ML100200314

License Amendment, Revise Technical Specification 5.5.6, Inservice Testing Program, to Incorporate References to ASME Code for Operation and Maintenance of Nuclear Power Plants

ML100200314
Person / Time
Site:	River Bend
Issue date:	03/31/2010
From:	Wang A Plant Licensing Branch IV
To:	Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME1653
Download: ML100200314 (15)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 31, 2010 Vice President, Operations Entergy Operations, Inc.

River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775 SUB~IECT:

RIVER BEND STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: REVISE TECHNICAL SPECIFICATION 5.5.6, "INSERVICE TESTING PROGRAM," TO INCORPORATE REFERENCES TO ASME CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS (TAC NO. ME1653)

Dear Sir or Madam:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 167 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1 (RBS). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated June 29, 2009.

The amendment revises TS 5.5.6, "Inservice Testing Program," which currently contains references to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI as the source for the inservice testing (1ST) of ASME Code Class 1, 2, and 3 pumps and valves. The proposed changes delete the references to Section XI of the ASME Code and incorporate references to the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). In addition, the amendment changes will limit applying Surveillance Requirement (SR) 3.0.2 to surveillances with a frequency of 2 years or less. The proposed changes are consistent with the Improved Standard Technical Specifications (ISTS) in Technical Specification Task Force (TSTF) Change Travelers TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF-497, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less."

- 2 A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

~\\0 Alan B. Wang, Project Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosures:

1. Amendment No. 167 to NPF-47

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY GULF STATES LOUISIANA, LLC AND ENTERGY OPERATIONS, INC.

DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. NPF-47

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (the licensee), dated June 29, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 167 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f:::J D.- \\

~'c-5s,v--("u.O

~'V

\\.JJ--"

Michael 1. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. NPF-47 and Technical Specifications Date of Issuance: March 31, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Facility Operating License No. NPF-47 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.

Facility Operating License Remove -3 Technical Specifications Remove 5.0-10 5.0-10 5.0-11 5.0-11

-3 (3)

EOI, pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)

EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis. or instrument calibration or associated with radioactive apparatus or components; and (6)

EOI, pursuant to the Act and 10 CFR Parts 30,40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level EOI is authorized to operate the facility at reactor core power levels not in excess of 3091 megawatts thermal (100% rated power) in accordance with the conditions specified herein. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 167 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 167

5.5 Programs and Manuals 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

g.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary:

1.

for noble gases: s 500 mrem/yr to the total body and s 3000 mrem/yr to the skin, and

2.

for iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half-lives> 8 days: s 1500 mrem/yr to any organ;

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives> 8 days in gaseous effluents released from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j.

Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the cyclic and transient occurrences identified on USAR Table 3.98-22 to ensure that the reactor vessel is maintained within the design limits.

5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:

a.

Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

(continued)

RIVER BEND 5.0-10 Amendment No. 84, 167

5.5 Programs and Manuals 5.5 Programs and Manuals ASME OM Code and applicable Addenda terminology for Required frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b.

The provisions of SR 3.0.2 are applicable to the above required frequencies and to other normal and accelerated frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;

c.

The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d.

Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

5.5.7 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.

a.

Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N51 0-1989 at the system flowrate specified below

+/- 10%:

ESF Ventilation System Flowrate SGTS 12,500 cfm FBVS 10,000 cfm CRFAS 4,000 cfm (continued)

RIVER BEND 5.0-11 Amendment No. 81 165,167

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 167 TO FACILITY OPERATING LICENSE NO. NPF-47 ENTERGY OPERATIONS, INC.

RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458

1.0 INTRODUCTION

By application dated June 29,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091880420), Entergy Operations, Inc. (Entergy, the licensee),

requested changes to the Technical Specifications (TSs) for the River Bend Station, Unit 1 (RBS).

The amendment would revise TS 5.5.6, "Inservice Testing Program," which currently contains references to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI as the source for the inservice testing (1ST) of ASME Code Class 1,2, and 3 pumps and valves. The proposed changes would delete the references to Section XI of the ASME Code and incorporate references to the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). In addition, the amendment changes would limit applying Surveillance Requirement (SR) 3.0.2 to surveillances with a frequency of 2 years or less. The proposed changes are consistent with the Improved Standard Technical Specifications (ISTS) in Technical Specification Task Force (TSTF) Change Travelers TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a." and TSTF-497, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less."

2.0 REGULATORY EVALUATION

The regulations in paragraph 50.55a(f)(5)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), require that, "If a revised inservice test program for a facility conflicts with the technical specification for the facility, the licensee shall apply to the Commission for amendment of the technical specifications to conform the technical specification to the revised program."

The licensee shall submit this application, as specified in 10 CFR 50.4, at least 6 months before the start of the period during which the provisions become applicable, as determined by 10 CFR 50.55a(f)(4).

- 2 In 1990, the ASME published the initial edition of the ASME OM Code, which provides rules for 1ST of pumps and valves. The ASME OM Code was developed and is maintained by the ASME Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASME Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of rules for the 1ST of pumps and valves from the ASME,Section XI, Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. The ASME intended the ASME OM Code to replace Section XI rules for 1ST of pumps and valves, and the Section XI rules for 1ST of pumps and valves that had been incorporated by reference into NRC regulations have been deleted from Section XI. The RBS third 10-year interval 1ST program was updated to comply with the 200'1 Edition through the 2003 Addenda of the ASME OM Code as required by 10 CFR 50.55a(f)(4)(ii). As a consequence, the TS reference to Section XI of the ASME Code for 1ST requirements is a reference to a deleted portion of the ASME Code, and a revision to the TS is needed. Entergy's TS amendment dated June 9, 2009, was submitted, in part, to revise the TS to refer to the current ASME OM Code requirements.

NUREG-1434, Revision 3.0, "Standard Technical Specifications (STS) - General Electric Plants, BWR 6," dated June 2004, contains the improved STS for General Electric plants.

NUREG-1434, Revision 3.1 was modified via Change Travelers TSTF-479 in December 2005 and TSTF-497 in October 2006. TSTF-479 addressed changes to reflect revision of 10 CFR 50.55a, "Codes and standards," and TSTF-497 addressed changes to STS Section 5.5.7, "Inservice Testing Program," to reflect the NRC position that the provisions of SR 3.0.2 are applicable to other normal and accelerated frequencies specified as 2 years or less in the 1ST program.

3.0 TECHNICAL EVALUATION

3.1 Proposed Changes to TS 5.5.6, "Inservice Testing Program The proposed changes would revise the RBS TS to incorporate the changes identified in Change Travelers TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF-497, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less." The proposed changes will revise TS 5.5.6, "Inservice Testing Program," for consistency with the requirements of 10 CFR 50.55a(f)(4) for pumps and valves which are classified as ASME Code Class 1,2, and 3. The proposed changes will also limit applying SR 3.0.2 to surveillances with a frequency of 2 years or less.

Specifically, the current TS 5.5.6.a references, in part, the ASME Code as follows:

a.

Testing frequencies specified in Section XI of ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Required frequencies for Addenda terminology for performing inservice testing inservice testing activities

- 3 TS 5.5.6.a will be revised to read, in part, as follows:

a.

Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

ASME OM Code and applicable Addenda Required frequencies terminology for for performing inservice inservice testing testing activities Currently, TS 5.5.6.b reads as follows:

b.

The provisions of SR 3.0.2 are applicable to the above required frequencies for performing inservice testing activities; TS 5.5.6.b will be revised to read as follows:

b.

The provisions of SR 3.0.2 are applicable to the above required frequencies and to other normal and accelerated frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities; Currently, TS 5.5.6.d reads as follows:

d.

Nothing in the ASME Boiler and pressure Vessel Code shall be construed to supersede the requirements of any TS.

TS 5.5.6.d will be revised to read as follows:

d.

Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

3.2 Licensee's Evaluation In its June 29, 2009 submittal, the licensee states that the purpose of the 1ST programs is to assess the operational readiness of pumps and valves, to detect degradation that might affect component operability, and to maintain safety margins with provisions for increased surveillance and corrective action. The regulations in 10 CFR 50.55a define the requirements for applying industry codes to each licensed nuclear powered facility. Licensees are required by 10 CFR 50.55a(f)(4)(i) initially to prepare programs to perform inservice testing of certain ASME Code,Section III, Class 1, 2, and 3 pumps and valves during the initial 120-month interval. The regulations require that programs be developed utilizing the latest edition and addenda incorporated into paragraph (b) of 10 CFR 50.55a on the date 12 months prior to the date of issuance of the operating license subject to the limitations and modifications identified in paragraph (b). NRC regulations (10 CFR 50.55a(f)(4)(ii)) also require that the 1ST programs be

- 4 revised during successive 120-month intervals to comply with the latest edition and addenda of the Code incorporated by reference in paragraph (b), 12 months prior to the start of the interval.

Section XI of the ASME Code has been revised on a continuing basis over the years to provide updated requirements for the inservice inspection and testing of components. Until 1990, the ASME Code requirements addressing the 1ST of pumps and valves were contained in Section XI, Subsection IWP (pumps) and IWV (valves). In 1990, the ASME published the initial edition of the OM Code that provides the rules for the 1ST for pumps and valves. Since the establishment of the 1990 Edition of the ASME OM Code, the rules for the 1ST for pumps and valves are no longer being updated in ASME Code,Section XI. As identified in SECY-99-017, "Proposed Amendment to 10 CFR 50.55a," dated January 13, 1999 (ADAMS Accession No. ML090020134), the NRC has generally considered the evolution of the ASME Code to result in a net improvement in the measures for inspecting piping and components and testing pumps and valves.

The ASME OM Code will replace Section XI rules for 1ST of pumps and valves that had been incorporated by reference. The ASME Code,Section XI rules for 1ST of pumps and valves have been deleted.

The regulations in 10 CFR 50.55a(f)(3) require, in part, that ASME Code Class 1, 2, and 3 pumps and valves must meet the requirements of ASME OM Code. The RBS third 10-year interval 1ST program was updated to comply with the 2001 Edition and Addenda through 2003 of the ASME OM Code as required by 10 CFR 50.55a(f)(4)(ii). As a consequence, the TS 5.5.6 references to Section XI of the ASME Code for 1ST requirements result in references to a deleted portion of the ASME Code. The TS changes do not eliminate any 1ST requirements and do not affect Entergy's responsibility to seek relief from Code test requirements when they are impractical. The changes will eliminate the ASME Code inconsistency between the 1ST program and the TS as required by 10 CFR 50.55a(f)(5)(ii).

The changes to items TS 5.5.6.b will allow the provisions of SR 3.0.2 to be applied to "other specified ASME frequencies" and also limit use to frequencies "specified as 2 years or less in the 1ST Program." In its June 29, 2009, letter, the licensee describes these changes as follows:

For the first change, River Bend currently has the allowance to apply SR 3.0.2 to the specified ASME frequencies. This will include other frequencies associated in the program. This change is consistent with TSTF-479.

For the second portion of the change to TS 5.5.6.b, this revision will limit these allowances to frequencies of 2 years or less as identified in TSTF-497.

3.3

NRC Staff Evaluation

In 1990, the ASME published the initial edition of the ASME OM Code, which provides rules for 1ST of pumps and valves. The ASME OM Code was developed and is maintained by the ASME Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASME Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of rules for the 1ST of pumps and

- 5 valves from the ASME Code,Section XI, Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. The ASME intended the ASME OM Code to replace Section XI rules for 1ST of pumps and valves, and the Section XI rules for 1ST of pumps and valves that had been incorporated by reference into NRC regulations have been deleted from Section XI.

The regulations in 10 CFR 50.55a(f) require, in part, that ASME Code Class 1, 2, and 3 pumps and valves meet the testing requirements of the ASME OM Code. The RBS third 10-year interval 1ST program was updated to comply with the 2001 Edition through the 2003 Addenda of the ASME OM Code as required by 10 CFR 50.55a(f)(4)(ii). As a consequence, the TS reference to Section XI of the ASME Code for 1ST requirements results in a reference to a deleted portion of the ASME Code, and a revision to the TS is required. Entergy's TS amendment dated June 29, 2009, was submitted, in part, to revise the TS to reference the current ASME OM Code requirements.

The proposed changes to reference the ASME OM Code in TS 5.5.6 do not eliminate any inservice tests and do not relinquish the licensee of its responsibility to seek relief from Code test requirements. The changes, however, will eliminate the ASME Code inconsistency between the 1ST program and the TS as required by 10 CFR 50.55a(f)(5)(ii). The proposed changes will maintain consistency with the ASME Code requirements and implement a TS Bases Control Program consistent with TSTF-479 and NUREG-1434, Revision 3.0. Based on the above, the NRC staff concludes that this proposed change is administrative in nature and, therefore, is acceptable.

The proposed change to TS 5.5.6.b will allow the application of 25 percent extension provided for in SR 3.0.2 to all normal and accelerated frequencies specified in the 1ST program, but will limit the applicability to test intervals of 2 years or less. With the proposed change to TS 5.5.6.b, if a test frequency (e.g., quarterly) is augmented and increased (e.g., to a 6-week test frequency), it could also have the 25 percent extension applied. This is consistent with the intent that the extension would provide operational flexibility, but would not significantly degrade the reliability that results from performing the surveillance at a specified frequency. Further, the proposal to limit the applicability to frequencies of 2 years or less limits the maximum incremental time period, between surveillances, which could be added by the 25 percent extension, is consistent with the approved provisions in Change Traveler TSTF-497, and guidance provided in Section 6.0 of NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants," dated January 2005 (ADAMS Accession No. IVIL050550290). Without this limitation, some components, such as safety and relief valves, which may be tested at surveillance intervals significantly greater than 2 years, could have extensions applied which would be much greater than needed for operational flexibility. Based on the above, the NRC staff concludes that the proposed changes to TS 5.5.6.b are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.

- 6

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on August 25,2009 (74 FR 42928). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: John Y.S. Huang Date:

March 31, 2010

- 2 A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, IRN Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosures:

1. Amendment No. 167 to NPF-47

2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDciCptb Resource Ridsl\\lrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMRiverBend Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JHuang, NRRIDCI/CPTB ADAMS Accession No ML100200314

• SE memo OFFICE NRR/LPL4/PM NRR/LPL4/LA DIRS/ITSB/BC DCI/CPTB/BC OGC NRR/LPL4/BC NRR/LPL4/PM NAME ABWang JBurkhardl REliioll AMcMurtray*

DRolh MMarkley BSingal for ABWang DATE 3/10/10 3/9/10 3/16/10 1/11/10 3/24/10 3/31/10 3/31/10 OFFICIAL AGENCY RECORD