ML15152A473

Public Notice of Application for Amendment to Facility Operating License

ML15152A473
Person / Time
Site:	Watts Bar
Issue date:	06/03/2015
From:	Dion J Watts Bar Special Projects Branch
To:	James Shea Tennessee Valley Authority
Kuntz R, NRR/DORL/LPLWB, 415-3733
References
TAC MF6286
Download: ML15152A473 (6)

Text

PUBLIC NOTICE THE U.S. NUCLEAR REGULATORY COMMISSION PROPOSES TO AMEND THE FACILITY OPERATING LICENSE FOR THE WATTS BAR NUCLEAR PLANT, UNIT 1 The U.S. Nuclear Regulatory Commission (NRC, the Commission) has received an application dated May 29, 2015, from the Tennessee Valley Authority (TVA, the licensee) for an exigent amendment to the facility operating license for the Watts Bar Nuclear Plant (WBN),

Unit 1 located in Rhea County, Tennessee.

The proposed exigent amendment would provide a one-time change to Technical Specification (TS) Table 3.3.4-1, Function 4a, RCS Hot Leg Temperature Indication, to permit the temperature indication for Reactor Coolant System (RCS) Loop 4 to be inoperable for the remainder of WBN Unit 1 Operating Cycle 13, the refueling outage for which is scheduled to start in September 2015. Specifically, the proposed exigent amendment would revise Note A at the bottom of TS Table 3.3.4-1, "Remote Shutdown System Instrumentation and Controls," to state: For Function 4a, the temperature indicator for RCS hot leg 4 is not required to be operable for the remainder of Cycle 13. Additionally, should WBN Unit 1 experience a shutdown prior to the WBN Unit 1 Cycle 13 refueling outage, the temperature indicator will be repaired prior to startup.

The request is necessary because on May 16, 2015, TVA discovered that Temperature Indicator (TI) 1-TI-68-65C was not operable. Upon the discovery of this condition, TVA entered TS 3.3.4, Remote Shutdown System, Condition A. Condition A requires restoration of the temperature indicator within 30 days. TVA has isolated the problem to components of the temperature indicator (modifier circuit or thermocouple) that are both located inside the Reactor Building Polar Crane Wall. The 30-day completion time for Condition A of TS 3.3.4 expires on June 15, 2015, at approximately 0448 EDT, at which point a plant shutdown is required.

Accordingly, TVA requested approval of the proposed TS change by June 14, 2015, and that the implementation of the revised TS be effective immediately to avoid the requirement to shutdown WBN Unit 1. The temperature indicator is one of four instruments that provide indication in the Auxiliary Control Room (ACR) for the hot leg temperature of RCS Loop 4. The other three instruments remain operable.

The licensee requested that the proposed amendment be processed on an exigent basis, in accordance with the provisions in Title 10 of the Code of Federal Regulations (10 CFR)

Section 50.91(a)(6). Under 10 CFR 50.91(a)(6)(i)(B), where the Commission finds that exigent circumstances exist, in that a licensee and the Commission must act quickly and that time does not permit the Commission to publish a Federal Register notice allowing 30 days for prior public comment, and it also determines that the amendment involves no significant hazards considerations, the Commission will use local media to provide reasonable notice to the public in the area surrounding a licensee's facility of the licensee's amendment and of its proposed determination that no significant hazards consideration is involved, consulting with the licensee on the proposed media release and on the geographical area of its coverage.

The licensee bases its claim of exigent circumstances on the following considerations.

TVA could not have reasonably anticipated the failure of the instrumentation. Although WBN Unit 1 did experience a failure of the RCS Loop 4 hot leg instrument in 2004, the issues in the 2004 failure resulted in a full scale reading. The issues associated with the current failure (failing low scale) have been isolated to the modifier circuit or the thermocouple. Nothing in the 2004 failure could have led TVA to reasonably anticipate the current failure. The repair of the affected instrumentation precludes repair at power because the affected instrumentation is located inside the Reactor Building Polar Crane Wall, which is a high dose area during power operations. The shutdown of the plant to implement the repairs is not necessary because the

remaining temperature indications available in the ACR are adequate to safely shutdown the unit should an emergency arise.

As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration using the standards in 10 CFR 50.92. The licensee and the NRC have evaluated the proposed change with regard to the determination of whether or not a significant hazards consideration is involved.

Operation of WBN Unit 1, in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed TS change to allow operation with only three of four loop remote shutdown indications for RCS hot leg temperature until the Cycle 13 refueling outage scheduled for September 2015 is only applicable to the following conditions:

A. Fire or smoke in the Main Control Room (MCR).

B. An evacuation of the MCR due to some other (non-fire) unspecified reason.

C. The design basis flood.

The inoperability of the one hot leg temperature indicator does not change the probability of occurrence for these events because the indicator is not an accident initiator. The hot leg temperature indicators on the four RCS loops are used for indication only and have no automatic control functions. During safe shutdown for an MCR evacuation event, design basis flood, or fire related event, no fuel damage is postulated to occur, nor is the integrity of the reactor coolant pressure boundary or containment barriers postulated to be lost. Sufficient redundancy exists with the operational instrumentation to ensure that decay heat removal functions are not adversely affected by this change. Therefore, the proposed change does not

involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed amendment will not create the possibility of a new or different kind of accident from any previously analyzed. The proposed TS change does not alter the function of the Remote Shutdown System, which is to achieve and maintain safe reactor shutdown from outside the MCR. The TS instrumentation and controls required are such that sufficient capability is retained for decay heat removal via the Steam Generators to provide the indication required for safe shutdown capabilities. The proposed change will not result in the installation of any new equipment or system. The hot leg temperature instrument is used for indication only and has no automatic control functions. No new operations procedures will be created by this change. Appropriate operational procedures will be updated to clarify that the RCS Loop 4 hot leg temperature indication in the ACR is not available during the remainder of Cycle 13. No new operating conditions or modes will be created by this proposed change. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

The proposed amendment will not involve a significant reduction in a margin of safety.

Sufficient redundancy exists with the operational instrumentation to ensure that decay heat removal functions are not adversely affected by this change. Because the conduit, cables, and equipment that provide hot leg temperature indication in the ACR are routed outside the Control Building, removal of the RCS Loop 4 hot leg temperature indication is acceptable due to the redundant paths not being affected by a Control Building fire. Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Following an initial review of this application, the requested amendment has been evaluated against the standards in 10 CFR 50.92 and the NRC has made a proposed

(preliminary) determination that the requested amendment involves no significant hazards considerations. Operation of WBN Unit 1 in accordance with the proposed amendment would not significantly increase the probability or consequences of any accident previously considered, nor create the possibility of a new or different kind of accident, nor significantly reduce any margin of safety.

If the proposed determination that the requested exigent license amendment involves no significant hazards consideration becomes final, the NRC will issue the amendment without first offering an opportunity for a public hearing. An opportunity for a hearing will be published in the Federal Register at a later date and any hearing request will not delay the effective date of the amendment.

If the NRC decides in its final determination that the requested exigent license amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register and, if a hearing is granted, it will be held before the amendment is issued.

Comments on the proposed determination of no significant hazards consideration may be (1) telephoned to Jessie Quichocho, Chief, Watts Bar Special Projects Branch, by collect call to 301-415-0209, or by facsimile to 301-415-1222, (2) e-mailed to Jessie.Quichocho@nrc.gov, or (3) submitted in writing to the Chief, Rules, Announcements and Directives Branch, Division of Administrative Services, Office of Administration, Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. All comments received by 5:00 p.m. on June 11, 2015, will be considered in reaching a final determination. A copy of the application may be examined electronically through the NRCs Agencywide Documents Access and Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html by using the Accession No. ML15149A511 and at the Commission's Public

Document Room (PDR), located at One White Flint North, Public File Area O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737, or by e-mail to pdr.resource@nrc.gov.