NLS2015080, Response to Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program

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Response to Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program
ML15188A349
Person / Time
Site: Cooper Entergy icon.png
Issue date: 06/30/2015
From: Limpias O
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2015080
Download: ML15188A349 (5)
v • d • e


Text

N Nebraska Public Power District Always there when you need us NLS2015080 June 30, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Response to Nuclear Regulatory Commnission Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program Cooper Nuclear Station, Docket No. 50-298, DPR-46

References:

1. Email from Siva Lingam, U.S. Nuclear Regulatory Commission, to Jim Shaw, Nebraska Public Power District, dated June 2, 2015, "Cooper - Relief Request (RR) RP-08 Associated with Comprehensive Pump Test Upper Limit and RR RP-09 Regarding Variance Around the Reference Values for Fifth Ten-Year Interval Pump IST Program (TAC Nos. MF5919 and MF5920)"
2. Letter from Oscar A. Limpias, Nebraska Public Power District, to the U.S.

Nuclear Regulatory Commission, dated March 19, 2015, "Fifth Ten-Year Interval Pump and Valve Inservice Testing Program Relief Requests"

Dear Sir or Madam:

The purpose of this letter is for the Nebraska Public Power District to respond to the Nuclear Regulatory Commission's Requests for Additional Information (RAI) (Reference 1) related to the Cooper Nuclear Station Fifth Ten-Year Interval Inservice Testing Relief Requests RP-08, "Comprehensive Pump Test Upper Limit" and RP-09, "Variance Around the Reference Values" (Reference 2).

The response to the specific RAI questions is provided in the attachment to this letter.

This letter does not contain any new regulatory commitments.

If you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3871 / Fax: (402) 825-5211 www.nppd.com

NLS2015080 Page 2 of 2 Sincer y, a A. Limpia Vice resident - Nuclear and Chief Nuclear Officer

/dv

Attachment:

Response to Nuclear Regulatory Commission Requests for Additional Information for Relief Requests RP-08, "Comprehensive Pump Test Upper Limit," and RP-09, "Variance Around the Reference Values," for Fifth Ten-Year Interval Pump and Valve Inservice Testing (IST) Program cc: Regional Administrator w/ attachment USNRC - Region IV Cooper Project Manager w/ attachment USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/ attachment USNRC - CNS NPG Distribution w/o attachment CNS Records w/ attachment

NLS2015080 Attachment Page 1 of 3 Attachment Response to Nuclear Regulatory Commission Requests for Additional Information for Relief Requests RP-08, "Comprehensive Pump Test Upper Limit," and RP-09, "Variance Around the Reference Values," for Fifth Ten-Year Interval Pump and Valve Inservice Testing (IST) Program Cooper Nuclear Station, Docket No. 50-298, DPR-46 The Nuclear Regulatory Commission (NRC) requests for additional information (RAI) regarding Relief Requests RP-08, "Comprehensive Pump Test Upper Limit" and RP-09, "Variance Around the Reference Values" are shown in italics. The Nebraska Public Power District (NPPD) response to the requests are shown in normal font.

RAI RP-08-01 Provide a list ofpumps that this alternativerequest applies to. Include the pump name and number, the pump type, the American Society ofMechanical Engineers (ASME) Code class, the ASME Operationand Maintenance (OM) Code category (Group A or B), the design basis accidentflow rate (indicate ifnot applicable),and the 1ST comprehensivepump test or Group A pump testflow rate that will be used to determine ifa pump periodicverification test is required.

NPPD Response Upon further review, Cooper Nuclear Station (CNS) will not pursue relief request RP-08 for all class 1, 2, and 3 IST pumps. The following table provides the list of pumps that RP-08 will be applicable to along with the requested information. The last column of the table also indicates which pumps will have a pump periodic verification (PPV) test based on the current design basis accident flow rate and the current comprehensive pump test flow rate. As is required by the 2012 ASME OM Code, Mandatory Appendix V, Section V-3000(e), the basis for the PPV test parameters will be documented by the owner.

Instrument inaccuracies associated with the PPV test parameters will be accounted for within the safety analyses and/or within the test acceptance criteria. CNS considers this a clarification to Mandatory Appendix V, Section V-3000(f), which states that the owner shall account for the pump periodic verification test instrument accuracies in the test acceptance criteria. Although not expected, any flow rate changes associated with this table would be available for NRC inspection, upon request.

NLS2015080 Attachment Page 2 of 3 RP-08 IST Class 1. 2 and 3 Applicable PumDs Pump Name Pump Pump Type ASME ASME OM Design IST PPV Test Number Code Code Basis Comprehensive Required Class Category Accident Pump Test (Yes/No)

Flow Rate Flow Rate (gallons per (gallons per minute) minute)

Reactor REC-P- Horizontal Equipment A/B/C/D centrifugal 3 Group A 416 1100 No Cooling Pumps pump Residual Heat RHl-P Vertical Removal A/B/C/D centrifugal 2 Group A 7700 7800 No Pumps pump Service Water SW-P- Vertical line Group A 5846 5500 Yes Pumps A/B/C/D shaft pump RAI RP-08-02 Explain what is meant by the statement in Section 5 that says, "Therefore, any IST pump that is utilizing the 1.06 multiplierfor the comprehensivepump test will meet this condition."

NPPD Response This sentence is meant to be a concluding statement for the paragraph. For any pump that utilizes the 1.06 multiplier for the comprehensive pump test, a PPV test, if applicable, will also be required. However, a separate PPV test would not be applicable if the design basis accident flow rate does not exist or is bounded by the comprehensive pump test flow rate or Group A pump test flow rate.

RAI RP-09-01 Provide a list ofpumps that this alternative request applies to. Include the pump name and number, the pump type, the ASME Code class, and the ASME OM Code category (Group A or B).

NPPD Response The following table provides the list of pumps that RP-09 is applicable to along with the requested information.

NLS2015080 Attachment Page 3 of 3 RP-09 IST Class 1, 2, and 3 Applicable Pumps Pump Name Pump Number Pump Type ASME Code ASME OM Code Class Category Core Spray Pumps CS-P-A/B Vertical centrifugal 2 Group B pump High Pressure Coolant HPCI-P-MP Turbine driven Injection Main & HPCI-P-BP horizontal centrifugal 2 Group B Booster Pumps pump Reactor Core Isolation Turbine driven Cooling Main Pump RCIC-P-MP horizontal centrifugal pump 2 Group B Reactor Equipment REC-P-AIB/C/D Horizontal centrifugal 3 Group A Cooling Pumps pump Residual Heat Removal RP-/C/D Vertical centrifugal 2 Group A Pumps pump Service Water Pumps SW-P-AiB/C/D Vertical line shaft 3 Group A pump Residual Heat Removal SW-P- Horizontal centrifugal 3 Group A Service Water Booster BPA/B/C/D pump Pumps

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