRC Staffs view of the License Renewal process, an applicant need never include an analysis to project a TLAA to the end of the period of extended operation in the License Renewal Application (LRA), pursuant to 10 CFR ¶ 54.21 (c)(1)(ii). The licensee may instead make a generally stated "commitment" to perform this analysis as an aging management plan pursuant to 10 CFR 5 54.21 (c)(1)(iii) after license renewal is approved. This commitment to project the TLAA need not specify details of the methodology the applicant will employ, and can constitute the applicant's entire proposed "aging management plan." There is no place for public participation or the Atomic Safety and Licensing Board in this process; the NRC Staff will perform all substantive review of the analysis that may fully constitute a licensee's "aging management plan" after the close of any Board proceedings. Moreover, the NRC Staff does not consider "commitments" legally binding or enforceable under 10 CFR | ||
Entergy performed the CUFen analyses to project the CUF calculations that are part of Vermont Yankee's current licensing basis (CLB) to the end of the period of extended operations. | * 2.206. As the I Licensing Board Order (Regarding the Briefing of Certain Legal Issues) (June 27, 2008). | ||
The CUFen analyses are intended to demonstrate that a metal fatigue"aging management plan" involving component inspection, repair and replacement is unnecessary. | |||
If the CUFen analyses fail to demonstrate that vulnerable Vermont Yankee components will meet acceptance criteria through the end of the renewed license term, Entergy is required to amend it6 LRA to specifically describe the scope, method and frequency of a proposed inspection and maintenance program. 10 CFR § 54.2 1(c)(1). NEC would then be entitled to review and evaluate this program pursuant to its Contention' 2, now stayed by Board Order pending resolution of Contentions 2A and 2B.2 Entergy contends that its CUFen analyses are not a projection'of a TLAA. This is incorrect. | ( | ||
The CUFen analyses project CUF calculations, which are a TLAA incorporated in Vermont Yankee's CLB. Entergy's LRA states the following: | State of Vermont has aptly observed, the Staff does not propose to eliminate review of safety analyses; it just wants to eliminate the role of the public and the Board in that review. | ||
Fatigue evaluations were preformed in the design of the VYNPS Class 1 components designed in accordance with the requirements specified in ASME Section III. The fatigue evaluations are contained in analyses and stress reports, and because they are based on a number of transient cycles assumed for a 40-year plant life, these evaluations are considered TLAA.LRA 4.3-1; See also, Exhibit NEC-JH_62, NRC Summary of Telephone Conference Call Held on August 20, 2007, Concerning the Vermont Yankee Nuclear Power Station License Renewal Application at Enclosure 2 ("Fatigue analyses based on a set of design transients and on the life of the plant are treated as TLAAs.")./The NRC Staff's explanation of its treatment of the CUFen reanalyses makes clear that the Staff's position elevates form over substance. | - The Atomic Energy Act (AEA) mandates the public participation Entergy and the NRC Staff would foreclose; the NRC may not exclude a material public-safety related issue from consideration by the Atomic Safety and Licensing Board at the request of an interested person. | ||
It also underscores NEC's argument that the Staffsview of § 54.21(c)(1) renders § 54.21(c)(1)(ii) superfluous. | S) | ||
The Staff claims that it did not change its interpretation of § 54.21 (c)(1) between August 2007 and May 2008. Rather, Entergy changed its view of which section of § 54.21 (c)(1) applies to the CUFen inalyses: "Entergy temporarily indicated that it would rely on § 54.21 (c)(ii), before ultimately relying upon 54.21(c)(1)(iii)." NRC Staffs Brief in Response to Board Order at 4. The NRC's regulations should not and do riot allow in applicant to alter the Staff's treatment of a safety analysis by citing to subsection (iii) instead of subsection (ii). Moreover, why would any applicant choose to include a TLAA projection in its LRA pursuant to § 54.21(c)(ii) if it can postpone NRC review of that analysis until after the close of any ASLB proceedings just by citing to § 54.21 (c)(1)(iii) instead? NEC submits that the answer to this question is never. Entergy's strategy in the Indian Point license renewal proceeding, discussed in NEC's Rebuttal Statement of Position at 6, bears this out. See, Exhibit NEC-JH-67. | See, Union of ConcernedScientists v. UnitedStates Nuclear Re~gulatoy Commission, 735 F.2d 1437 (D.C. | ||
Entergy initially characterized its CUFen analysis as a TLAA 3 demonstration under § 54.21 (c) (ii) because that is what itis -it is an analysis to project the CUF TLAA to the end of the period of extended operation. | CiT. 1984). Entergy's and the NRC Staff's arguments are without merit. | ||
B. ENTERGY'S CUFEN ANALYSES ARE NOT AN AGING MANAGEMENT PLAN SUBJECT TO 10 CFR ý 54.21 (c)(1)(iii). | A. ENTERGY'S CUFEN ANALYSES ARE TO PROJECT A METAL FATIGUE TLAA TO THE END OF THE PERIOD OF EXTENDED OPERATION, PURSUANT TO 10 CFR § 54.21 (c)(1)(ii). | ||
Both Entergy and the NRC Staff contend that the CUFen analyses are a component of a Fatigue Monitoring Program ("FMP"), consistent with'GALL Section X.M1. Entergy and the Staff further contend that the FMP is an "aging management plan" that satisfies the requirements of 10 CFR 5 54.21 (c)(1)(iii). | Entergy's CUFen analyses are a TLAA demonstration meant to substitute for the management of aging due to metal fatigue through inspection, repair and replacement of components; as such, it must be included in the license renewal application (LRA) pursuant to 10 CFR 54. 2 1 (c)(1)(ii). Entergy performed the CUFen analyses to project the CUF calculations that are part of Vermont Yankee's current licensing basis (CLB) to the end of the period of extended operations. The CUFen analyses are intended to demonstrate that a metal fatigue "aging management plan" involving component inspection, repair and replacement is unnecessary. If the CUFen analyses fail to demonstrate that vulnerable Vermont Yankee components will meet acceptance criteria through the end of the renewed license term, Entergy is required to amend it6 LRA to specifically describe the scope, method and frequency of a proposed inspection and maintenance program. 10 CFR § 54.2 1(c)(1). NEC would then be entitled to review and evaluate this program pursuant to its Contention' 2, now stayed by Board Order pending resolution of Contentions 2A and 2B. | ||
These arguments misconstrue both the relationship of the CUFen analyses to the FMP and the meaning of § 54.21 (c)(1).The CUFen analyses are not a component of the FMP. The FMP is a program implerhented during the license renewal period that tracks the number of transients for selected reactor coolant system components to confirm the validity of the CUFen TLAA analyses completed pursuant to 54.21 (c)(1)(ii) or 54.21 (c)(1)(i). | 2 | ||
As explained in Entergy's LRA: The Fatigue Monitoring Program (FMP) tracks actual plant transients and evaluates these against the design transients | |||
..... "[T]he FMP will ensure that the number of transient cycles experienced by the plant remain within the analyzed numbers of cycles and hence, the component CUFs remain below the values calculated in the fatigue evaluations. | Entergy contends that its CUFen analyses are not a projection'of a TLAA. This is incorrect. The CUFen analyses project CUF calculations, which are a TLAA incorporated in Vermont Yankee's CLB. Entergy's LRA states the following: | ||
LRA Amendment 31, Attachment 1.The FMP does not satisfy the requirements of 10 CFR 54.21(c)(1)(iii). | Fatigue evaluations were preformed in the design of the VYNPS Class 1 components designed in accordance with the requirements specified in ASME Section III. The fatigue evaluations are contained in analyses and stress reports, and because they are based on a number of transient cycles assumed for a 40-year plant life, these evaluations are considered TLAA. | ||
As explained in this and NEC's prior briefing, § 54.2-1(c)(1)(iii) requires the applicant to "demonstrate that...[t]he effects of aging ... will be adequately managed for the period of extended operation" in the event that "the applicant cannot or chooses not to justify or extend an existing time-limited aging analysis." 10 CFR § 54.21(c)(1); | LRA | ||
Nuclear Regulatory Commission, Nuclear Power Plant License Renewal; Revisions, Final Rule, 60 FR 22461-01, 22480 (May 8, 1995). The FMP serves to confirnri the justification or projection of a TLAA. The demonstration required by 54.21(c)(1)(iii) substitutes for the validation or projection of a TLAA, and should consist of a 4 program'of component inspection, repair and replacement that specifies scope, method and frequency. | * 4.3-1; See also, Exhibit NEC-JH_62, NRC Summary of Telephone Conference Call Held on August 20, 2007, Concerning the Vermont Yankee Nuclear Power Station License Renewal Application at Enclosure 2 ("Fatigue analyses based on a set of design transients and on the life of the plant are treated as TLAAs."). | ||
C. NEC CONTESTS ENTERGY'S AND THE NRC STAFF'S INTERPRETATION OF NRC REGULATIONS, NOT THE REGULATIONS THEMSELVES. | / | ||
Both Entergy and the NRC Staff contend that NEC's argument that § 54.21(c) requires an applicant to perform analyses to justify or project a TLAA before a license is issued is an attack on NRC regulations that contravenes 10 CFR § 2.335(a). | The NRC Staff's explanation of its treatment of the CUFen reanalyses makes clear that the Staff's position elevates form over substance. It also underscores NEC's argument that the Staffsview of § 54.21(c)(1) renders § 54.21(c)(1)(ii) superfluous. The Staff claims that it did not change its interpretation of § 54.21 (c)(1) between August 2007 and May 2008. Rather, Entergy changed its view of which section of § 54.21 (c)(1) applies to the CUFen inalyses: "Entergy temporarily indicated that it would rely on § 54.21 (c)(ii), before ultimately relying upon 54.21(c)(1)(iii)." NRC Staffs Brief in Response to Board Order at 4. The NRC's regulations should not and do riot allow in applicant to alter the Staff's treatment of a safety analysis by citing to subsection (iii) instead of subsection (ii). Moreover, why would any applicant choose to include a TLAA projection in its LRA pursuant to § 54.21(c)(ii) if it can postpone NRC review of that analysis until after the close of any ASLB proceedings just by citing to § 54.21 (c)(1)(iii) instead? NEC submits that the answer to this question is never. Entergy's strategy in the Indian Point license renewal proceeding, discussed in NEC's Rebuttal Statement of Position at 6, bears this out. See, Exhibit NEC-JH-67. Entergy initially characterized its CUFen analysis as a TLAA 3 | ||
NEC contests the interpretation of the regulations, not the regulations themselves. | |||
If the NRC's guidance concerning Fatigue Monitoring Programs published in GALL Section X.M1 can be interpreted to'permit a licensee to'complete a TLAA justification or projection after a renewed license is issued, then this guidance is inconsistent with the plain language, structure and intent of §§ 54.21 (c) and 54.29(a)discussed in this and NEC's prior briefing. | demonstration under § 54.21 (c) (ii) because that is what itis - it is an analysis to project the CUF TLAA to the end of the period of extended operation. | ||
An intervenor may contest the validity of NRC guidance, including the GALL report, in a license-renewal proceeding. | B. ENTERGY'S CUFEN ANALYSES ARE NOT AN AGING MANAGEMENT PLAN SUBJECT TO 10 CFR ý 54.21 (c)(1)(iii). | ||
D.' THE NRC'S REVIEW OF ENTERGY'S CUFEN CALCULATIONS FOR THE FEEDWATER NOZZLE AND RECIRCULATION NOZZLE WOULD NOT BE "MINISTERIAL." The NRC Staff suggests that its post-licensing review of Entergy's CUFen calculations for the recirculation outlet and core spray nozzles using the same method Entergy used to calculate CUFen for the feedwater nozzle would be ministerial and therefore consistent with NRC precedent defining the proper scope of post-licensing resolution by the Staff. The Staff analogizes its review of the CUFen calculations to post-licensing review that was approved in In the | Both Entergy and the NRC Staff contend that the CUFen analyses are a component of a Fatigue Monitoring Program ("FMP"), consistent with'GALL Section X.M1. Entergy and the Staff further contend that the FMP is an "aging management plan" that satisfies the requirements of 10 CFR 5 54.21 (c)(1)(iii). These arguments misconstrue both the relationship of the CUFen analyses to the FMP and the meaning of § 54.21 (c)(1). | ||
has made.*" * *In short, evaluating whether contract provisions in fact function as intended is not merely a ministerial act; it calls for legal judgment. | The CUFen analyses are not a component of the FMP. The FMP is a program implerhented during the license renewal period that tracks the number of transients for selected reactor coolant system components to confirm the validity of the CUFen TLAA analyses completed pursuant to | ||
We think the Board went too far in putting evaluation of the legal effectiveness of service agreements into the hands of the NRC Staff without itself reviewing a sample service contract.Id.The Staffs analogy is inapposite. | * 54.21 (c)(1)(ii) or 54.21 (c)(1)(i). As explained in Entergy's LRA: | ||
As the record in this proceeding to date demonstrates, Entergy's CUFen analyses are complex and' there is room for the exercise of discretion even in the application of a preapproved methodology. | The Fatigue Monitoring Program (FMP) tracks actual plant transients and evaluates these against the design transients ..... "[T]he FMP will ensure that the number of transient cycles experienced by the plant remain within the analyzed numbers of cycles and hence, the component CUFs remain below the values calculated in the fatigue evaluations. | ||
The Staff s review of the CUFen calculations cannot be reasonably compared to its review of service agreements to determine whether they conform to a template contract. | LRA Amendment 31, Attachment 1. | ||
In addition, if Entergy finds that CUFen for the recirculation, outlet or core spray nozzles exceeds the acceptance criteria, its TLAA demonstration has failed.In this case, it must revert to an aging management program consisting of inspection, repair and replacement. | The FMP does not satisfy the requirements of 10 CFR | ||
NEC has the right to evaluate this plan pursuant to its Contention | * 54.21(c)(1)(iii). As explained in this and NEC's prior briefing, § 54.2-1(c)(1)(iii) requires the applicant to "demonstrate that... | ||
[t]he effects of aging ... will be adequately managed for the period of extended operation" in the event that "the applicant cannot or chooses not to justify or extend an existing time-limited aging analysis." 10 CFR § 54.21(c)(1); Nuclear Regulatory Commission, Nuclear Power Plant License Renewal; Revisions, Final Rule, 60 FR 22461-01, 22480 (May 8, 1995). The FMP serves to confirnri the justification or projection of a TLAA. The demonstration required by 54.21(c)(1)(iii) substitutes for the validation or projection of a TLAA, and should consist of a 4 | |||
Entergy must complete its TLAA demonstration before the license is granted.II. ISSUE 2 Even if § 54.21(c) does allow an applicant to perform analyses to project a TLAA after a license is issued as an aging management plan pursuant to § 54.21 (c) (1) (iii), the applicant is still required to provide enough detail about how it intends to conduct this analysis in the LRA so as 6 to allow the NRC Staff and intervenors to evaluate whether the analyses will provide reasonable assurance of public safety. If insufficient detail is provided, the NRC will not have enough information to find reasonable assurance of public safety and would be arbitrary and capricious in approving the license renewal. Alternatively, the NRC must postpone its substantive review of the analyses and its finding of reasonable assurance until after a license is issued, thereby illegally curtailing intervenors' rights to a hearing before the ASLB on all issues material to the licensing decision, and violating NRC precedent holding that "the mechanism of post-hearing resolution must not be employed to obviate the basic findings prerequisite to an operating license." In the Matter of | |||
This is certainly true in the case of Entergy's CUFen analyses -- the record in this case to date demonstrates that the CUFen methodology is highly complex and its application allows for substantial "wiggle room" on the part of the analyst. NEC could not fully evaluate Entergy's methodology without reviewing Entergy's actual analyses, as well as substantial additional information regarding inputs and assumptions. | program'of component inspection, repair and replacement that specifies scope, method and frequency. | ||
The record in this case also demonstrates the value of public participation in the ASLB process. Since NEC filed its Contentions 2, 2A and 2B, the NRC has reexamined and changed its policies regarding at least one issue raised by NEC -the use of a simplified Green's function method to calculate CUF values. See, Exhibits NEC-JH_23, NEC-JH_24. | C. NEC CONTESTS ENTERGY'S AND THE NRC STAFF'S INTERPRETATION OF NRC REGULATIONS, NOT THE REGULATIONS THEMSELVES. | ||
Intervenor participation in this proceeding led the NRC to more closely scrutinize a previously approved method and reject it. Entergy's and the NRC Staff s interpretation of NRC regulations would short circuit this valuable process and facilitate a more superficial examination of important public safety issues.I 7 In summary, 10 CFR 5 54.21 (c)(1) and 54.29(a) together require thatEntergy's LRA must include either an analysis justifying or projecting its CUF TLAA, or an aging management plan, involving component inspection, repair and replacement, and specifying scope, method and frequency. | Both Entergy and the NRC Staff contend that NEC's argument that § 54.21(c) requires an applicant to perform analyses to justify or project a TLAA before a license is issued is an attack on NRC regulations that contravenes 10 CFR § 2.335(a). NEC contests the interpretation of the regulations, not the regulations themselves. If the NRC's guidance concerning Fatigue Monitoring Programs published in GALL Section X.M1 can be interpreted to'permit a licensee to'complete a TLAA justification or projection after a renewed license is issued, then this guidance is inconsistent with the plain language, structure and intent of §§ 54.21 (c) and 54.29(a) discussed in this and NEC's prior briefing. An intervenor may contest the validity of NRC guidance, including the GALL report, in a license-renewal proceeding. | ||
Entergy has chosen to perform analyses to project its CUF TLAA pursuant to 54.21(c)(1). | D.' THE NRC'S REVIEW OF ENTERGY'S CUFEN CALCULATIONS FOR THE FEEDWATER NOZZLE AND RECIRCULATION NOZZLE WOULD NOT BE "MINISTERIAL." | ||
It must complete this analysis prior to the close of ASLB proceeding and issuance of a.renewed license. It cannot complete analyses for the core spray and recirculation outlet nozzles pursuant to a license condition, or correct any flaws in its CUFen methodology pursuant to a licensing commitment. | The NRC Staff suggests that its post-licensing review of Entergy's CUFen calculations for the recirculation outlet and core spray nozzles using the same method Entergy used to calculate CUFen for the feedwater nozzle would be ministerial and therefore consistent with NRC precedent defining the proper scope of post-licensing resolution by the Staff. The Staff analogizes its review of the CUFen calculations to post-licensing review that was approved in In the Matterof Private FuelStorage, LL C. (IndependentSpent Fuel Storage Installation), CLI-00-1 3, 52 N.R.C. 23, 34 (2000). In that case, the Commission sanctioned post-license Staff review of certain licensee contracts, provided that they conformed to an ASLB-approved form contract. | ||
If Entergy's CUFen analyses fail to demonstrate that the components it evaluated will satisfy acceptance criteria through the end of the period of extended operation, Entergy must propose an aging management plan. NEC would then be entitled to review this plan pursuant to its Contention 2.July 15, 2008 New England Coalition, Inc.by: Andrew Raubvoge Karen Tyler SHEMS DUNKIEL IKASSEL & SAUNDERS PLLC For the firm Attorneys for NEC 8 | The Commission stated: | ||
", UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of Entergy Nuclear Vermont Yankee, LLC | 5 | ||
))CERTIFICATE OF SERVICE I, Christina Nielsen, hereby certify that copies of NEW ENGLAND COALITION, INC.'S SUPPLEMENTAL PREHEARING REPLY BRIEF in the above-captioned proceeding were served on the persons listed below, by U.S. Mail, first class, postage prepaid; and, where indicated by an e-mail address below, by electronic mail, on the 1 5 th of July, 2008.I Administrative Judge Alex S. Karlin, Esq., Chair Atomic Safety and Licensing Board Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | |||
/E-mail: ask2@nrc.gov Administrative Judge William H. Reed 1819 Edgewood Lane Charlottesville, VA 22902 | To reconcile post-hearing verification of a license condition by the NRC Staff with cases like Union of Concerned Scientists, Shoreham, and Indian Point Station, we must insist that the condition be precisely drawn so that the verification of compliance becomes a largely ministerial rather than an adjudicatory act - that is, the Staff verification efforts should be able to verify compliance without having to make overly complex judgments on whether a particular contrac't provision conforms, as a legal or factual matter, to promises [the licensee] has made. | ||
*" * | |||
* In short, evaluating whether contract provisions in fact function as intended is not merely a ministerial act; it calls for legal judgment. We think the Board went too far in putting evaluation of the legal effectiveness of service agreements into the hands of the NRC Staff without itself reviewing a sample service contract. | |||
Id. | |||
The Staffs analogy is inapposite. As the record in this proceeding to date demonstrates, Entergy's CUFen analyses are complex and' there is room for the exercise of discretion even in the application of a preapproved methodology. The Staff s review of the CUFen calculations cannot be reasonably compared to its review of service agreements to determine whether they conform to a template contract. In addition, if Entergy finds that CUFen for the recirculation, outlet or core spray nozzles exceeds the acceptance criteria, its TLAA demonstration has failed. | |||
In this case, it must revert to an aging management program consisting of inspection, repair and replacement. NEC has the right to evaluate this plan pursuant to its Contention 2. The CUFen calculations for the core spray and recirculation outlet nozzles therefore cannot take place after the close of ASLB proceedings. Entergy must complete its TLAA demonstration before the license is granted. | |||
II. ISSUE 2 Even if § 54.21(c) does allow an applicant to perform analyses to project a TLAA after a license is issued as an aging management plan pursuant to § 54.21 (c) (1)(iii), the applicant is still required to provide enough detail about how it intends to conduct this analysis in the LRA so as 6 | |||
to allow the NRC Staff and intervenors to evaluate whether the analyses will provide reasonable assurance of public safety. If insufficient detail is provided, the NRC will not have enough information to find reasonable assurance of public safety and would be arbitrary and capricious in approving the license renewal. Alternatively, the NRC must postpone its substantive review of the analyses and its finding of reasonable assurance until after a license is issued, thereby illegally curtailing intervenors' rights to a hearing before the ASLB on all issues material to the licensing decision, and violating NRC precedent holding that "the mechanism of post-hearing resolution must not be employed to obviate the basic findings prerequisite to an operating license." In the Matter of ConsolidatedEdison Company of New York, Inc (IndianPoint Station, Unit No. | |||
2), CLI-74-23, 7 A.E.C. 947, 950-52 (1974). | |||
An applicant could not provide sufficient information about many TLAA methodologies without actually performing the analysis and making it available for review by the NRC Staff and intervenors. This is certainly true in the case of Entergy's CUFen analyses -- the record in this case to date demonstrates that the CUFen methodology is highly complex and its application allows for substantial "wiggle room" on the part of the analyst. NEC could not fully evaluate Entergy's methodology without reviewing Entergy's actual analyses, as well as substantial additional information regarding inputs and assumptions. The record in this case also demonstrates the value of public participation in the ASLB process. Since NEC filed its Contentions 2, 2A and 2B, the NRC has reexamined and changed its policies regarding at least one issue raised by NEC - the use of a simplified Green's function method to calculate CUF values. See, Exhibits NEC-JH_23, NEC-JH_24. Intervenor participation in this proceeding led the NRC to more closely scrutinize a previously approved method and reject it. Entergy's and the NRC Staff s interpretation of NRC regulations would short circuit this valuable process and facilitate a more superficial examination of important public safety issues. | |||
I 7 | |||
In summary, 10 CFR 5 54.21 (c)(1) and 54.29(a) together require thatEntergy's LRA must include either an analysis justifying or projecting its CUF TLAA, or an aging management plan, involving component inspection, repair and replacement, and specifying scope, method and frequency. Entergy has chosen to perform analyses to project its CUF TLAA pursuant to 54.21(c)(1). It must complete this analysis prior to the close of ASLB proceeding and issuance of a.renewed license. It cannot complete analyses for the core spray and recirculation outlet nozzles pursuant to a license condition, or correct any flaws in its CUFen methodology pursuant to a licensing commitment. If Entergy's CUFen analyses fail to demonstrate that the components it evaluated will satisfy acceptance criteria through the end of the period of extended operation, Entergy must propose an aging management plan. NEC would then be entitled to review this plan pursuant to its Contention 2. | |||
July 15, 2008 New England Coalition, Inc. | |||
by: | |||
Andrew Raubvoge Karen Tyler SHEMS DUNKIEL IKASSEL & SAUNDERS PLLC For the firm Attorneys for NEC 8 | |||
", | |||
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. ) ASLBP No. 06-849-03-LR | |||
) | |||
(Vermont Yankee Nuclear Power Station) ) | |||
CERTIFICATE OF SERVICE I, Christina Nielsen, hereby certify that copies of NEW ENGLAND COALITION, INC.'S SUPPLEMENTAL PREHEARING REPLY BRIEF in the above-captioned proceeding were served on the persons listed below, by U.S. Mail, first class, postage prepaid; and, where indicated by an e-mail address below, by electronic mail, on the 1 5 th of July, 2008. | |||
I Administrative Judge Office of the Secretary Alex S. Karlin, Esq., Chair Attn: Rulemaking and Adjudications Staff Atomic Safety and Licensing Board Mail Stop: O-16C1 Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Washington, DC 20555-0001 / i E-mail: hearingdocket@nrc.gov E-mail: ask2@nrc.gov Sarah Hofmann, Esq. | |||
Administrative Judge Director of Public Advocacy William H. Reed Department of Public Service 1819 Edgewood Lane 112 State Street, Drawer 20 Charlottesville, VA 22902 Montpelier, VT 05620-2601 E-mail: whrcvillea~embaramail.com E-mail: sarah.hofmann@state.vt.us Office of Commission Appellate Adjudication Lloyd B. Subin, Esq. | |||
Mail Stop: O-16C1 Mary C. Baty, Esq. | |||
U.S. Nuclear Regulatory Commission Susan L. Uttal, Esq. | |||
Washington, DC 20555-0001 Jessica A. Bielecki, Esq. | |||
E-mail: OCAAmail@nrc.gov Office of the General Counsel Mail Stop 0-15 D21 Administrative Judge U.S. Nuclear Regulatory Commission Dr. Richard E. Wardwell Washington, DC 20555-0001 Atomic Safety and Licensing Board Panel E-mail: lbs3@nrc.gov; mcbt(nrc.gov; Mail Stop T-3 F23 susan.uttal@nrc.gov; jessica.bieleckignrc.gov U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 E-mail: rew@nrc.gov Anthony Z. Roisman,,Esq. | |||
National Legal Scholars Law Firm 84 East Thetford Road Lyme, NH 03768 E-mail: aroisman(~nationallegalscholars.com | |||
Marcia Carpentier, Esq. David R. Lewis, Esq. | |||
Lauren Bregman Matias F. Travieso-Diaz Atomic Safety and Licensing Board Panel Pillsbury Winthrop Shaw Pittman LLP Mail Stop T-3 F23 2300 N Street NW U.S. Nuclear Regulatory Commission Washington, DC 20037-1128 Washington, DC 20555-0001 E-mail: david.lewis@pillsburylaw.com E-mail: mxc7@nrc.gov matias.travieso-diazan illsburvlaw.com Lauren.Bregman@nrc.gov Diane Curran Peter C. L. Roth, Esq. Harmon, Curran, Spielberg, & Eisenberg, L.L.P. | |||
Office of the Attorney General 1726 M Street N.W., Suite 600 33 Capitol Street Washington, D.C. 20036 Concord, NH 03301 E-mail: dcurrangharmoncurran.com E-mail: Peter.rothgdoi.nh.gov, Matthew Brock Assistant Attorney General Environmental Protection Division Office of the Attorney General One Ashburton Place, 18 th Floor Boston, MA 02108 E-mail: Matthew.Brock@state.ma.us by:. | |||
Christina' Nielsen, Administrative Assistant SHEMS DUNKIEL KASSEL & SAUNDERS PLLC}} |
Revision as of 14:45, 14 November 2019
ML082050104 | |
Person / Time | |
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Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
Issue date: | 07/15/2008 |
From: | Tyler K New England Coalition, Shems, Dunkiel, Kassel, & Saunders, PLLC |
To: | Atomic Safety and Licensing Board Panel |
SECY RAS | |
References | |
50-271-LR, ASLBP 06-849-03-LR, RAS M-145 | |
Download: ML082050104 (10) | |
Text
AS -DOCKETED USNRC July 16, 2008 (8:00am)
OFFICE OF SECRETARY UNITED STATES RULEMAKINGS AND NUCLEAR REGULATORY COMMISSION ADJUDICATIONS' STAFF ATOMIC SAFETY AND LICENSING BOARD In the Matter of )
)
ENTERGY NUCLEAR VERMONT YANKEE, LLC ) Docket No. 50-271-LR and ENTERGY NUCLEAR OPERATIONS, INC. ) ASLBP No. 06-849-03-LR
)
(Vermont Yankee Nuclear Power Station) )
NEW ENGLAND COALITION, INC.
SUPPLEMENTAL PREHEARING REPLY BRIEF New England Coalition, Inc. ("NEC") submits this supplemental prehearing reply brief pursuant to the Board's Order of June 27, 2008.1 I. ISSUES JA AND 1B In Entergy's and the NRC Staffs view of the License Renewal process, an applicant need never include an analysis to project a TLAA to the end of the period of extended operation in the License Renewal Application (LRA), pursuant to 10 CFR ¶ 54.21 (c)(1)(ii). The licensee may instead make a generally stated "commitment" to perform this analysis as an aging management plan pursuant to 10 CFR 5 54.21 (c)(1)(iii) after license renewal is approved. This commitment to project the TLAA need not specify details of the methodology the applicant will employ, and can constitute the applicant's entire proposed "aging management plan." There is no place for public participation or the Atomic Safety and Licensing Board in this process; the NRC Staff will perform all substantive review of the analysis that may fully constitute a licensee's "aging management plan" after the close of any Board proceedings. Moreover, the NRC Staff does not consider "commitments" legally binding or enforceable under 10 CFR
- 2.206. As the I Licensing Board Order (Regarding the Briefing of Certain Legal Issues) (June 27, 2008).
(
State of Vermont has aptly observed, the Staff does not propose to eliminate review of safety analyses; it just wants to eliminate the role of the public and the Board in that review.
- The Atomic Energy Act (AEA) mandates the public participation Entergy and the NRC Staff would foreclose; the NRC may not exclude a material public-safety related issue from consideration by the Atomic Safety and Licensing Board at the request of an interested person.
S)
See, Union of ConcernedScientists v. UnitedStates Nuclear Re~gulatoy Commission, 735 F.2d 1437 (D.C.
CiT. 1984). Entergy's and the NRC Staff's arguments are without merit.
A. ENTERGY'S CUFEN ANALYSES ARE TO PROJECT A METAL FATIGUE TLAA TO THE END OF THE PERIOD OF EXTENDED OPERATION, PURSUANT TO 10 CFR § 54.21 (c)(1)(ii).
Entergy's CUFen analyses are a TLAA demonstration meant to substitute for the management of aging due to metal fatigue through inspection, repair and replacement of components; as such, it must be included in the license renewal application (LRA) pursuant to 10 CFR 54. 2 1 (c)(1)(ii). Entergy performed the CUFen analyses to project the CUF calculations that are part of Vermont Yankee's current licensing basis (CLB) to the end of the period of extended operations. The CUFen analyses are intended to demonstrate that a metal fatigue "aging management plan" involving component inspection, repair and replacement is unnecessary. If the CUFen analyses fail to demonstrate that vulnerable Vermont Yankee components will meet acceptance criteria through the end of the renewed license term, Entergy is required to amend it6 LRA to specifically describe the scope, method and frequency of a proposed inspection and maintenance program. 10 CFR § 54.2 1(c)(1). NEC would then be entitled to review and evaluate this program pursuant to its Contention' 2, now stayed by Board Order pending resolution of Contentions 2A and 2B.
2
Entergy contends that its CUFen analyses are not a projection'of a TLAA. This is incorrect. The CUFen analyses project CUF calculations, which are a TLAA incorporated in Vermont Yankee's CLB. Entergy's LRA states the following:
Fatigue evaluations were preformed in the design of the VYNPS Class 1 components designed in accordance with the requirements specified in ASME Section III. The fatigue evaluations are contained in analyses and stress reports, and because they are based on a number of transient cycles assumed for a 40-year plant life, these evaluations are considered TLAA.
- 4.3-1; See also, Exhibit NEC-JH_62, NRC Summary of Telephone Conference Call Held on August 20, 2007, Concerning the Vermont Yankee Nuclear Power Station License Renewal Application at Enclosure 2 ("Fatigue analyses based on a set of design transients and on the life of the plant are treated as TLAAs.").
/
The NRC Staff's explanation of its treatment of the CUFen reanalyses makes clear that the Staff's position elevates form over substance. It also underscores NEC's argument that the Staffsview of § 54.21(c)(1) renders § 54.21(c)(1)(ii) superfluous. The Staff claims that it did not change its interpretation of § 54.21 (c)(1) between August 2007 and May 2008. Rather, Entergy changed its view of which section of § 54.21 (c)(1) applies to the CUFen inalyses: "Entergy temporarily indicated that it would rely on § 54.21 (c)(ii), before ultimately relying upon 54.21(c)(1)(iii)." NRC Staffs Brief in Response to Board Order at 4. The NRC's regulations should not and do riot allow in applicant to alter the Staff's treatment of a safety analysis by citing to subsection (iii) instead of subsection (ii). Moreover, why would any applicant choose to include a TLAA projection in its LRA pursuant to § 54.21(c)(ii) if it can postpone NRC review of that analysis until after the close of any ASLB proceedings just by citing to § 54.21 (c)(1)(iii) instead? NEC submits that the answer to this question is never. Entergy's strategy in the Indian Point license renewal proceeding, discussed in NEC's Rebuttal Statement of Position at 6, bears this out. See, Exhibit NEC-JH-67. Entergy initially characterized its CUFen analysis as a TLAA 3
demonstration under § 54.21 (c) (ii) because that is what itis - it is an analysis to project the CUF TLAA to the end of the period of extended operation.
B. ENTERGY'S CUFEN ANALYSES ARE NOT AN AGING MANAGEMENT PLAN SUBJECT TO 10 CFR ý 54.21 (c)(1)(iii).
Both Entergy and the NRC Staff contend that the CUFen analyses are a component of a Fatigue Monitoring Program ("FMP"), consistent with'GALL Section X.M1. Entergy and the Staff further contend that the FMP is an "aging management plan" that satisfies the requirements of 10 CFR 5 54.21 (c)(1)(iii). These arguments misconstrue both the relationship of the CUFen analyses to the FMP and the meaning of § 54.21 (c)(1).
The CUFen analyses are not a component of the FMP. The FMP is a program implerhented during the license renewal period that tracks the number of transients for selected reactor coolant system components to confirm the validity of the CUFen TLAA analyses completed pursuant to
- 54.21 (c)(1)(ii) or 54.21 (c)(1)(i). As explained in Entergy's LRA:
The Fatigue Monitoring Program (FMP) tracks actual plant transients and evaluates these against the design transients ..... "[T]he FMP will ensure that the number of transient cycles experienced by the plant remain within the analyzed numbers of cycles and hence, the component CUFs remain below the values calculated in the fatigue evaluations.
LRA Amendment 31, Attachment 1.
The FMP does not satisfy the requirements of 10 CFR
- 54.21(c)(1)(iii). As explained in this and NEC's prior briefing, § 54.2-1(c)(1)(iii) requires the applicant to "demonstrate that...
[t]he effects of aging ... will be adequately managed for the period of extended operation" in the event that "the applicant cannot or chooses not to justify or extend an existing time-limited aging analysis." 10 CFR § 54.21(c)(1); Nuclear Regulatory Commission, Nuclear Power Plant License Renewal; Revisions, Final Rule, 60 FR 22461-01, 22480 (May 8, 1995). The FMP serves to confirnri the justification or projection of a TLAA. The demonstration required by 54.21(c)(1)(iii) substitutes for the validation or projection of a TLAA, and should consist of a 4
program'of component inspection, repair and replacement that specifies scope, method and frequency.
C. NEC CONTESTS ENTERGY'S AND THE NRC STAFF'S INTERPRETATION OF NRC REGULATIONS, NOT THE REGULATIONS THEMSELVES.
Both Entergy and the NRC Staff contend that NEC's argument that § 54.21(c) requires an applicant to perform analyses to justify or project a TLAA before a license is issued is an attack on NRC regulations that contravenes 10 CFR § 2.335(a). NEC contests the interpretation of the regulations, not the regulations themselves. If the NRC's guidance concerning Fatigue Monitoring Programs published in GALL Section X.M1 can be interpreted to'permit a licensee to'complete a TLAA justification or projection after a renewed license is issued, then this guidance is inconsistent with the plain language, structure and intent of §§ 54.21 (c) and 54.29(a) discussed in this and NEC's prior briefing. An intervenor may contest the validity of NRC guidance, including the GALL report, in a license-renewal proceeding.
D.' THE NRC'S REVIEW OF ENTERGY'S CUFEN CALCULATIONS FOR THE FEEDWATER NOZZLE AND RECIRCULATION NOZZLE WOULD NOT BE "MINISTERIAL."
The NRC Staff suggests that its post-licensing review of Entergy's CUFen calculations for the recirculation outlet and core spray nozzles using the same method Entergy used to calculate CUFen for the feedwater nozzle would be ministerial and therefore consistent with NRC precedent defining the proper scope of post-licensing resolution by the Staff. The Staff analogizes its review of the CUFen calculations to post-licensing review that was approved in In the Matterof Private FuelStorage, LL C. (IndependentSpent Fuel Storage Installation), CLI-00-1 3, 52 N.R.C. 23, 34 (2000). In that case, the Commission sanctioned post-license Staff review of certain licensee contracts, provided that they conformed to an ASLB-approved form contract.
The Commission stated:
5
To reconcile post-hearing verification of a license condition by the NRC Staff with cases like Union of Concerned Scientists, Shoreham, and Indian Point Station, we must insist that the condition be precisely drawn so that the verification of compliance becomes a largely ministerial rather than an adjudicatory act - that is, the Staff verification efforts should be able to verify compliance without having to make overly complex judgments on whether a particular contrac't provision conforms, as a legal or factual matter, to promises [the licensee] has made.
- " *
- In short, evaluating whether contract provisions in fact function as intended is not merely a ministerial act; it calls for legal judgment. We think the Board went too far in putting evaluation of the legal effectiveness of service agreements into the hands of the NRC Staff without itself reviewing a sample service contract.
Id.
The Staffs analogy is inapposite. As the record in this proceeding to date demonstrates, Entergy's CUFen analyses are complex and' there is room for the exercise of discretion even in the application of a preapproved methodology. The Staff s review of the CUFen calculations cannot be reasonably compared to its review of service agreements to determine whether they conform to a template contract. In addition, if Entergy finds that CUFen for the recirculation, outlet or core spray nozzles exceeds the acceptance criteria, its TLAA demonstration has failed.
In this case, it must revert to an aging management program consisting of inspection, repair and replacement. NEC has the right to evaluate this plan pursuant to its Contention 2. The CUFen calculations for the core spray and recirculation outlet nozzles therefore cannot take place after the close of ASLB proceedings. Entergy must complete its TLAA demonstration before the license is granted.
II. ISSUE 2 Even if § 54.21(c) does allow an applicant to perform analyses to project a TLAA after a license is issued as an aging management plan pursuant to § 54.21 (c) (1)(iii), the applicant is still required to provide enough detail about how it intends to conduct this analysis in the LRA so as 6
to allow the NRC Staff and intervenors to evaluate whether the analyses will provide reasonable assurance of public safety. If insufficient detail is provided, the NRC will not have enough information to find reasonable assurance of public safety and would be arbitrary and capricious in approving the license renewal. Alternatively, the NRC must postpone its substantive review of the analyses and its finding of reasonable assurance until after a license is issued, thereby illegally curtailing intervenors' rights to a hearing before the ASLB on all issues material to the licensing decision, and violating NRC precedent holding that "the mechanism of post-hearing resolution must not be employed to obviate the basic findings prerequisite to an operating license." In the Matter of ConsolidatedEdison Company of New York, Inc (IndianPoint Station, Unit No.
2), CLI-74-23, 7 A.E.C. 947, 950-52 (1974).
An applicant could not provide sufficient information about many TLAA methodologies without actually performing the analysis and making it available for review by the NRC Staff and intervenors. This is certainly true in the case of Entergy's CUFen analyses -- the record in this case to date demonstrates that the CUFen methodology is highly complex and its application allows for substantial "wiggle room" on the part of the analyst. NEC could not fully evaluate Entergy's methodology without reviewing Entergy's actual analyses, as well as substantial additional information regarding inputs and assumptions. The record in this case also demonstrates the value of public participation in the ASLB process. Since NEC filed its Contentions 2, 2A and 2B, the NRC has reexamined and changed its policies regarding at least one issue raised by NEC - the use of a simplified Green's function method to calculate CUF values. See, Exhibits NEC-JH_23, NEC-JH_24. Intervenor participation in this proceeding led the NRC to more closely scrutinize a previously approved method and reject it. Entergy's and the NRC Staff s interpretation of NRC regulations would short circuit this valuable process and facilitate a more superficial examination of important public safety issues.
I 7
In summary, 10 CFR 5 54.21 (c)(1) and 54.29(a) together require thatEntergy's LRA must include either an analysis justifying or projecting its CUF TLAA, or an aging management plan, involving component inspection, repair and replacement, and specifying scope, method and frequency. Entergy has chosen to perform analyses to project its CUF TLAA pursuant to 54.21(c)(1). It must complete this analysis prior to the close of ASLB proceeding and issuance of a.renewed license. It cannot complete analyses for the core spray and recirculation outlet nozzles pursuant to a license condition, or correct any flaws in its CUFen methodology pursuant to a licensing commitment. If Entergy's CUFen analyses fail to demonstrate that the components it evaluated will satisfy acceptance criteria through the end of the period of extended operation, Entergy must propose an aging management plan. NEC would then be entitled to review this plan pursuant to its Contention 2.
July 15, 2008 New England Coalition, Inc.
by:
Andrew Raubvoge Karen Tyler SHEMS DUNKIEL IKASSEL & SAUNDERS PLLC For the firm Attorneys for NEC 8
",
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. ) ASLBP No. 06-849-03-LR
)
(Vermont Yankee Nuclear Power Station) )
CERTIFICATE OF SERVICE I, Christina Nielsen, hereby certify that copies of NEW ENGLAND COALITION, INC.'S SUPPLEMENTAL PREHEARING REPLY BRIEF in the above-captioned proceeding were served on the persons listed below, by U.S. Mail, first class, postage prepaid; and, where indicated by an e-mail address below, by electronic mail, on the 1 5 th of July, 2008.
I Administrative Judge Office of the Secretary Alex S. Karlin, Esq., Chair Attn: Rulemaking and Adjudications Staff Atomic Safety and Licensing Board Mail Stop: O-16C1 Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Washington, DC 20555-0001 / i E-mail: hearingdocket@nrc.gov E-mail: ask2@nrc.gov Sarah Hofmann, Esq.
Administrative Judge Director of Public Advocacy William H. Reed Department of Public Service 1819 Edgewood Lane 112 State Street, Drawer 20 Charlottesville, VA 22902 Montpelier, VT 05620-2601 E-mail: whrcvillea~embaramail.com E-mail: sarah.hofmann@state.vt.us Office of Commission Appellate Adjudication Lloyd B. Subin, Esq.
Mail Stop: O-16C1 Mary C. Baty, Esq.
U.S. Nuclear Regulatory Commission Susan L. Uttal, Esq.
Washington, DC 20555-0001 Jessica A. Bielecki, Esq.
E-mail: OCAAmail@nrc.gov Office of the General Counsel Mail Stop 0-15 D21 Administrative Judge U.S. Nuclear Regulatory Commission Dr. Richard E. Wardwell Washington, DC 20555-0001 Atomic Safety and Licensing Board Panel E-mail: lbs3@nrc.gov; mcbt(nrc.gov; Mail Stop T-3 F23 susan.uttal@nrc.gov; jessica.bieleckignrc.gov U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 E-mail: rew@nrc.gov Anthony Z. Roisman,,Esq.
National Legal Scholars Law Firm 84 East Thetford Road Lyme, NH 03768 E-mail: aroisman(~nationallegalscholars.com
Marcia Carpentier, Esq. David R. Lewis, Esq.
Lauren Bregman Matias F. Travieso-Diaz Atomic Safety and Licensing Board Panel Pillsbury Winthrop Shaw Pittman LLP Mail Stop T-3 F23 2300 N Street NW U.S. Nuclear Regulatory Commission Washington, DC 20037-1128 Washington, DC 20555-0001 E-mail: david.lewis@pillsburylaw.com E-mail: mxc7@nrc.gov matias.travieso-diazan illsburvlaw.com Lauren.Bregman@nrc.gov Diane Curran Peter C. L. Roth, Esq. Harmon, Curran, Spielberg, & Eisenberg, L.L.P.
Office of the Attorney General 1726 M Street N.W., Suite 600 33 Capitol Street Washington, D.C. 20036 Concord, NH 03301 E-mail: dcurrangharmoncurran.com E-mail: Peter.rothgdoi.nh.gov, Matthew Brock Assistant Attorney General Environmental Protection Division Office of the Attorney General One Ashburton Place, 18 th Floor Boston, MA 02108 E-mail: Matthew.Brock@state.ma.us by:.
Christina' Nielsen, Administrative Assistant SHEMS DUNKIEL KASSEL & SAUNDERS PLLC