ML14115A213
| ML14115A213 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/28/2014 |
| From: | Lyon C Plant Licensing Branch IV |
| To: | Reddemann M Energy Northwest |
| Lyon C | |
| References | |
| TAC MF3673 | |
| Download: ML14115A213 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968 April 28, 2014
SUBJECT:
COLUMBIA GENERATING STATION-SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE:
AMENDMENT REQUEST FOR CHANGING TECHNICAL SPECIFICATION TABLE 3.3.1.1-1, FUNCTION 7, "SCRAM DISCHARGE VOLUME WATER LEVEL-HIGH" (TAC NO. MF3673)
Dear Mr. Reddemann:
By letter dated March 24, 2014, Energy Northwest submitted a license amendment request for Columbia Generating Station (CGS). The proposed amendment request would revise the specified function description and surveillance requirements (SRs) in Technical Specification Table 3.3.1.1-1, "Reactor Protection System [RPS] Instrumentation," Function 7, "Scram Discharge Volume [SDV] Water Level - High." The proposed changes support a planned upgrade to the CGS RPS SDV Water Level - High instrumentation. 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 (1 0 CFR), an amendment to the license (including the technical specifications) 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/relief 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 you supplement the application to address the information requested in the enclosure by May 9, 2014. 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 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 and associated time frame requested in this letter were discussed with Ms. L. Williams, et al., of your staff on April 24, 2014. If you have any questions regarding this matter, I may be reached at (301) 415-2296 or via e-mail at fred.lyon@nrc.gov.
Docket No. 50-397
Enclosure:
Supplemental Information Request cc w/encl: Distribution via Listserv Sincerely, CFJsn Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUPPLEMENTAL INFORMATION NEEDED SCRAM DISCHARGE VOLUME WATER LEVEL-HIGH ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397
- 1.
By letter dated March 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14098A400), Energy Northwest submitted a license amendment request (LAR) for Columbia Generating Station (CGS). The proposed amendment request would revise the specified function description and surveillance requirements (SRs) in Technical Specification (TS) Table 3.3.1.1-1, "Reactor Protection System [RPS] Instrumentation," Function 7, "Scram Discharge Volume [SDV] Water Level-High." The LAR supports planned upgrades to level sensing equipment different and diverse from the level sensing equipment currently used forTS Table 3.3.1.1-1, Function 7a. However, the LAR does not provide enough information regarding the proposed instrument forTS Table 3.3.1.1-1, Function 7b, for the NRC staff to be able to evaluate the proposed TS change. Please provide the following information:
- a.
Manufacturer and model of the level transmitter to be used forTS Table 3.3.1.1-1, Functions 7.a and 7.b. For Function 7.b, please provide a sketch of the typical instrument channel showing the "before change" and "after change" configurations.
- b.
Identify the power sources for the level sensing equipment forTS Table 3.3.1.1-1, Functions 7.a and 7.b.
- c.
Please clarify whether the instrumentation forTS Table 3.3.1.1-1, Function 7.a includes a trip unit.
- 2.
The LAR proposed adoption of Technical Specification Task Force (TSTF) traveler TSTF-493 (Revision 4), Option A Surveillance Notes, for Function 7.b. The LAR described the licensee's intent to replace the existing level float switches with electronic analog transmitters and trip units for Function 7.b. Installation of the proposed equipment for Function 7.b would require modifications to accommodate new level sensing instrument and trip unit. These changes could affect the TS Allowable Value (AV) and SRs for Function 7.b. Section 3.2 of the LAR stated that the setpoint calculations did not result in any changes to the TS AV for this function.
Implementation of TSTF-493, Note 1 requires the licensee to calculate appropriate magnitudes for AL T and AFT. Please provide information necessary to confirm that the AV remains the same, and provide a description of the methodology used to calculate the As-Left Tolerance (AL T), and As-Found Tolerance (AFT). Also, please provide a summary setpoint calculation for Function 7.b, and supporting design input data, consistent with Regulatory Guide 1.1 05, Revision 3, "Setpoints for Safety-Related Instrumentation," December 1999 (ADAMS Accession No. ML993560062), and Enclosure Regulatory Issue Summary (RIS) 2006-17, "NRC Staff Position on the Requirements of 10 CFR 50.36, 'Technical Specifications,' Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels," dated August 24, 2006 (ADAMS Accession No. ML051810077).
- 3.
The licensee proposed to add SRs forTS Table 3.3.1.1-1, Function ?.a. Please explain the rationale for the selection of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as the required periodicity for performance of the channel check function.
- 4.
The LAR stated the proposed level instrument forTS Table 3.3.1.1-1, Function 7.b would consist of level transmitter and trip unit. Please explain if the proposed instrument forTS Table 3.3.1.1-1, Function 7.b would support performance of the channel check and whether it would require periodic trip unit calibration.
- ML14115A213 OFFICE NRRIDORULPL4-1/PM NRRIDORULPL4-1/LA NAME FLyon JBurkhardt DATE 4/28/14 4/28/14 Sincerely, IRA/
Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLAJBurkhardt Resource RidsNrrPMColumbia Resource RidsRgn4MaiiCenter Resource RAivarado, NRR/DE/EICB DRahn, NRR/DE/EICB
- memo dated 4/8/14 NRRIDE/EICB/BC*
N RRIDORULPL4-1/BC N RRIDORULPL4-1/PM JThorp MMarkley FLyon 4/8/14 4/28/14 4/28/14