ML093060132

License Amendment No. 240, Revised Administrative Changes to Technical Specification 5.5.8, Inservice Testing Program, to Adopt TSTF-479-A and TSTF-497-A

ML093060132
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/23/2009
From:	Kalyanam N Plant Licensing Branch IV
To:	Entergy Operations
Kalyanam N, NRR/DORL/LPL4, 415-1480
References
TAC ME1829
Download: ML093060132 (23)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 23, 2009 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO.1 - ISSUANCE OF AMENDMENT RE:

MODIFICATIONS TO TECHNICAL SPECIFlCATIONS TO REFLECT REVISION TO 10 CFR 50.55a, TECHNICAL SPECIFICATION TASK FORCE CHANGE TRAVELERS TSTF-479-A AND TSTF-497-A (TAC NO. ME1829)

Dear Sir or Madam:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 240 to Renewed Facility Operating License No. DPR-51 for Arkansas Nuclear One, Unit NO.1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated August 5, 2009.

The amendment revises the Administrative Controls TS 5.5.8, "Inservice Testing Program," for consistency with the requirements of paragraph 50.55a(f)(4) of Title 10 of the Code of Federal Regulations (10 CFR), for pumps and valves which are classified as American Society of Mechanical Engineers (ASME) Code Class 1, Class 2, and Class 3. These changes are in accordance with the changes in NRC-approved Technical Specification Task Force (TSTF) change traveler TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a", and TSTF-497, "Limit Inservice Testing Program Surveillance Requirement 3.0.2 Application to Frequencies of 2 Years or Less."

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

N. Kaly Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosures:

1. Amendment No. 240 to DPR-51

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

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

DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 240 Renewed License No. DPR-51

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

A. The application for amendment by Entergy Operations, Inc. (EOI, the licensee),

dated August 5, 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, 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.

Enclosure 1

-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 Renewed Facility Operating License No. DPR-51 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment 1\10. 240, are hereby incorporated in the renewed license. EOI shall operate the facility in accordance with the Technical Specifications.

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

Attachment:

Changes to the Renewed Facility Operating License No. DPR-51 and Technical Specifications Date of Issuance: December 23, 2009

ATTACHMENT TO LICENSE AMENDMENT NO. 240 RENEWED FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Renewed Facility Operating License No. DPR-51 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.

Operating License REMOVE INSERT 3 3 Technical Specifications REMOVE INSERT 5.0-10 5.0-10

-3 (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 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; (6) EOI, pursuant to the Act and 10 CFR Parts 30 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 renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 steady state reactor core power levels not in excess of 2568 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 240, are hereby incorporated in the renewed license.

EOI shall operate the facility in accordance with the Technical Specifications.

(3) Safety Analysis Report The licensee's SAR supplement submitted pursuant to 10 CFR 54.21 (d),

as revised on March 14, 2001, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than May 20,2014.

(4) Physical Protection EOI shall fUlly implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Arkansas Nuclear One Physical Security Plan, Training and Qualifications Plan, and Safeguards Contingency Plan," as submitted on May 4,2006.

Renewed License No. DPR-51 Amendment No. 240 Revised by letter dated July 18, 2007

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.6 (Not Used).

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel. Surface and volumetric examination of the reactor coolant pump flywheels will be conducted coincident with refueling or maintenance shutdowns such that during 10 year intervals all four reactor coolant pump flywheels will be examined. Such examinations will be performed to the extent possible through the access ports, i.e., those areas of the flywheel accessible without motor disassembly. The surface and volumetric examination may be accomplished by Acoustic Emission Examination as an initial examination method. Should the results of the Acoustic Emission Examination indicate that additional examination is necessary to ensure the structural integrity of the flywheel, then other appropriate NDE methods will be performed on the area of concern.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program inspection frequencies.

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

a. Testing frequencies applicable to the ASME Code For Operation and Maintenance (OM) of Nuclear Power Plants and applicable Addenda as follows:

ASME OM Code terminology for Required Frequencies for performing inservice testing activities inservice testing activities Monthly At least once per 31 days Every 6 weeks At least once per 42 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.

ANO-1 5.0-10 Amendment No. ~,~, 240

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT 1\10. 240 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-51 ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNIT NO.1 DOCKET 1\10. 50-313 1.0 II\ITRODUCTION By letter dated August 5,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092180256), Entergy Operations, Inc. (Entergy) (the licensee),

submitted a license amendment request (LAR) to modify Technical Specifications (TSs) for Arkansas Nuclear One, Unit 1, to incorporate Technical Specification Task Force (TSTF) change travelers TSTF-479 and TSTF-497.

Specifically, the amendment modifies TS 5.5.8, "Inservice Testing Program," and revises TS 5.5.8.a which replaces references to Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code with references to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), TS 5.5.8.b which restricts extension of testing frequencies to those frequencies specified as 2 years or less, and TS 5.5.8.d which replaces references to the ASME Boiler and Pressure Vessel Code with references to the ASME OM Code. These changes are in accordance with the changes in Nuclear Regulatory Commission (NRC)-approved TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF-497, "Limit Inservice Testing Program Surveillance Requirement 3.0.2 Application to Frequencies of 2 Years or Less."

2.0 REGULATORY EVALUATIOI\I The regulations in Section 50.55a, "Codes and standards," of Title 10 of the Code of Federal Regulations (10 CFR) define the requirements for applying industry codes to each licensed nuclear powered facility. Licensees are required by 10 CFR 50.55a(f)(4 )(i) to prepare programs to perform inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves during the initial 120-month interval. The regulations require that programs be developed using 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 Enclosure 2

-2 modification identified in paragraph (b). The regulations also require that the inservice testing programs be 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. NRC amended 10 CFR 50.55a(f)(4)(ii) to require licensees to update their inservice testing programs to the latest edition of the ASME OM Code, which was incorporated by reference into 10 CFR 50.55a(b).

The proposed changes in the LAR to replace references to Section XI of the ASME Boiler and Pressure Vessel Code with updated references to the ASME OM Code in TS 5.5.8, "Inservice Testing Program," are in accordance with 10 CFR 50.55a.

In accordance with 10 CFR 50.36(c)(3), surveillance requirements (SR) are "requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The LAR proposes to limit the TS 5.5.8, "Inservice Testing Program," SR 3.0.2 application to testing frequencies of 2 years or less. As discussed in Section 3.0 below, the proposed changes will continue to assure that SRs will maintain the necessary quality of systems and components so that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Therefore, the proposal continues to satisfy 10 CFR 50.36(c)(3).

3.0 TECHNICAL EVALUATION

As stated in Section 2.0 above, 10 CFR 50.55a(f)(4)(ii) requires licensees to update their inservice testing programs to the latest edition of the ASME OM Code. The licensee's revision to TS 5.5.8, "Inservice Testing Program," parts a and d, is administrative in nature in that the TSs are updated to incorporate the latest edition of the ASME OM Code, as required by 10 CFR 50.55a. The proposed change to update the Inservice Testing Program to the latest edition of the ASME OM Code is consistent with TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a."

TS 5.5.8.a currently lists various specific testing frequencies for the Inservice Testing Program.

TS 5.5.8.b currently states that the provisions of SR 3.0.2 are applicable to TS 5.5.8.a. The LAR proposes to modify TS 5.5.8.b so that the provisions of SR 3.0.2 are applicable to other normal and accelerated testing frequencies that are not specifically listed in TS 5.5.8.a, and are specified as less than 2 years in the Inservice Testing Program. The proposed changes are consistent with TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a" and TSTF-497, Revision 0, "Limit Inservice Testing Program Surveillance Requirement 3.0.2 Application to Frequencies of 2 Years or Less." The NRC staff has previously determined that the provisions of SR 3.0.2, when applied to normal and accelerated testing frequencies as specified as 2 years or less in the Inservice Testing Program, will continue to assure that SRs will maintain the necessary quality of systems and components so that facility operation will be within safety limits, and that the limiting conditions for operation will be met. TSTF-479, Revision 0, was approved by the NRC on December 6, 2005 (ADAMS Accession No. ML053460302), and TSTF-497, Revision 0, was approved by the NRC on October 4,2006 (ADAMS Accession No. ML062780321).

-3 3.1

SUMMARY

The changes proposed by TSTF-497 enhance the intention to apply the 25 percent inservice testing interval extension for SR 3.0.2 to test frequencies of 2 years or less. The NRC staff concludes that the proposed changes are consistent with the requirements as contained in 10 CFR 50.36. On this basis, the NRC staff concludes that the changes proposed by TSTF-497 are acceptable.

The changes proposed by TSTF-479 revise references in the TS Administrative Controls Inservice Test Program and Bases (e.g., from Section XI of the ASME Boiler and Pressure Vessel Code to the ASME OM Code) thereby reflecting the current edition of the Code specified in 10 CFR 50.55a(b)(3). The TS Inservice Testing Program was revised to indicate that the provisions of SR 3.0.2 are applicable to other inservice testing Frequencies that are not specified in the program. The Inservice Testing Program may have frequencies for testing that are based on risk and do not conform to standard testing frequencies specified in the TS. The staff concluded that the proposed revision to adopt the changes to TS 5.5.8.b is consistent with TSTF-497 and is, therefore, acceptable.

4.0 STATE CONSULTATION

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

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 October 6,2009 (74 FR 51330). 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: Aron Lewin Date: December 23, 2009

ML093060132 *SE memo dated OFFICE NRRlLPL4/PM NRRlLPL4/LA DIRS/ITSB/BC DC/lCPTB/BC OGC NRRlLPL4/BC NRRlLPL4/PM NKalyanam NDiFrancesco NAME NKalyanam JBurkhardl RElliolt' YHuang JSuttenberg MMarkley for DATE 11/5/09 11/5/09 9/10109 11/12/09 11/16/09 12/23/09 12/23/09