RBG-47361, Application for Technical Specification Changes Technical Specification Task Force Improved Standard Technical Specification Change Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.

Application for Technical Specification Changes Technical Specification Task Force Improved Standard Technical Specification Change Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.

ML13203A143
Person / Time
Site:	River Bend
Issue date:	07/16/2013
From:	Olson E Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-47361
Download: ML13203A143 (8)

Text

Entergy Operations, Inc.

River Bend Station "Entergy 5485 U.S. Highway 61N St. Francisville, LA 70775 Tel 225-381-4374 Eric Olson Site Vice President RBG-47361 July 16, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Application for Technical Specification Changes Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-535, "Revise Shutdown Margin Definition To Address Advanced Fuel Designs" River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47

Dear Sir or Madam:

In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Entergy Operations, Inc. (Entergy) is submitting a request for an amendment to the Technical Specifications (TS) for River Bend Station (RBS), Unit 1.

The proposed amendment modifies the TS definition of "Shutdown Margin " (SDM) to require calculation of the SDM at a reactor moderator temperature of 68 0 F or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new Boiling Water Reactor (BWR) fuel designs which may be more reactive at shutdown temperatures above 68 0 F.

Attachment 1 provides a description of the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change.

Although this request is neither exigent nor emergency, your prompt review is requested.

Once approved, the amendment shall be implemented within 60 days.

There are no commitments in this letter.

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RBG-47361 Page 2 of x If you have any questions or require additional information, please contact Mr. J. A. Clark at (225) 381-4177 I declare under penalty of perjury that the foregoing is true and correct. Executed on July 16, 2013 Sincerely, EO/JAC/bmb Attachments:

1. Analysis of Proposed Technical Specification Change

2. Proposed Technical Specification Changes (mark-up)

RBF1-13-0062 LAR 2013-11 cc: Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Blvd.

Arlington, TX 76011-4511 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn: Mr. Alan Wang MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section JiYoung Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 Public Utility Commission of Texas Attn: PUC Filing Clerk 1701 N. Congress Avenue P. 0. Box 13326 Austin, TX 78711-3326

Attachment 1 RBG-47361 Analysis of Proposed Technical Specification Change to RBG-47361 Page 1 of 3

1.0 DESCRIPTION

The proposed amendment modifies the Technical Specifications (TS) definition of "Shutdown Margin " (SDM) to require calculation of the SDM at a reactor moderator temperature of 68 0 F or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new Boiling Water Reactor (BWR) fuel designs which may be more reactive at shutdown temperatures above 68'F.

The availability of the model safety evaluation for this TS improvement was announced in the FederalRegister as part of the Consolidated Line Item Improvement Process (CLIIP).

2.0 BACKGROUND

The background for this application is adequately addressed by the NRC Notice of Availability of Model Safety Evaluation on Technical Specification Improvement to modify the requirements regarding Technical Specifications (TS) definition of "Shutdown Margin " (SDM).

Entergy is not proposing any variations or deviations from the TS changes described in the TSTF-535, Revision 0, or the applicable parts of the NRC staff's model safety evaluation.

3.0 TECHNICAL ANALYSIS

4.1 Applicability of Published Safety Evaluation Entergy has reviewed the model safety evaluation as part of the Federal Register Notice of Availability. This review included a review of the NRC staff's evaluation, as well as the information provided in TSTF-535. Entergy has concluded that the justifications presented in the TSTF-535 proposal and the model safety evaluation prepared by the NRC staff are applicable to River Bend Station Unit 1, and therefore justify this amendment for the incorporation of the proposed changes to the River Bend Station, Unit 1, TS.

Entergy is not proposing any variations or deviations from the TS changes described in the TSTF-535, Revision 0, or the NRC staff's model safety evaluation.

4.1 CONCLUSION

S In conclusion, based on the considerations discussed above, (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.

to RBG-47361 Page 2 of 3 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Determination Entergy requests adoption of TSTF-535, Revision 0, "Revise Shutdown Margin Definition to Address Advanced Fuel Designs," which is an approved change to the standard technical specifications (STS), into the River Bend Station, Unit 1 Technical Specifications (TS). The proposed amendment modifies the TS definition of "Shutdown Margin " (SDM) to require calculation of the SDM at a reactor moderator temperature of 68°F or a higher temperature that represents the most reactive state throughout the operating cycle.

Entergy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed change revises the definition of SDM. SDM is not an initiator to any accident previously evaluated. Accordingly, the proposed change to the definition of SDM has no effect on the probability of any accident previously evaluated. SDM is an assumption in the analysis of some previously evaluated accidents and inadequate SDM could lead to an increase in consequences for those accidents. However, the proposed change revises the SDM definition to ensure that the correct SDM is determined for all fuel types at all times during the fuel cycle. As a result, the proposed change does not adversely affect the consequences of any accident previously evaluated.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change revises the definition of SDM. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operations. The change does not alter assumptions made in the safety analysis regarding SDM.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

to RBG-47361 Page 3 of 3

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change revises the definition of SDM. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The proposed change ensures that the SDM assumed in determining safety limits, limiting safety system settings or limiting conditions for operation is correct for all BWR fuel types at all times during the fuel cycle.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, Entergy concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

5.2 Applicable Regulatory Requirements/Criteria A description of the proposed TS change and its relationship to applicable regulatory requirements was provided in the NRC Notice of Availability of the Model Safety Evaluation.

6.0 ENVIRONMENTAL CONSIDERATION

Entergy has reviewed the environmental evaluation included in the safety evaluation, as part of the CLIIP Notice of Availability of the Model Safety Evaluation. Entergy has concluded that the staff's findings presented in that evaluation are applicable to RBS, Unit 1 and the evaluation is hereby incorporated by reference for this application.

7.0 REFERENCES

1. Technical Specifications Task Force (TSTF) 535, "Revise Shutdown Margin Definition to Address Advanced Fuel Designs" Revision 0 Dated February 26, 2013.

2. NRC Model Safety Evaluation, Federal Register dated February 26, 2013.

Attachment 2 RBG-47361 Proposed Technical Specification Changes (mark-up)

Note, markup deletions identified by strikethrough (delete) and additions identified by underline (addition).

to RBG-47361 Page 1 of 1 Definitions 1.1 1.1 Definitions (continued)

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that: I

a. The reactor is xenon free;

b. The moderator temperature is > 68°F; corresponding to the most reactive state: and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME RESPONSE TIME consists of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80% of the turbine bypass capacity is established; and

b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

RIVER BEND 1.0-6 Amendment No. 94