ML17297B774

E-mail Attachment Oct 27 2006 Notice of Availabilty TSTF-484

ML17297B774
Person / Time
Site:	Technical Specifications Task Force
Issue date:	10/27/2017
From:	Office of Nuclear Reactor Regulation
To:
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Download: ML17297B774 (4)

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63050 Federal Register / Vol. 71, No. 208 / Friday, October 27, 2006 / Notices 3 The Atomic Energy Act, as amended by the Energy Policy Act of 2005, authorizes NRC to regulate Ra-226 and NRC is in the process of amending its regulations for discrete sources of Ra-226.

4 Radioactive materials are to be considered aggregated or collocated if breaching a common physical security barrier (e.g., a locked door at the entrance to a storage room) would allow access to the radioactive material or devices containing the radioactive material.

5 If several radionuclides are aggregated, the sum of the ratios of the activity of each source, I of radionuclide, n, A (i,n), to the quantity of con-cern for radionuclide n, Q(n), listed for that radionuclide equals or exceeds one. [(aggregated source activity for radionuclide A) ÷ (quantity of con-cern for radionuclide A)] + [(aggregated source activity for radionuclide B) ÷ (quantity of concern for radionuclide B)] + etc. * *

• 1.

Guidance for Aggregation of Sources continued for other barriers within or NUCLEAR REGULATORY NRC supports the use of the behind the inner barrier. COMMISSION International Atomic Energy The following example illustrates the Associations (IAEA) source point: A lockable room has sources Notice of Availability of Model Safety categorization methodology as defined stored in it. Inside the lockable room, Evaluation on Technical Specification in IAEA Safety Standards Series No. there are two shielded safes with Improvement To Modify Requirements RS-G-1.9, Categorization of additional sources in them. Inventories Regarding LCO 3.10.1, Inservice Leak Radioactive Sources, (2005) (see http:// are as follows: and Hydrostatic Testing Operation www-pub.iaea.org/MTCD/publications/ The room has the following sources Using the Consolidated Line Item PDF/Pub1227_web.pdf) and as endorsed outside the safes: Cf-252, 0.12 TBq (3.2 Ci); Improvement Process by the agencys Code of Conduct for the Co-60, 0.18 TBq (4.9 Ci), and Pu-238, 0.3 TBq (8.1 Ci). Application of the unity rule AGENCY: Nuclear Regulatory Safety and Security of Radioactive Commission.

yields: (0.12 ÷ 0.2) + (0.18 ÷ 0.3) + (0.3 ÷ 0.6)

Sources, January 2004 (see http://www- = 0.6 + 0.6 + 0.5 = 1.7. Therefore, the sources ACTION: Notice of availability.

pub.iaea.org/MTCD/publications/PDF/ would require additional security measures.

Code-2004_web.pdf). The Code defines Shielded safe #1 has a 1.9 TBq (51 Ci) Cs-

SUMMARY

Notice is hereby given that a three-tiered source categorization 137 source and a 0.8 TBq (22 Ci) Am-241 the staff of the Nuclear Regulatory scheme. Category 1 corresponds to the source. In this case, the sources would Commission (NRC) has prepared a largest source strength (equal to or require additional security measures, model safety evaluation (SE) relating to greater than 100 times the quantity of regardless of location, because they each the modification of shutdown testing concern values listed in Table 1.) and exceed the quantities in Table 1.

Shielded safe #2 has two Ir-192 sources, requirements in technical specifications Category 3, the smallest (equal or (TS) for Boiling Water Reactors (BWR).

each having an activity of 0.3 TBq (8.1 Ci).

exceeding one-tenth the quantity of The NRC staff has also prepared a model In this case, the sources would not require concern values listed in Table 1.). additional security measures while locked in no-significant-hazards-consideration Additional security measures apply to the safe. The combined activity does not (NSHC) determination relating to this sources that are equal to or greater than exceed the threshold quantity 0.8 TBq (22 matter. The purpose of these models is the quantity of concern values listed in Ci). to permit the NRC to efficiently process Table 1, plus aggregations of smaller amendments that propose to modify sources that are equal to or greater than Because certain barriers may cease to LCO 3.10.1. The proposed changes the quantities in Table 1. Aggregation exist during source handling operations would revise LCO 3.10.1, and the only applies to sources that are (e.g., a storage location may be unlocked associated Bases, to expand its scope to collocated. during periods of active source usage),

include provisions for temperature Licensees who possess individual licensees should, to the extent excursions greater than [200] °F as a sources in total quantities that equal or practicable, consider two modes of consequence of inservice leak and exceed the Table 1 quantities are source usageoperations (active hydrostatic testing, and as a required to implement additional source usage) and shutdown (source consequence of scram time testing security measures. Where there are storage mode). Whichever mode results initiated in conjunction with an many small (less than the quantity of in the greatest inventory (considering inservice leak or hydrostatic test, while concern values) collocated sources barrier status) would require additional considering operational conditions to be whose total aggregate activity equals or security measures for each location.

Use the following method to in Mode 4. Licensees of nuclear power exceeds the Table 1 values, licensees are determine which sources of radioactive reactors to which the models apply to implement additional security material require implementation of the could then request amendments, measures.

Some source handling or storage Additional Security Measures (ASMs): confirming the applicability of the SE activities may cover several buildings,

• Include any single source equal to and NSHC determination to their or several locations within specific or greater than the quantity of concern reactors.

buildings. The question then becomes, in Table A. DATES: The NRC staff issued a Federal When are sources considered

• Include multiple collocated sources Register notice on August 21, 2006 (71 collocated for purposes of aggregation? of the same radionuclide when the FR 48561) that provided a model safety For purposes of the additional controls, combined quantity equals or exceeds evaluation (SE) and a model no sources are considered collocated if the quantity of concern. significant hazards consideration breaching a single barrier (e.g., a locked

• For combinations of radionuclides, (NSHC) determination relating to door at the entrance to a storage room) include multiple collocated sources of modification of requirements regarding would allow access to the sources. different radionuclides when the LCO 3.10.1, Inservice Leak and Sources behind an outer barrier should aggregate quantities satisfy the following Hydrostatic Testing Operation. The be aggregated separately from those unity rule: [(amount of radionuclide A) NRC staff hereby announces that the behind an inner barrier (e.g., a locked ÷ (quantity of concern of radionuclide model SE and NSHC determination may jlentini on PROD1PC65 with NOTICES source safe inside the locked storage A)] + [(amount of radionuclide B) ÷ be referenced in plant-specific room). However, if both barriers are (quantity of concern of radionuclide B)] applications to adopt the changes. The simultaneously open, then all sources + etc. . . . 1. staff will post a model application on within these two barriers are considered [FR Doc. E6-18066 Filed 10-26-06; 8:45 am] the NRC web site to assist licensees in to be collocated. This logic should be BILLING CODE 7590-01-P using the consolidated line item VerDate Aug<31>2005 16:53 Oct 26, 2006 Jkt 211001 PO 00000 Frm 00066 Fmt 4703 Sfmt 4703 E:\FR\FM\27OCN1.SGM 27OCN1

Federal Register / Vol. 71, No. 208 / Friday, October 27, 2006 / Notices 63051 improvement process (CLIIP) to revise Applicability incorporated into the first section of 3.0 the TS on LCO 3.10.1, Inservice Leak Licensees opting to apply for this TS while scram time testing is not and Hydrostatic Testing Operation. change are responsible for reviewing the discussed until the second half of staffs evaluation, referencing the section 3.0. The information provided in FOR FURTHER INFORMATION CONTACT: Tim the comment is captured in the second Kobetz, Mail Stop: O-12H2, Division of applicable technical justifications, and providing any necessary plant-specific half of section 3.0. Comment 6 was not Inspections and Regional Support, incorporated due to possible confusion Office of Nuclear Reactor Regulation, information. Each amendment application made in response to the regarding the term conservatively. In U.S. Nuclear Regulatory Commission, reviewing the TSTF-484, Revision 0 Washington, DC 20555-0001, telephone notice of availability will be processed submittal, the NRC has concluded that 301-415-1932. and noticed in accordance with there is reasonable assurance that the applicable rules and NRC procedures.

SUPPLEMENTARY INFORMATION: health and safety of the public will not Public Notices be endangered by operation in the Background proposed manner, such activities will be In a notice in the Federal Register dated August 21, 2006 (71 FR 48561), conducted in compliance with the Regulatory Issue Summary 2000-06, Commissions regulations, and the Consolidated Line Item Improvement the staff requested comment on the use of the CLIIP to process requests to revise issuance of the amendment will not be Process for Adopting Standard inimical to the common defense and Technical Specification Changes for the TS regarding LCO 3.10.1, Inservice Leak and Hydrostatic Testing security or to the health and safety of Power Reactors, was issued on March the public. Therefore, it was decided 20, 2000. The consolidated line item Operation. In addition, there have been several plant-specific amendment that comment 6 was not needed in order improvement process (CLIIP) is to justify TSTF-484, Revision 0 intended to improve the efficiency of requests to adopt changes similar to approval. The revised model SE is NRC licensing processes by processing those described in TSTF-484 and included in this notice for use by proposed changes to the standard notices have been published for these licensees. As described in the model technical specifications (STS) in a applications. TSTF-484, as well as the application prepared by the staff, manner that supports subsequent NRC staffs safety evaluation and model licensees may reference in their plant-license amendment applications. The application, may be examined, and/or specific applications to adopt TSTF-CLIIP includes an opportunity for the copied for a fee, at the NRC/s Public 484, the SE and NSHC determination.

public to comment on a proposed Document Room, located at One White change to the STS after a preliminary Flint North, 11555 Rockville Pike (first Model Safety Evaluation assessment by the NRC staff and a floor), Rockville, Maryland. Publicly U.S. Nuclear Regulatory Commission, finding that the change will likely be available records are accessible Office of Nuclear Reactor Regulation, offered for adoption by licensees. The electronically from the ADAMS Public Consolidated Line Item Improvement, CLIIP directs the NRC staff to evaluate Library component on the NRC Web Technical Specification Task Force any comments received for a proposed site, (the Electronic Reading Room). Change TSTF-484, Revision 0, Use of change to the STS and to either The staff received one response with TS 3.10.1 for Scram Time Testing reconsider the change or announce the seven comments following the notice Activities published August 21, 2006 (71 FR availability of the change for adoption 48561), soliciting comments on the 1.0 Introduction by licensees.

model SE and NSHC determination By application dated [Date], [Name of This notice involves the modification related to TSTF-484, Revision 0. The Licensee] (the licensee) requested of LCO 3.10.1. The proposed changes comments were offered by the TSTF in changes to the Technical Specifications would revise LCO 3.10.1, and the a letter dated September 20, 2006 (TS) for the [Name of Facility].

associated Bases, to expand its scope to (ADAMS# ML062650171). The The proposed changes would revise include provisions for temperature comments are administrative in nature Limiting Condition for Operation (LCO) excursions greater than [200] °F as a in that they provide clarification and do 3.10.1, and the associated Bases, to consequence of inservice leak and not have a material impact on the model expand its scope to include provisions hydrostatic testing, and as a SE and NSHC determination published for temperature excursions greater than consequence of scram time testing August 21, 2006 (71 FR 48561). TSTF [200] °F as a consequence of inservice initiated in conjunction with an comments that were incorporated leak and hydrostatic testing, and as a inservice leak or hydrostatic test, while include the comment on the Federal consequence of scram time testing considering operational conditions to be Register Notice for Comment and initiated in conjunction with an in Mode 4. This change was proposed comments 1, 3, 4, and 5 on the Model inservice leak or hydrostatic test, while for incorporation into the standard Safety Evaluation. The TSTF has been considering operational conditions to be technical specifications by the owners informed of NRC staff decision not to in Mode 4.

groups participants in the Technical incorporate comments 2 and 6.

Specification Task Force (TSTF) and is Comment 2 provides for additional 2.0 Regulatory Evaluation designated TSTF-484. TSTF-484 can be information about TSTF-484 regarding 2.1 Inservice Leak and Hydrostatic viewed on the NRCs web page utilizing scram time testing to be included in Testing. The Reactor Coolant System the Agencywide Documents Access and paragraph one of section 3.0. In the (RCS) serves as a pressure boundary and Management System (ADAMS). ADAMS original Model Safety Evaluation also serves to provide a flow path for the accession numbers are ML052930102 published for comment on August 21, circulation of coolant past the fuel. In (TSTF-484 Submittal), ML060970568 2006 (71 FR 48561), the first half of order to maintain RCS integrity, Section jlentini on PROD1PC65 with NOTICES (NRC Request for Additional section 3.0 discusses hydrostatic and XI of the American Society of Information, RAI), ML061560523 (TSTF leakage testing, while the second half of Mechanical Engineers (ASME) Pressure Response to NRC RAIs), and section 3.0 discusses scram time testing. Vessel Code requires periodic ML062650171 (TSTF Response to NRC NRC staff believe that there may be hydrostatic and leakage testing.

Notice for Comment). confusion if the comment is Hydrostatic tests are required to be VerDate Aug<31>2005 16:53 Oct 26, 2006 Jkt 211001 PO 00000 Frm 00067 Fmt 4703 Sfmt 4703 E:\FR\FM\27OCN1.SGM 27OCN1

63052 Federal Register / Vol. 71, No. 208 / Friday, October 27, 2006 / Notices performed once every ten years and than 120 days while SR 3.1.4.4 requires RCS is pressurized. Because of the leakage tests are required to be scram time testing to be conducted number of control rods that must be performed each refueling outage. following work on the CRD system or tested, it is possible for the inservice Appendix G to 10 CFR Part 50 states following fuel movement within the leak or hydrostatic test to be completed that pressure tests and leak tests of the affected core cell. Both SRs must be prior to completing the scram time test.

reactor vessel that are required by performed at reactor steam dome Under existing provisions, if scram time Section XI of the American Society of pressure greater than or equal to [800] testing can not be completed during the Mechanical Engineers (ASME) Pressure psig and prior to exceeding 40 percent LCO 3.10.1 inservice leak or hydrostatic Vessel Code must be completed before rated thermal power (RTP). test, scram time testing must be the core is critical. TSTF-484, Revision 0, Use of TS suspended. Additionally, if LCO 3.10.1 NUREG-1433, General Electric Plants, 3.10.1 for Scram Time Testing is not implemented and average reactor BWR/4, Revision 3, Standard Technical Activities, would modify LCO 3.10.1 to coolant temperature exceeds [200] °F Specifications (STS) and NUREG-1434, allow SR 3.1.4.1 and SR 3.1.4.4 to be while performing the scram time test, General Electric Plants, BWR/6, conducted in Mode 4 with average scram time testing must also be Revision 3, STS both currently contain reactor coolant temperature greater than suspended. In both situations, scram LCO 3.10.1, Inservice Leak and [200] °F. Scram time testing would be time testing is resumed during startup Hydrostatic Testing Operation. LCO performed in accordance with LCO and is completed prior to exceeding 40 3.10.1 was created to allow for 3.10.4, Single Control Rod percent RTP. TSTF-484, Revision 0, Use hydrostatic and leakage testing to be WithdrawalCold Shutdown. This of TS 3.10.1 for Scram Time Testing conducted while in Mode 4 with modification to LCO 3.10.1 does not Activities, modifies LCO 3.10.1 to allow average reactor coolant temperature alter the means of compliance with a licensee to complete scram time greater than [200] °F provided certain Criterion 10 of Appendix A to 10 CFR testing initiated during inservice leak or secondary containment LCOs are met. Part 50. hydrostatic testing. As stated earlier, TSTF-484, Revision 0, Use of TS since the current LCO 3.10.1 allows 3.10.1 for Scram Time Testing 3.0 Technical Evaluation testing to be conducted while in Mode Activities, modifies LCO 3.10.1 to allow The existing provisions of LCO 3.10.1 4 with average reactor coolant a licensee to implement LCO 3.10.1, allow for hydrostatic and leakage testing temperature greater than [200] °F, the while hydrostatic and leakage testing is to be conducted while in Mode 4 with proposed change does not introduce any being conducted, should average reactor average reactor coolant temperature new operational conditions beyond coolant temperature exceed [200] °F greater than [200] °F, while imposing those currently allowed. Completion of during testing. This modification does Mode 3 secondary containment scram time testing prior to reactor not alter current requirements for requirements. Under the existing criticality and power operations results hydrostatic and leakage testing as provision, LCO 3.10.1 would have to be in a more conservative operating required by Appendix G to 10 CFR Part implemented prior to hydrostatic and philosophy with attendant potential

50. leakage testing. As a result, if LCO safety benefits.

2.2 Control Rod Scram Time 3.10.1 was not implemented prior to It is acceptable to perform other Testing. Control rods function to control hydrostatic and leakage testing, testing concurrent with the inservice reactor power level and to provide hydrostatic and leakage testing would leak or hydrostatic test provided that adequate excess negative reactivity to have to be terminated if average reactor this testing can be performed safely and shut down the reactor from any normal coolant temperature exceeded [200] °F does not interfere with the leak or operating or accident condition at any during the conduct of the hydrostatic hydrostatic test. However, it is not time during core life. The control rods and leakage test. TSTF-484, Revision 0, permissible to remain in TS 3.10.1 are scrammed by using hydraulic Use of TS 3.10.1 for Scram Time Testing solely to complete such testing pressure exerted by the control rod Activities, modifies LCO 3.10.1 to allow following the completion of inservice drive (CRD) system. Criterion 10 of a licensee to implement LCO 3.10.1, leak or hydrostatic testing and scram Appendix A to 10 CFR part 50 states while hydrostatic and leakage testing is time testing.

that the reactor core and associated being conducted, should average reactor Since the tests are performed with the coolant, control, and protection systems coolant temperature exceed [200] °F reactor pressure vessel (RPV) nearly shall be designed with appropriate during testing. The modification will water solid, at low decay heat values, margin to assure that specified allow completion of testing without the and near Mode 4 conditions, the stored acceptable fuel limits are not exceeded potential for interrupting the test in energy in the reactor core will be very during any condition of normal order to reduce reactor vessel pressure, low. Small leaks from the RCS would be operation, including the effects of cool the RCS, and restart the test below detected by inspections before a anticipated operational occurrences. [200] °F. Since the current LCO 3.10.1 significant loss of inventory occurred. In The scram reactivity used in design allows testing to be conducted while in addition, two low-pressure emergency basis accidents (DBA) and transient Mode 4 with average reactor coolant core cooling systems (ECCS) injection/

analyses is based on an assumed control temperature greater than [200] °F, the spray subsystems are required to be rod scram time. proposed change does not introduce any operable in Mode 4 by TS 3.5.2, ECCS-NUREG-1433, General Electric Plants, new operational conditions beyond Shutdown. In the event of a large RCS BWR/4, Revision 3, STS and NUREG- those currently allowed. leak, the RPV would rapidly 1434, General Electric Plants, BWR/6, SR 3.1.4.1 and SR 3.1.4.4 require that depressurize and allow operation of the Revision 3, STS both currently contain control rod scram time be tested at low pressure ECCS. The capability of surveillance requirements (SR) to reactor steam dome pressure greater the low pressure ECCS would be conduct scram time testing when certain than or equal to [800] psig and before adequate to maintain the fuel covered jlentini on PROD1PC65 with NOTICES conditions are met in order to ensure exceeding 40 percent rated thermal under the low decay heat conditions that Criterion 10 of Appendix A to 10 power (RTP). Performance of control rod during these tests. Also, LCO 3.10.1 CFR Part 50 is satisfied. SR 3.1.4.1 scram time testing is typically requires that secondary containment requires scram time testing to be scheduled concurrent with inservice and standby gas treatment system be conducted following a shutdown greater leak or hydrostatic testing while the operable and capable of handling any VerDate Aug<31>2005 16:53 Oct 26, 2006 Jkt 211001 PO 00000 Frm 00068 Fmt 4703 Sfmt 4703 E:\FR\FM\27OCN1.SGM 27OCN1

Federal Register / Vol. 71, No. 208 / Friday, October 27, 2006 / Notices 63053 airborne radioactivity or steam leaks 7.0 References (GATT 1994), and Article XVI:4 of the that may occur during performance of 1. NUREG-1433, General Electric Plants, WTO Agreement. That request may be testing. BWR/4, Revision 3, Standard Technical found at http://www.wto.org contained The protection provided by the Specifications (STS), August 31, 2003. in documents designated as WT/DS350/

normally required Mode 4 applicable 2. NUREG-1434, General Electric Plants, 1 and WT/DS350/1/Add.1. USTR LCOs, in addition to the secondary BWR/6, Revision 3, Standard Technical invites written comments from the Specifications (STS), August 31, 2003. public concerning the issues raised in containment requirements required to

3. Request for Additional Information (RAI) this dispute. In connection with the be met by LCO 3.10.1, minimizes Regarding TSTF-484, April 7, 2006, ADAMS potential consequences in the event of issues raised in the request for accession number ML060970568. consultations, the public should be any postulated abnormal event during 4. Response to NRC RAIs Regarding TSTF-testing. In addition, the requested 484, June 5, 2006, ADAMS accession number aware that on March 6, 2006, the modification to LCO 3.10.1 does not ML061560523. Department of Commerce announced create any new modes of operation or 5. TSTF-484 Revision 0, Use of TS 3.10.1 that it will no longer use zeroing operating conditions that are not for Scram Times Testing Activities, May 5, when making average-to-average currently allowed. Therefore, the staff 2005, ADAMS accession number comparisons in an antidumping ML052930102. investigation. See 71 FR 11189.

finds the proposed change acceptable.

6. TSTF Response to NRC Notice for DATES: Although USTR will accept any 4.0 State Consultation Comment, September 20, 2006, ADAMS comments received during the course of accession number ML062650171.

the dispute settlement proceedings, In accordance with the Commissions Principal Contributor: Aron Lewin. comments should be submitted on or regulations, the [Name of State] State Dated at Rockville, Maryland this 12th of before November 15, 2006 to be assured official was notified of the proposed October 2006. of timely consideration by USTR.

issuance of the amendment. The State official had [no] comments. [If For the Nuclear Regulatory Commission. ADDRESSES: Comments should be comments were provided, they should Timothy Kobetz, submitted (i) electronically, to be addressed here]. Branch Chief, Technical Specifications FR0702@ustr.eop.gov, Attn: EC Zeroing Branch, Division of Inspections and Regional II (DS350) in the subject line, or (ii) by 5.0 Environmental Consideration Support, Office of Nuclear Reactor fax, to Sandy McKinzy at (202) 395-Regulation. 3640. For documents sent by fax, USTR The amendment changes a requests that the submitter provide a

[FR Doc. E6-18076 Filed 10-26-06; 8:45 am]

requirement with respect to installation confirmation copy to the electronic mail BILLING CODE 7590-01-P or use of a facility component located address listed above.

within the restricted area as defined in FOR FURTHER INFORMATION CONTACT:

10 CFR Part 20. The NRC staff has OFFICE OF THE UNITED STATES Elissa Alben, Assistant General Counsel, determined that the amendment TRADE REPRESENTATIVE Office of the United States Trade involves no significant increase in the Representative, 600 17th Street, NW.,

amounts, and no significant change in [Docket No. WTO/DS350] Washington, DC 20508, (202) 395-9622.

the types, of any effluents that may be released offsite, and that there is no WTO Dispute Settlement Proceeding SUPPLEMENTARY INFORMATION: USTR is significant increase in individual or Regarding Measures Related to providing notice that consultations have cumulative occupational radiation Zeroing and Certain Investigations, been requested pursuant to the WTO exposure. The Commission has Administrative Reviews and Sunset Understanding on Rules and Procedures previously issued a proposed finding Reviews Involving Products From the Governing the Settlement of Disputes that the amendment involves no European Communities (DSU). If such consultations should significant hazards consideration, and fail to resolve the matter and a dispute AGENCY: Office of the United States settlement panel is established pursuant there has been no public comment on Trade Representative. to the DSU, such panel, which would such finding issued on [Date] ([ ] FR ACTION: Notice; request for comments. hold its meetings in Geneva,

[ ]). Accordingly, the amendment meets the eligibility criteria for categorical Switzerland, would be expected to issue

SUMMARY

The Office of the United a report on its findings and exclusion set forth in 10 CFR States Trade Representative (USTR) is 51.22(c)(9). Pursuant to 10 CFR 51.22(b) recommendations within nine months providing notice that the European after it is established.

no environmental impact statement or Communities (EC) has requested environmental assessment need be consultations with the United States Major Issues Raised by the EC prepared in connection with the under the Marrakesh Agreement With respect to the measures at issue, issuance of the amendment. Establishing the World Trade the ECs request for consultations refers 6.0 Conclusion Organization (WTO Agreement) to the following:

concerning various measures relating to 1. The implementing regulations of The Commission has concluded, zeroing and antidumping duty orders on the U.S. Department of Commerce based on the considerations discussed certain products from the EC. The EC (DOC), § 19 CFR Part 351, in above, that: (1) There is reasonable alleges that determinations made by particular § 351.414(c)(2);

assurance that the health and safety of U.S. authorities concerning these 2. The methodology of the DOC for the public will not be endangered by products, and certain related matters, determining the dumping margin in operation in the proposed manner, (2) are inconsistent with Articles 1, 2.1, 2.4, reviews on the basis of the comparison such activities will be conducted in 2.4.2, 5.8, 9.1, 9.3, 9.5, 11, 18.3 and 18.4 of a weighted average normal value with jlentini on PROD1PC65 with NOTICES compliance with the Commissions of the Agreement on Implementation of individual export prices; regulations, and (3) the issuance of the Article VI of the General Agreement on 3. The determinations of dumping by amendment will not be inimical to the Tariffs and Trade 1994 (AD the DOC, the determinations of injury common defense and security or to the Agreement), Article VI of the General by the U.S. International Trade health and safety of the public. Agreement on Tariffs and Trade 1994 Commission (ITC), the DOC notices VerDate Aug<31>2005 16:53 Oct 26, 2006 Jkt 211001 PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 E:\FR\FM\27OCN1.SGM 27OCN1