ML15174A267

Issuance of Amendments Regarding the Inservice Testing Program

ML15174A267
Person / Time
Site:	Oconee
Issue date:	07/07/2015
From:	Hall J Plant Licensing Branch II
To:	Batson S Duke Energy Carolinas
Hall J
References
TAC MF3756, TAC MF3757, TAC MF3758
Download: ML15174A267 (19)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2015 Mr. Scott Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3, ISSUANCE OF AMENDMENTS REGARDING THE INSERVICE TESTING PROGRAM (TAC NOS. MF3756, MF3757, AND MF3758)

Dear Mr. Batson:

The U.S. Nuclear Regulatory Commission (NRG) has issued the enclosed Amendment Nos. 393, 395, and 394 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station (ONS), Units 1, 2, and 3, respectively. The amendments consist of changes to the ONS operating licenses and Technical Specifications (TSs) in response to the application from Duke Energy Carolinas, LLC (Duke Energy), dated March 14, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14078A0.37). These amendments revise ONS TS 5.5.9, "lnservice Testing Program," to reflect the current edition of the American Society of Mechanical Engineers (ASME) Code that is referenced in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b). These changes were proposed for consistency with the NRG-approved Technical Specification Task Force (TSTF) Travelers TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF-497, Revision 0, "Limit lnservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less."

A copy of the NRC staff's related Safety Evaluation providing the technical bases for the staff's approval of the amendments is also enclosed.

S. Batson A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. If you have any questions, please contact me at 301-415-4032.

Sind:er y, O {J /J () *

.~1---.1~

Javes R. Hall, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50~270, and 50-287

Enclosures:

1. Amendment No. 393 to DPR-38

2. Amendment No. 395 to DPR-47

3. Amendment No. 394 to DPR-55

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 393 Renewed License No. DPR-38

1. ,The Nuclear Regulatory Commission (the Commission) ha$ found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility),

Renewed Facility Operating License No. DPR-38, filed by Duke Energy Carolinas, LLC (the licensee), dated March 14, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as '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 set forth in 10 CFR Chapter I; D. The issuance of this 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. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 393, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Sp!3cifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-38 and the Technical Specifications Date of Issuance: . JUl y 7, 2015

UNITED STATES NUCLEAR.REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 395

• Renewed License No. DPR-47

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

A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility),

Renewed Facility Operating License No. DPR-47, filed by Duke Energy Carolinas, LLC (the licensee}, dated March 14, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; D. The issuance of this 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 2

2. Accordingly, the license is hereby amended by page changes *to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.8 of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 395, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. *

3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No ..DPR-47 and the Technical Specifications Date of Issuance: July 7, 2015

UNITED STATES

.NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET N0 .. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 394 Renewed License No. DPR-55

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

A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility),

Renewed Facility Operating License No. DPR-55, .filed by Duke Energy Carolinas, LLC (the licensee), dated March 14, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; D. The issuance of this 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 3

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 394, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

• This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-55

• and the Technical Specifications Date of Issuance: July 7, 2015

ATTACHMENT TO LICENSE AMENDMENT NO. 393 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 LICENSE AMENDMENT NO. 395 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND LICENSE AMENDMENT NO. 394 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Reneyved Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages.are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages Licenses Licenses License No. DPR-38, page 3 License No. DPR-38, page 3 License No. DPR-47, page 3 License No. DPR-47, page 3 License No. DPR-55, page 3 License No. DPR-55, page 3 5.0-12 5.0-12 5.0-13 5.0-13

A Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 393 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ,-J1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and,any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-38 Amendment No. 393

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 395 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ,-J1 (d) hereof) and there is no demonstrable net detriment to applicant arising from th_at transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a priva,te or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-47 Amendment No. 395

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 394 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications ..

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers

• the cost of the transaction (as defined in ~1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-55 Amendment No. 394

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendori Surveillance Program, inspection frequendes, and acceptance criteria shall be in

• accordance with* Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, as amended by relief granted in accordance with 10 CFR 50.55a(a)(3).

The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.8 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for inspection of each reactor coolant pump flywheel.

At approximately three-year intervals, the bore and keyway of each reactor coolant pump flywheel shall be subjected to an inplace, volumetric examination.

Whenever maintenance or repair activities necessitate flywheel removal, a surface examination of exposed surfaces and a complete volumetric examination shall be performed if the interval measured from the previous such inspection is greater than 6 2/3 years. The interval may be extended up to one year to permit inspections to coincide with a planned outage.

5.5.9 lnservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves:

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

OCONEE UNITS 1, 2, & 3 5.0-12

-*-* & SJA Amendment Nos.393 J:35

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 lnservice Testing Program (continued)

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 lnservice 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.

5.5.10 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following provisions: *

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage.* The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.

OCONEE UNITS 1, 2, & 3 5.0-13 Amendment Nos. 333 _,_ -

335, &394

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555..0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 393 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 395 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND AMENDMENT NO. 394 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287

1.0 INTRODUCTION

By letter dated March 14, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14078A037), Duke Energy Carolinas, LLC (the licensee) requested to amend the operating license of Oconee Nuclear Station, Units 1, 2, and 3 (ONS). This license amendment request proposed changes to revise Technical Specification (TS) 5.5.9, "lnservice Testing Program," to provide consistency with the requirements of 10 CFR 50.55a(f)(4) for in-service testing (IST) of pumps and valves and remove requirements that are redundant to the requirements of Title 1O of the Code of Federal Regulations (10 CFR), Section 50.55a.

Specifically, the proposed changes would revise ONS TS 5.5.9, to be consistent with Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) Travelers TSTF-479, Revision 0, "Changes tO Reflect Revision of 10 CFR 50.55a," and TSTF-497, Revision 0, "Limit lnservice Testing Program SR [surveillance requirement] 3.0.2 Application to Frequencies of 2 Years or Less." TSTF-479 changes references in the IST program to the latest approved edition and addenc;ia of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). TSTF-497 adds an editorial change to clarify that the provisions of SR 3.0.2 are applicable to valves with IST intervals of 2 years or less.

In addition, the proposed amendment corrects an identified typographical error in TS 5.5.8, "Reactor Coolant P~mp Flywheel Inspection Program."

2.0 . REGULATORY EVALUATION The Commission's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36. That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls.

The NRC staff reviewed the proposed changes for compliance with 10 CFR 50.36, "Technical Specifications, and consistency with the precedent as established in NUREG-1430, "Standard Technical Specifications Babcock and Wilcox Plants, Revision 4, including changes incorporated via TSTF-479 and TSTF-497. These TSTF travelers affect changes to NUREG-1430 in STS 5.5.8, "lnservice Testing Program."

By letter dated December 6, 2005, the NRC approved Revision 0 of TSTF-479, "Changes to Reflect Revisions of 10 CFR 50.55a." TSTF-479, Revision 0, revises references in the STS Administrative Controls IST Program and STS Bases to reflect the current edition of the ASME Code specified in 10 CFR 50.55a(b). The NRC concluded that the revision was acceptable because the requirements of 10 CFR 50.55a adequately provide for IST.

By letter dated October 4, 2006, the NRC approved Revision 0 of TSTF-497, "Limit lnservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less." TSTF-497, Revision 0, revises the STS IST program by clarifying that the application of the 25 percent(%) IST interval extension allowed by SR 3.0.2 was for IST frequencies of two years or less. The NRC concluded that the revision was acceptable because it was an editorial change that clarified that the provisions of SR 3.0.2 (i.e., the 25% interval extension) are applicable to pumps and valves with IST intervals of two years or less.

The changes were also reviewed for compliance with the requirements for IST as contained in 10 CFR 50.55a(f)(4) for ASME Code Class 1, 2, and 3 pumps and valves: They are also consistent with the guidance in NUREG-1482, "Guidelines for In-service Testing at Nuclear Power Plants."

3.0 TECHNICAL EVALUATION

The licensee requested this amendment to Technical Specification (TS) 5.5.9, "lnservice Testing Program," for ONS. TS 5.5.9 would be revised to update references to the source of requirements for the lnservice Testing of the ASME Code Class 1, 2, and 3 pumps and valves, and to address the applicability of SR 3.0.2 to some non-standard pump and valve testing frequencies.

The licensee has stated that the proposed changes to the TS are consistent with NRG-approved TSTF Travelers TSTF-479-A, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," as modified by TSTF-497-A, Revision 0, "Limit lnservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less."

The licensee also proposes an editorial change (not part of either TSTF) to correct an identified typographical error in TS 5.5.8, "Reactor Coolant Pump Flywheel Inspection Program,"

{corresponding to NURE(3-1430 STS 5.5.7). In the third sentence of the paragraph, the word "urface" would be changed to "surface."

3.1 TSTF-479, Revision 0. "Changes to Reflect Revision of 10 CFR 50.55a" The purposes of the lnservice Testing Programs are 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. NRC regulation, 10 CFR 50.55a, defines the requirementl? for applying industry codes to each licensed nuclear powered facility. Licensees are required by 10 CFR 50.55a{f)(4)(i) to initially prepare programs to perform in-service testing of certain ASME Section Ill, Code Class 1, 2, and 3 pumps and valves during the initial 120-month interval. 10 CFR 50.55a{f)(5)(ii) requires licensees to update their IST program to the latest approved edition and addenda of the ASME OM Code incorporated by reference into 10 CFR 50.55a(b).

Section XI of the ASME Code has been revised 'on a continuing basis over the years to provide updated requirements for the in-service inspection and in-service testing of components. Until 1990, the ASME Code requirements addressing the IST of pumps and valves were contained in Section XI, Subsections IWP (pumps) and IWV (valves). In 1990, the ASME published the initial edition of the OM Code that provides the rules for the in-service testing of pumps and valves.

Since the establishment of the 1990 Edition of the OM Code, the rules for the in-service testing of pumps are no longer being updated in Section XI.

The TS change does not eliminate any tests and does not relinquish the licensee of its responsibility to seek relief from Code test requirements when they are impractical. The proposed change of the ASME Code reference from "ASME Section XI" to "ASME OM Code" eliminates the ASME Code inconsistency between the IST program and the TS, as required by 10 CFR 50.55a(f)(4)(ii); therefore, the NRC staff finds these proposed changes to be acceptable. This change is also consistent with the NRC's basis for approval of TSTF-479 in that the requirements of 10 CFR 50.SSa adequately provide for IST.

3.2 TSTF-497, Revision o. "Limit In-service Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less" TSTF-479, Rev. O, "Changes to Reflect Revision of 10 CFR 50.55a," revised the lnservice Testing Program located in Chapter 5 of the STS to reflect the latest approved version of the ASME Code.

TSTF-479 also revised paragraph b of NUREG-1430 STS 5.5.8 "In-service Testing Program;" by adding "The provisions of SR 3.0.2 are applicable to the above required Frequencies and other normal and accelerated Frequencies specified in the In-service Testing Program for performing in-service testirig activities." This requirement referred to the valves in the table above it, which only lists valves with a test frequency interval of 2 years or less.

In order to enhance the 2 years or less test frequency requirement, \

TSTF-497 revised the sentence in paragraph b to state: "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 In-service Testing Program for performing In-service testing activities." Without this limitation, some components, such as safety and relief valves that may be tested at surveillance intervals significantly greater than two years, could have extensions applied which would be much greater than needed for operational flexibility. This is an editorial change to clarify that SR 3.0.2 is applicable to pumps and valves with IST intervals of 2 years or less.

The proposed changes are consistent with the bases of the NRC's approval of TSTF-479 and TSTF-497. These changes are also consistent with the relevant portions of 10 CFR 50, 55a. Also, the staff concludes that the licensee's editorial change to ONS TS 5.5.8 is of a clarifying, non-technical nature. Therefore, the staff finds the proposed changes acceptable.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding, which was published in the Federal Register on March 31, 2015 (80 FR 17086). Accordingly, the amendments meet 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 amendments. *

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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: K. West Date: July 7, 2015

ML15174A267 *See memo OFFICE NRR/LPL2-1 /PM NRR/LPL2-1 /LA DSS/STSB/BC* OGC NAME RH all SFigueroa RElliott (MChernoff for) BHarris DATE 06/26/15 06/25/15 03/09/15 07/02/15 OFFICE NRR/LPL2-1/BC NRR/LPL2-1 /PM NAME RPascarelli (SWilliams for) RH all DATE 07/07/15 07/07/15