ML070660581

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D.C. Cook Additional Draft RAI on 11/3/06 Application for Amendment Re. RTD Bypass Loop
ML070660581
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 03/07/2007
From: Tam P
NRC/NRR/ADRO/DORL/LPLIII-1
To: Scarpello M, Simpson S, Waters J
American Electric Power Co
References
TAC MD3462, TAC MD3463
Download: ML070660581 (3)


Text

From: Peter Tam To: Joe Waters; Michael Scarpello; Sue Simpson Date: 03/07/2007 1:04:50 PM

Subject:

D.C. Cook: Additional Draft RAI on 11/3/06 Application re. RTD Bypass Loop (TAC MD3462, 3)

Sue, Joe:

By the letter dated November 3, 2006, you submitted an application for amendment regarding replacement of the RTD and bypass loop piping with detectors mounted in the primary loop piping. I previously sent you 4 draft RAI questions regarding instrumentation. Subsequent to that, our instrumentation branch provided 2 more questions (Questions 5 and 6 below) and a list of references. Please call me to set up a conference call to discuss these questions.

(1) Enclosure 2, Section 4.0, discusses in general, the instrument uncertainty considerations for the calculations of the Allowable Value for OTT and OPT and Enclosure 3 provides the generic D. C. Cook Nuclear Plant (DCCNP) setpoint methodology found acceptable by the NRC. Please provide the detailed calculations, including all actual values used for uncertainties, that show justification for the increase in Allowable Values for OTT and OPT.

Also, please provide the source and/or justification for each uncertainty value used in the calculation.

(2) Enclosure 2, Section 3.0, states that the three hot leg scoops in each RCS loop will be modified to accept the new thermowells, which will contain the new, fast-response RTDs and that a hole will be drilled through the end of each scoop to facilitate flow past the RTD. How large is the drilled exit hole in comparison to the scoops water-entry cross-section size? How was it determined that this exit hole size was sufficient to not cause reduced flow through the scoop that could potentially add to a delay in the response time of the measurement of RCS temperature changes or even introduce another uncertainty in the measurement?

(3) Enclosure 2, Section 4.0, describes in general, the existing control board alarms and indicators that would detect an RTD element failure. It also mentioned the ability to easily connect the spare single element RTD that will be in each thermowell in case the primary RTD element fails. Please confirm that the RTD periodic surveillance will include both elements of the RTD in each thermowell.

(4) Enclosure 2, Section 3.0, describes in general, the arrangement whereby the three RTDs in an RCS loop will be electronically averaged to obtain a single hot-leg RCS temperature for that loop. Please describe the averaging function. Can a failure of one of the three RTDs in an RCS loop be automatically identified and taken out of the averaging equation by the new electronic averaging circuit?

(5) Enclosure 3 states that the NRC concluded that the DCCNP allowable value calculation methodology is acceptable in a letter dated June 1, 2005 (Reference 6). However, based on the staff concerns identified in the NRC Regulatory Issue Summary (RIS) 2006-17 (Reference 4), please provide a statement confirming that the setpoints for OTT and OPT are Limiting Safety System Settings for the variables on which a Safety Limit (SL) has been placed.

(6) The NRC letter to the NEI SMTF dated September 7, 2005 (Reference 1), describes Setpoint-Related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part A of the Enclosure to the letter provides LCO notes to be added to the TS, and Part B 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 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 6b and 6c, 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 inoperable or operable 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.

Reference 1 - Letter from Patrick L. Hiland, NRC, to NEI Setpoint Methods Task Force, "Technical Specification for Addressing Issues Related to Setpoint Allowable Values," dated September 7, 2005, available on the NRC public website in the Agency Documents Access and Management System (ADAMS), Accession No. ML052500004.

Reference 2 - Letter from Bruce A. Boger, NRC, to Alexander Marion, "Instrumentation, Systems, and Automatic Society (ISA) S67.04 Methods for Determining Trip Setpoints and Allowable Values for Safety-Related Instrumentation," dated August 23, 2005, ADAMS Accession No. ML051660447.

Reference 3 - Letter from James A. Lyons, NRC, to Alex Marion, Nuclear Energy Institute (NEI), "Instrumentation, Systems, and Automation Society S67.04 Methods for Determining Trip Setpoints and Allowable Values for Safety-Related Instrumentation," dated March 31, 2005, ADAMS Accession No. ML050870008.

Reference 4 - Nuclear Regulatory Commission Regulatory Issue Summary 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36 Technical Specification, Regarding Limiting Safety System Setting During Periodic Testing and Calibration of Instrument Channels, dated August 24, 2006, ADAMS Accession No. ML051810077.

Reference 5 - Technical Specification Task Force (TSTF) recommendation for Standard Technical Specification (STS) changes, TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions, Revision 0, January 27, 2006. ADAMS Accession No. ML060270503.

Reference 6 - Letter from J. Donohew, NRC, to Nazar, I&M, dated June 1, 2005, Paragraphs G.1.2.a, G.1.2.b, and G.3.2 of the Safety Evaluation for the conversion of the CNP TS to Improved Technical Specifications, ADAMS Accession No. ML050620034.

This e-mail aims solely to prepare you and others for the proposed conference call. This e-mail does not formally convey an NRC staff position, and does not formally request for additional information. We will discuss during the conference call how these draft questions will be disposed.

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation e-mail: pst@nrc.gov Tel.: 301-415-1451 CC: Eugene Eagle; Iqbal Ahmed; Samuel Miranda Mail Envelope Properties

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Subject:

D.C. Cook: Additional Draft RAI on 11/3/06 Application re. RTD Bypass Loop (TAC MD3462, 3)

Creation Date 03/07/2007 1:04:50 PM From: Peter Tam Created By: PST@nrc.gov Recipients Action Date & Time aep.com Transferred 03/07/2007 1:05:25 PM jrwaters (Joe Waters) mkscarpello (Michael Scarpello) sdsimpson (Sue Simpson) nrc.gov OWGWPO01.HQGWDO01 Delivered 03/07/2007 1:04:56 PM IXA CC (Iqbal Ahmed) nrc.gov OWGWPO02.HQGWDO01 Delivered 03/07/2007 1:04:56 PM EOE CC (Eugene Eagle) Opened 03/07/2007 1:16:13 PM nrc.gov TWGWPO01.HQGWDO01 Delivered 03/07/2007 1:04:56 PM SXM1 CC (Samuel Miranda) Opened 03/07/2007 1:06:13 PM Post Office Delivered Route aep.com OWGWPO01.HQGWDO01 03/07/2007 1:04:56 PM nrc.gov OWGWPO02.HQGWDO01 03/07/2007 1:04:56 PM nrc.gov TWGWPO01.HQGWDO01 03/07/2007 1:04:56 PM nrc.gov Files Size Date & Time MESSAGE 9187 03/07/2007 1:04:50 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed

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