ML032370148

Response to NRC Request for Additional Information on Reactor Pressure Vessel Material Surveillance Program

ML032370148
Person / Time
Site:	Hope Creek
Issue date:	08/14/2003
From:	Garchow D Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LCR H02-013, LRN-03-0344
Download: ML032370148 (5)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 AUG 14 2003 LRN-03-0344 LCR H02-013 O PSEG Nuclear LLC U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION ON REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354

Reference:

Letter LR-N02-0319, Request For Change To Reactor Materal Surveillance Program, dated December 23, 2002 On December 23, 2002, PSEG Nuclear LLC (PSEG) submitted the referenced request for a change to Hope Creek Updated Final Safety Analysis Report (HCUFSAR), Section 5.3, Reactor Vessel", and Appendix 5A, Compliance with I OCFR50, Appendix G and H."

In a letter dated July 16, 2003, PSEG received a request from the NRC for additional information regarding reactor pressure vessel material surveillance program at Hope Creek Generating Station. Attachment I contains PSEG's responses.

If you 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.

Sincerely, Executed on 1)( I'll3 L.

I Vi. Garciow Vice Presidbnt - Projects & Licensing 405 Attachment

-A (C)g 95-2168 REV. 7/99

LRN-03-0344 2

AUG 1 4 2003 Document Control Desk C:

Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia,YA 19406 Mr. Richard Ennis, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box415 Trenton, New Jersey 08625

LRN-03-0344 Document Control Desk Attachment HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM NRC Question 1: of your application dated December 23, 2002, stated that in a letter dated March 29, 2002 (ADAMS Accession No. ML021010214), PSEG committed to update fluence calculations in accordance with Regulatory Guide (RG) 1.190 by May 1, 2005.

The commitment in the letter dated March 29, 2002, reads as follows:

Based on approval of this request, new pressure-temperature limit curves will be submitted as part of the Hope Creek extended power uprate utilizing the methodology of Regulatory Guide 1.190. Submittal of the technical specification changes are targeted for May 2003 with implementation of the extended power uprate in the Fall 2004 outage.

In addition, PSEG's letter dated May 29, 2003 (ADAMS Accession No. MI-031620164) stated that the extended power uprate submittal is scheduled for September 2003.

Please clarify the date of the commitment to update the fluence calculations in accordance with RG 1.190.

Response

The current pressure-temperature limits, Technical Specification 3 /4.4.6, issued with Amendment 139 for Hope Creek are valid through Cycle 12. Cycle 12 ends in Fall 2004, requiring new pressure-temperature limits. It was originally planned that power uprate would also be implemented at the same time. However, due to changes in the review cycle, power uprate may not occur until after the Fall 2004 refueling outage.

Therefore, based on this revised implementation schedule, the pressure-temperature limits update based on Regulatory Guide (RG) 1.190 will be decoupled from the power uprate submittal. The pressure-temperature limits based on RG 1.190 will be submitted by December 31, 2003. The new limits, while based on RG 1.190, will also include the effects of increased power level associated with power uprate.

NRC Question 2:

The NRC staffs letter dated February 1, 2002 (ADAMS Accession No. ML020380691),

and the associated Safety Evaluation, provided the staffs approval of the BWRVIP ISP and specified the conditions for BWR licensees' participation in the ISP. The staff concluded that the BWRVIP ISP is acceptable for BWR licensee implementation provided that the licensee use one or more compatible neutron fluence methodologies, acceptable to the NRC staff to determine surveillance capsule and RPV neutron 1

LRN-03-0344 Document Control Desk Attachment I fluences. The NRC's letter dated February 1, 2002, also stated that licensees who elect to participate in the program will need to submit a license amendment request to incorporate the ISP into the facility licensing basis. Attachment 2 of your application dated December 23, 2002, provided the proposed changes to the Hope Creek UFSAR that would be incorporated as a result of the amendment request. However, the proposed changes do not show the methodology that will be used. The UFSAR markup should be revised to reflect that the methodology used to perform the fluence calculations will be consistent with RG 1.190.

Response

The markup of Section 5.3.1.6.2 of the Hope Creek Generating Station UFSAR has been revised to include reference to RG 1.190 for future fluence calculations. Revised page 5.3-11 is attached.

2

Replace with A/~Ise 1

i t wihdrawal schedule of the three sets of specimens in the rea or is planned as follows:

1. Th irst set at the 300 azimuth was withdrawn during the

~5th re ling outage.

2. The secon set will be withdrawn when its exposure corresponds to ifteen effective full power years or at the time when t accumulated neutron fluence of the capsule corresponds t the approximate EOL fluence at the reactor vessel inner 1 location, whichever comes first. This withdrawal will scheduled for the nearest vessel refueling date based on t above criteria.

3. The third set will be held to th EQL (not less than once, nor more than twice the peak EOL ssel fluence at the vessel inside surface). This capsule ay be held without testing following withdrawal.

A discussion of the extent of compliance to 10CFR50, Appendix H provided in Appendix 5A.

5.3.1.6.2 Neutron Flux and Fluence Calculations A

description of the methods of analysis is contained in Sections 4.1.4.5 and 4.3.2.8. Future neutron fluence calculations will be performed in accordance with Regulatory Guide 1.190.

5.3.1.6.3 Predicted Irradiation Effects on Vessel Beltline Materials Estimated maximum changes to initial RTNDT and upper shelf 5.3-11 HCGS-UFSAR Revision 8 September 25, 1996