ML081910106

Request for Supplemental Information Pertaining to a License Amendment Request to Revise the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value

ML081910106
Person / Time
Site:	Duane Arnold
Issue date:	07/11/2008
From:	Feintuch K NRC/NRR/ADRO/DORL/LPLIII-1
To:	Richard Anderson Nuclear Management Co
Feintuch K, NRR/DORL/LPL3-1, 415-3079
References
TAC MD8950
Download: ML081910106 (6)

Text

July 11, 2008 Mr. Richard L. Anderson Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785

SUBJECT:

DUANE ARNOLD ENERGY CENTER - REQUEST FOR SUPPLEMENTAL INFORMATION PERTAINING TO A LICENSE AMENDMENT REQUEST TO REVISE THE 4160 VOLT BUS UNDERVOLTAGE (DEGRADED VOLTAGE) MAXIMUM ALLOWED VALUE (TAC NO. MD8950)

Dear Mr. Anderson:

By letter dated May 30, 2008, Agencywide Documents Access and Management System (ADAMS) Accession No. ML081630205, the FPL Energy Duane Arnold, LLC, requested for a license amendment (LAR) to revise the upper limit of the allowable value for Function 2.a, 4.16 kV Emergency Bus Voltage (Degraded Voltage), Bus Undervoltage, in technical specifications (TS) Table 3.3.8.1-1, Loss of Power Instrumentation, from less than or equal to 3899 volts to less than or equal to 3822 volts.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff=s acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR),

an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.

In order to make the application complete, the NRC staff requests that FPL Energy Duane Arnold, LLC, supplement the application to address the information requested in the enclosure by July 17, 2008. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff=s request is not received

R. Anderson by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff=s detailed technical review by separate correspondence.

The information requested and associated time frame in this letter were discussed with Tony Browning of your staff on July 2, 2008.

If you have any questions, please contact me at (301) 415-3079.

Sincerely,

/RA/

Karl D. Feintuch, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc w/encl: See next page

ML081910106 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/EICB/BC NRR/LPL3-1/BC NAME KFeintuch THarris WKemper LJames DATE 7/10/08 7/9/08 7/10/08 7/11/08 REQUEST FOR SUPPLEMENTAL INFORMATION DUANE ARNOLD ENERGY CENTER LICENSE AMENDMENT REQUEST REVISION OF TECHNICAL SPECIFICATION (TS) TABLE 3.3.8.1-1, 4160 V BUS UNDERVOLTAGE By letter dated May 30, 2008, the FPL Energy Duane Arnold, LLC, requested a license amendment (LAR) to revise the upper limit of the allowable value for Function 2.a, 4.16 kV Emergency Bus Voltage (Degraded Voltage), Bus Undervoltage, in TS Table 3.3.8.1-1, Loss of Power Instrumentation, from less than or equal to 3899 volts to less than or equal to 3822 volts.

The staff has determined that in order to complete its review of the LAR acceptability, the staff needs the following supplemental information:

1. Setpoint Calculation Methodology: Provide documentation (including sample calculations) of the methodology used for establishing the limiting setpoint (or NSP) and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing described below. Indicate the related analytical limits and other limiting design values (and the sources of these values) for the setpoint.

2. Safety Limit (SL)-Related Determination: Provide a statement as to whether or not the setpoint is a limiting safety system setting for a variable on which a SL has been placed as discussed in 10 CFR 50.36(d)(1)(ii)(A). Such setpoints are described as ASL-Related@ in the discussions that follow. In accordance with 10 CFR 50.36(d)(1)(ii)(A), the following guidance is provided for identifying a list of functions to be included in the subset of limiting safety system settings (LSSSs) specified for variables on which SLs have been placed as defined in Standard Technical Specifications Sections 2.1.1, reactor core SLs and 2.1.2, reactor coolant system pressure SLs. This subset includes automatic protective devices in TSs for specified variables on which SLs have been placed that: (1) initiate a reactor trip; or (2) actuate safety systems. As such these variables provide protection against violating reactor core safety limits, or reactor coolant system pressure boundary safety limits.

Examples of instrument functions that might have LSSSs included in this subset in accordance with the plant-specific licensing basis, are pressurizer pressure reactor trip (pressurized-water reactors), rod block monitor withdrawal blocks (boiling-water reactors), feedwater and main turbine high water level trip (boiling-water reactors), and end of cycle recirculation pump trip (boiling-water reactors).

If the proposed setpoint is determined not to be SL-related, explain the basis for this determination.

3. For setpoints that is determined to be SL-related: The Nuclear Regulatory Commission (NRC) letter to the Nuclear Energy Institute SMTF dated September 7, 2005 (Agencywide Documents Access and Management System Accession No. ML052500004), describes setpoint-related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part AA@ of the Enclosure to the letter provides limiting condition for operation notes to be added to the TS, and Part AB@ includes a check list of the information to be provided in the TS Bases related to the proposed TS changes.

a. Describe whether and how you plan to implement the SRTS suggested in the September 7, 2005, letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c, below.

b. As-Found Setpoint evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system.

Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be Ainoperable@ or Aoperable but degraded.@ If the criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g.

plant test procedure) explain how the requirements of 10 CFR 50.36 are met.

c. As-Left Setpoint control: Describe the controls employed to ensure that the instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g. plant test procedure) explain how the requirements of 10 CFR 50.36 are met.

4. For setpoints that are not determined to be SL-related: Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the as-left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. Also, discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be Ainoperable@ or Aoperable but degraded.@ If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it is ensured that the controls will be implemented.

5. The LAR in Exhibit A, Section 3.2, DAEC Licensing Basis, states, The maximum allowable voltage for the 4160 volt Emergency Bus Undervoltage relays does not constitute a Limiting Safety System Setting (LSSS) Provide justifications for this statement, specifically considering the requirements for LSSS specified in 10 CFR 50.36(d)(1)(ii)(A).

Duane Arnold Energy Center cc:

Mr. J. A. Stall Mr. D. A. Curtland Executive Vice President, Nuclear and Plant Manager Chief Duane Arnold Energy Center Nuclear Officer 3277 DAEC Rd.

Florida Power & Light Company Palo, IA 52324-9785 P. O. Box 14000 Juno Beach, FL 33408-0420 Abdy Khanpour Vice President, Engineering Support Mr. M. S. Ross Florida Power & Light Company Managing Attorney P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408 P. O. Box 14000 Juno Beach, FL 33408-0420 Daniel K. McGhee Iowa Department of Public Health Ms. Marjan Mashhadi Bureau of Radiological Health Senior Attorney 321 East 12th Street Florida Power & Light Company Lucas State Office Building, 5th Floor 801 Pennsylvania Avenue, NW Des Moines, IA 50319-0075 Suite 220 Washington, DC 20004 Chairman, Linn County Board of Supervisors T. O. Jones 930 1st Street SW Vice President, Nuclear Operations Cedar Rapids, IA 52404 Mid-West Region Florida Power & Light Company Peter Wells, Acting Vice President, P. O. Box 14000 Nuclear Juno Beach, FL 33408 Training and Performance Improvement Florida Power & Light Company Steven R. Catron P. O. Box 14000 Manager, Regulatory Affairs Juno Beach, FL 33408-0420 Duane Arnold Energy Center 3277 DAEC Road Mark E. Warner Palo, IA 52324 Vice President, Nuclear Plant Support Florida Power & Light Company U. S. Nuclear Regulatory Commission P. O. Box 14000 Resident Inspector=s Office Juno Beach, FL 33408-0420 Rural Route #1 Palo, IA 52324 Mr. Mano Nazar Senior Vice President and Nuclear Chief Operating Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408 Last revised July 2, 2008