ML18145A094

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Correction to Amendment No. 19 Regarding Application to Allow Inoperable Reactor Coolant System Loop 3 Temperature Indication for Operating Cycle 2 (EPID-L-2018-LLA-0003)
ML18145A094
Person / Time
Site: Watts Bar  Tennessee Valley Authority icon.png
Issue date: 06/18/2018
From: Natreon Jordan
Plant Licensing Branch II
To: James Shea
Tennessee Valley Authority
Saba F
References
EPID L-2018-LLA-0003
Download: ML18145A094 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 18, 2018 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A Chattanooga, TN 37402 2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNIT 2-CORRECTION TO AMENDMENT NO. 19 REGARDING APPLICATION TO ALLOW INOPERABLE REACTOR COOLANT SYSTEM LOOP 3 TEMPERATURE INDICATION FOR OPERATING CYCLE 2 (EPID L-2018-LLA-0003)

Dear Mr. Shea:

By letter dated January 25, 2018 (Agencywide Documents Access and Management System Accession No. ML180228106), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 19 for the Watts Bar Nuclear Plant, Unit 2, Facility Operating License (FOL)

No. NPF-96. This amendment revised the FOL and Technical Specification (TS} Table 3.3.4 1, "Remote Shutdown System Instrumentation and Controls." The amendment authorized a one-time change to allow TS Table 3.3.4 1, Function 4a, Reactor Coolant System (RCS) hot leg Temperature Indication for RCS Loop 3 to be inoperable for the remainder of Watts Bar Unit 2 Operating Cycle 2.

Subsequent to the issuance of this amendment, the NRC staff identified the following editorial errors on pages 3 and 4 of the FOL:

On page 3, in License Condition (5) December 31, 2018, was typographically changed to December 31, 2017.

On page 4, in the second line of License Condition (9), typographically "NRC" was changed to "NRG."

On Page 4, Paragraph "E" was typographically changed to paragraph "F."

The NRC staff has determined that these errors, on the paragraphs not associated with Amendment 19, were made inadvertently. The corrections do not change any of the conclusions associated with the issuance of Amendment No. 19 and do not affect the associated notice to the public. The replacement license condition pages that corrected the above typographical errors are enclosed.

If you have any questions, please contact Farideh Saba at 301-415-1447 or farideh.saba@nrc.gov.

Docket No. 50-391

Enclosure:

Corrected License Pages for Amendment No. 19 cc: Listserv Sincerely,

,0)-,/ Natreon J. Jordan, Project Manager F"

Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ENCLOSURE Corrected Pages 3 and 4 of Facility Operating License No. NPF 96 for Amendment No. 19 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391

Unit 2 3-C.

The 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)

(2)

Maximum Power Level TV A is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal.

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 19 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

TVA shall implement permanent modifications to prevent overtopping of the embankments of the Fort Loudon Dam due to the Probable Maximum Flood by June 30, 2018.

(4)

PAD4TCD may be used to establish core operating limits for Cycles 1 and 2 only. PAD4TCD may not be used to establish core operating limits for subsequent reload cycles.

(5)

By December 31, 2018, the licensee shall report to the NRC that the actions to resolve the issues identified in Bulletin 2012-01, "Design Vulnerability in Electrical Power System," have been implemented.

(6)

The licensee shall maintain in effect the provisions of the physical security plan, security personnel training and qualification plan, and safeguards contingency plan, and all amendments made pursuant to the authority of 10 CFR 50.90 and 50.54(p ).

(7)

TVA shall fully implement and maintain in effect all provisions of the Commission approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The TVA approved CSP was discussed in NUREG-0847, Supplement 28, as amended by changes approved in License Amendment No. 7.

(8)

TVA shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility, as described in NUREG-0847, Supplement 29, subject to the following provision:

Facility License No. NPF-96 Amendment No. 19

4-TVA may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(9)

By May 31, 2018, TVA shall report that a listing organization acceptable to the NRC (as the Authority Having Jurisdiction) has determined that the fire detection monitoring panel in the main control room either meets the appropriate designated standards or has been tested and found suitable for the specified purpose.

(10)

TVA will verify for each core reload that the actions taken if Faw(Z) is not within limits will assure that the limits on core power peaking Fo(Z) remain below the initial total peaking factor assumed in the accident analyses.

(11)

TVA will implement the compensatory measures described in Section 3.4, "Additional Compensatory Measures," of TVA letter CNL-18-012, dated January 17, 2018, during the timeframe the temperature indicator for RCS hot leg 3 is not required to be operable for the remainder of Cycle 2.

If the RCS hot leg 3 temperature indicator is returned to operable status prior to the end of Cycle 2, then these compensatory measures are no longer required.

D.

The licensee shall have and maintain financial protection of such types and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

E.

This license is effective as of the date of issuance and shall expire at midnight on October 21, 2055.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by William M. Dean, Director Office of Nuclear Reactor Regulation Appendices:

1. Appendix A -

Technical Specifications

2. Appendix B -

Environmental Protection Plan Date of Issuance: October 22, 2015 Amendment No. 19

ML18145A094 OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DORL/LPL2-2/BC(A)

NAME FSaba BClayton BVenkataraman DATE 6/14/18/

6/14/18 6/18/18