ML111300539

Fort Calhoun, Unit 1 - Draft Request for Additional Information, Round 2, Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifica

ML111300539
Person / Time
Site:	Fort Calhoun
Issue date:	05/10/2011
From:	Wilkins L E Plant Licensing Branch IV
To:	Hansher B R Omaha Public Power District
Wilkins, L E, NRR/DORL/LPL4, 415-1377
Shared Package
ML111300519	List: ML111300528 ML111300539
References
TAC ME4542
Download: ML111300539 (2)

Text

SECOND REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO RELOCATE OPERATING AND SURVEILLANCE REQUIREMENTS FOR THE POWER-OPERATED RELIEF VALVE, SAFETY VALVE POSITION, AND TAILPIPE TEMPERATURE INSTRUMENTATION FROM THE TECHNICAL SPECIFICATIONS OMAHA PUBLIC POWER DISTRICT, FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 By letter dated August 16, 2010, as supplemented by letters dated September 27, 2010 and April 6, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML102290067, ML102720964, and ML110970356, respectively), Omaha Public Power District (OPPD, the licensee) requested changes to the Technical Specifications (TSs) for Fort Calhoun Station, Unit 1 (FCS). The proposed changes would relocate operating and surveillance requirements (SRs) for the power-operated relief valve (PORV) position, safety valve position (PSV), and tail pipe temperature instrumentation from the FCS TSs to the FCS Updated Safety Analysis Report (USAR). Specifically the proposed changes would revise:

• TS Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions"

• TS Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls" TS Table 2-5, Functions 3, 4, and 5, the associated Notes a, b, c, and d, and TS Table 3-3, Functions 23 and 24, would be deleted from the FCS TSs and relocated to the FCS USAR.

TS Table 3-3 Function 21 will be revised to be consistent with NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," Revision 3.0. Additionally, the TS Table 2-5 associated Note e will be re-lettered as Note a and TS Table 2-5 footnote i to Note c will be deleted.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided by the licensee and determined that the following information is needed in order to complete its evaluation.

1. By letter dated August 16, 2010. the licensee proposed to revise the technical specification as follows: Enclosure Item 21, PORV Operation and Acoustic Position Indication is being revised to delete the words "and Acoustic Position Indication.

" Item 21.a, the frequency is being changed from "M" to "R" to reflect channel functional testing of PORV operation, which is more aligned with NUREG-1432 surveillance requirements.

The licensee also states:

The proposed change also revises SR 3.1, Table 3-3, Item 21 to maintain the existing channel functional test of the PORVs on a refueling frequency, which is aligned with NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants, Revision 3 [STS].

Please provide the exact SR number of STS to which the licensee is referring.

2. In addition, after the deletion of the words "and Acoustic Position Indication," Item 21 will read "PORV Operation" However, SR 3.4.12.6 of STS states:

"Perform CHANNEL FUNCTIONAL TEST on each required PORV, excluding actuation" with a FREQUENCY of 31 days (page 3.4.12-4).

Please explain the discrepancy and justify the proposed revision of the required SR frequency from "M" to "R."

3. By letter dated August 16, 2010, the licensee proposes to relocate the technical specification for maintaining and testing the acoustic monitors and the tail pipe temperatures Please provide the NRC staff with the proposed wording in the USAR or Technical Requirements Manual that will supplant the revised technical specification. Also, please describe the plan for identifying what channels will be required, how frequently they are to be tested, and what specific functionality is to be demonstrated by the proposed functional tests. In addition, provide the NRC staff with a description of how the proposed functional testing is to be conducted for each piece of equipment being functionally tested.

4. Please describe how the requirements for establishing limiting conditions for operations as described in 10 CFR 50.36 (c)(2)(ii)(A) Criterion 1 is still satisfied with respect to the detection of significant degradation of the reactor coolant pressure boundary associated with pressurizer steam leakage, after the proposed amendment goes into effect. In addition, please list the equipment and qualifications (e.g., EQ, seismic, power supply, etc.) that will be fulfilling this function. Enclosure