LR-N04-0365, Response to Request for Additional Information Regarding Request for Change to Technical Specifications to Support Removal of the Reactor Vessel Head Spray Piping

Response to Request for Additional Information Regarding Request for Change to Technical Specifications to Support Removal of the Reactor Vessel Head Spray Piping

ML042450535
Person / Time
Site:	Hope Creek
Issue date:	08/23/2004
From:	John Carlin Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LCR H02-002, LR-N04-0365
Download: ML042450535 (5)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 AUG 2 3 2004 § PSEG NuclearLLC LR-N04-0365 LCR H02-002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS TO SUPPORT REMOVAL OF THE REACTOR VESSEL HEAD SPRAY PIPING HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354

Reference:

Letter LR-N04-0310, Response To Request For Additional Information Regarding Request For Change To Technical Specifications To Support Removal Of The Reactor Vessel Head Spray Piping, dated July 15, 2004.

On July 15, 2004, PSEG Nuclear LLC (PSEG) submitted a response to the referenced request for additional information in support removal of the Reactor Head Spray System.

Mr. D. Collins, Hope Creek Project Manager called on July 16, 2004 to request clarification of our response on General Design Criteria (GDC) 14. Subsequently, he also requested clarification with respect to our response to GDC 53. This information was provided verbally. PSEG is docketing the information as Attachment 1 to this letter.

Ifyou have any questions or require additional information, please contact Mr. Michael Mosier at (856) 339-5434.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on '721?) i, BWL{

Vi esident - Nuclear Assessments Attachment 95-2168 REV. 7/99

Document Control Desk 2 LR-N04-0365 AUG 2 3 2004 C: Regional Administrator L NRC Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager - Hope Creek U.S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555-0001 USNRC Senior Resident Inspector- Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 I

Attachment I Response to NRC Request For Additional Information

Document Control Desk LR-N04-0365 Attachment I Question I il Inyour response to General Design Criteria 14, Reactor Pressure Coolant Pressure Boundary, PSEG indicated that a Reactor Pressure Vessel (RPV) hydrostatic test would be used to test the blind flange installed on nozzle N6A. Provide clarification as to whether this is an ASME over pressure hydrostatic test or a leakage test.

PSEG Response The test to be performed is a leakage test. HC.OP-IS.ZZ-0001, "Inservice System Leakage Test of the Reactor Coolant Pressure Boundary", is performed at normal operating temperature and pressure.

Question 2 In your response to General Design Criteria, Provisions for containment testing and inspection, you did not provide the design criteria for the six-inch pipe cap. Please provide the design pressure for the six-inch pipe cap.

PSEG Response The six-inch pipe cap is a Schedule 40, Class GBB, ASME IlIl B&PV,Section III, Class 2, 300 psig, 850 degrees F. The pipe cap weld is ASME ll, Class MC for pressure retaining components. The design pressure for containment is 62 psig and the design accident value is 48.1 psig. The original pipe was designed to ASME Class 1, Schedule 80.

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