ML101370761

Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application

ML101370761
Person / Time
Site:	Hope Creek
Issue date:	06/14/2010
From:	Bennett Brady License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
CUNANAN, A
References
TAC ME1832
Download: ML101370761 (7)

Text

June 14, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. NPF-57 for the Hope Creek Generating Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs request for additional information is included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were provided to John Hufnagel and other members of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2981 or by e-mail at bennett.brady@nrc.gov.

Sincerely,

/RA/

Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

As stated cc w/encl: See next page

ML101370761 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady S. Figueroa B. Pham B. Brady DATE 06/14/10 06/07/10 06/09/10 06/14/10

Letter to T. Joyce from B. Brady dated June 14, 2010

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)

DISTRIBUTION:

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Hope Creek Generating Station cc:

Mr. Robert Braun Senior Vice President Nuclear PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Plant Manager - Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Vice President - License Renewal Projects Exelon Nuclear LLC 200 Exelon Way Kennett Square, PA 19348 Mr. Jeffrie J. Keenan, Esquire Manager - Licensing PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Gregory Sosson Director Corporate Engineering PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Michael Gaffney Manager - Hope Creek Regulatory Assurance PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Ali Fakhar Manager, License Renewal PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Township Clerk Lower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy, CN 415 Trenton, NJ 08625-0415 Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Paul Davison Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038

Hope Creek Generating Station cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)

RAI 3.0.3.2.10-01

Background:

The applicant discussed the Fuel Oil Chemistry Program enhanced procedures for Hope Creek as part of the License Renewal Application. During the staff review of the enhanced sampling procedures for the main fuel oil storage tank, the diesel fire pump fuel oil storage tanks, and the diesel fuel oil storage tanks, it was noted that the procedures state that if a significant amount of water (greater than two ounces per gallon of fuel) is present, then a Notification per the Corrective Action Plan should be submitted.

Issue:

It is not clear how the person performing the testing will be able to complete the analysis with the current level of detail provided in the procedure. For example, with the main fuel oil storage tank, it was unclear how the tester would be able to discern two ounces of water in a 10 gallon sample. With the diesel fire pump fuel oil storage tank sample, it was unclear what level of water was rejectable, given that only a one liter sample was specified to be drawn.

Request:

Please clarify how there is reasonable assurance that the analyses requested to be performed in the enhanced procedures will be performed correctly.

RAI 3.1.1-15-01

Background:

The Generic Aging Lessons Learned (GALL) Report Item IV.C1-2 recommends that aging management should be performed according to Chapter XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS).

Issue:

In its review of components associated with AMR line item 3.1.1-15, the staff noted that cast austenitic stainless steel (CASS) is not listed as one of the materials. Additionally, for CASS flow elements, SRP-LR Table 3.1-1, item 57 recommends aging management for loss of fracture toughness due to thermal aging embrittlement. However, license renewal application (LRA) Table 3.4.2-4 includes two 3.1.1-15 line items under Table 1 items (flow elements, Class

1) with CASS as the material, and credits the LRA Boiler Water Reactor Water Chemistry and the One-Time Inspection Aging Management Programs (AMPs).

Request:

The staff requests that the applicant explain the following:

a) Why aging management review (AMR) line item 3.1.1-57 is not applicable when the GALL Report only exempts pump and valve bodies, and b) Why the flow elements associated with AMR line item 3.1.1-15 do not credit GALL AMP XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) to manage loss of fracture toughness/thermal aging embrittlement.

RAI 3.3.2.10-1

Background:

LRA Table 3.3.2-10, page 3.3-191, states that gray cast iron (retarding chamber) tanks exposed to raw water environment has an aging effect of loss of material due to general, pitting, crevice, galvanic, and microbiologically influenced corrosion, and fouling, and that the aging effects will be managed by the Fire Water System Program. The AMR line items reference Table 1 line item 3.3.1-68 and GALL Report item VII.G-24, for piping, piping components, and piping elements, and also cite generic note C, indicating that the component is different, but consistent with NUREG-1801 item for material, environment, and aging effect.

Issue:

The staff reviewed GALL AMP XI.M27, Fire Water System, and noted that the AMP recommends wall thickness evaluations of fire protection piping be performed using non-intrusive technique (e.g., volumetric testing) to identify loss of material due to corrosion. Based on a telephone conversation with the applicant on May 25, 2010, the applicant clarified that the retarding chamber is a vertical pipe installed in a horizontal piping system and acts like a tank.

The staff infers that this vertical pipe is a low point in the system and will have stagnant water and will be susceptible to loss of material due to general, pitting and crevice corrosion. It is not clear from a review of LRA Section B.2.1.18, Fire Water System Program, whether volumetric inspection to detect loss of material due to corrosion will be performed on the internal surface (specifically the bottom) of the fire water and the retarding chamber tanks.

Request:

Clarify if the (retarding chamber) tanks are included in the sample of fire protection system components that will be volumetrically inspected for wall thickness evaluation to detect loss of material prior to loss of intended function. If not included, please justify how loss of material due to general, pitting, crevice, galvanic, and microbiologically influenced corrosion, and fouling will be detected from the bottom surface of these tanks.