NL-15-1114, Response to Request for Additional Information for Alternative Requests RR-P-11 and RR-P-13

Response to Request for Additional Information for Alternative Requests RR-P-11 and RR-P-13

ML15197A187
Person / Time
Site:	Hatch
Issue date:	07/16/2015
From:	Pierce C Southern Co, Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-1114
Download: ML15197A187 (7)

Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway A

Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN COMPANY JUL 1 6 2015 Docket Nos.: 50-321 NL-15-1114 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Response to Request for Additional Information for Alternative Requests RR-P-11 and RR-P-13 Ladies and Gentlemen:

By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML15124A904), Southern Nuclear Operating Company (SNC), submitted alternative requests RR-P-11 and RR-P-13 for the fifth ten-year inservice testing (1ST) program for Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch). The submitted alternative requests propose to perform alternate pump tests in lieu of the requirements specified in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), in the 2004 Edition through the 2006 Addenda.

Based on subsequent discussions with the Nuclear Regulatory Commission (NRC) staff, additional information is needed for the staff to complete its review.

That information is provided in Enclosures 1 and 2 of this letter.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Ree.ctl~:p; C. R. Pierce Regulatory Affairs Director CRP/RMJ

Enclosures:

1. SNC Response to Request for Additional Information

2. Requested Information per RAI RR-P-13-1

U. S. Nuclear Regulatory Commission NL-15-1114 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch

Edwin I. Hatch Nuclear Plant Response to Request for Additional Informatio n for Alternative Requests RR-P-11 and RR-P-13 Enclosure 1 SNC Response to Request for Additional Informatio n

Enclosure 1 to NL-15-1114 SNC Response to Request for Additional Information RAI RR-P-11-1 Provide the names of the pumps and the type of pump for the equipment numbers listed in the "Components Affected" section.

SNC Response to RAI RR-P-11-1 The updated "Components Affected" section for RR-P-11 is provided below:

1E11-C002A-D (Residual Heat Removal - Centrifugal Pumps) -Group A 1E21-C001 A&B (Core Spray- Centrifugal Pumps)- Group B 2E11-C002A-D (Residual Heat Removal -Vertical Line Shaft Pumps)- Group A 2E21-C001 A&B (Core Spray- Vertical Line Shaft Pumps) -Group B RAI RR-P-11-2 Under "Requirements," Table ISTB-3520(b) is listed. There is no Table ISTB-3520(b) in the ASME OM Code. Please provide the correct reference.

SNC Response to RAI RR-P-11-2 The word Table" was inserted in this text in error. The correct requirements should state "ISTB-3520(b)."

RAI RR-P-13-1 In the "Components Affected" section, only equipment numbers are given.

Provide the pump name, ASME OM Code Group, and type of pump for each equipment number.

SNC Response to RAI RR-P-13-1 The table in Enclosure 2 provides the requested information for RR-P-13.

RAI RR-P-13-2 In the "Components Affected" section there are equipment numbers with the heading "Augmented Components." Describe why these components are labeled as augmented components, and why they are identified in this alternative request.

SNC Response to RAI RR-P-13-2 The augmented scope components listed are the Units 1 and 2 Reactor Core Isolation Cooling (RCIC) pumps and the Units 1 and 2 Diesel Fuel Oil Transfer pumps. These pumps are not considered to have individual safety functions as described in ISTA-11 OO(a) and therefore not required to be in the 1ST scope. Hatch does however consider these pumps important and has included them in augmented 1ST scope in order to provide for quality, periodic testing to E1-1 to NL-15-1114 SNC Response to Request for Additional Information help ensure they remain Operable. Their inclusion in this relief request is an additional conservative action establishing that the commitments made by Hatch in this proposed alternative request will be applied to these pumps as well.

E1-2

Edwin I. Hatch Nuclear Plant Response to Request for Additional Information for Alternative Requests RR-P-11 and RR-P-13 Enclosure 2 Requested Information per RAI RR-P-13-1

Enclosure 2 to NL-15-1114 Requested Information per RAI-RR-P-13-1 Relief Request RR-P-13 Components Affected Pump Number Description Pump Type Code OM Code Class Cateoorv 1(2) C41-C001A & B STANDBY LIQUID CONTROL PUMPS Pas. Displacement 3 Group B 1(2) E11-C001 A-D RHR SERVICE WATER PUMPS Vertical Line Shaft 3 Group A 1E11-C002A-D RESIDUAL HEAT REMOVAL PUMPS Centrifugal 3 Group A 2E11-C002A-D RESIDUAL HEAT REMOVAL PUMPS Vertical Line Shaft 3 Group A 1E21-C001A & B CORE SPRAY PUMPS Centrifugal 3 Group B 2E21-C001A & B CORE SPRAY PUMPS Vertical Line Shaft 3 Group B 1(2) E41-C001 HIGH PRESSURE COOLANT INJECTION PUMPS Centrifugal 2 Group B 1(2) E51-C001 REACTOR CORE ISOLATION COOLING PUMPS <1> Centrifugal 3 Group B 1(2) P41-C001 A-D PLANT SERVICE WATER PUMPS Vertical Line Shaft 2 Group A 1Y52-C001 A-C 1Y52-C101A & B 1 2Y52-C001A & C DIESEL FUEL OIL TRANSFER PUMPS < > Vertical Line Shaft 2 Group B 2Y52-C101A & C 2P41-C002 STANDBY DIESEL SERVICE WATER PUMP Vertical Line Shaft 2 Group B Note (1)- These are augmented components but the relief commitments will also apply to these pumps.