LR-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.

Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.

ML102520076
Person / Time
Site:	Hope Creek
Issue date:	08/19/2010
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N10-0310
Download: ML102520076 (5)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC AUG 1 9 2010 10 CFR 50.90 LR-N10-0310 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Supplement to License Amendment Request H09-06 to Adopt TSTF-460, REVISION 0, "CONTROL ROD SCRAM TIMES"

References:

(1) Letter from PSEG to NRC, "License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated December 1, 2009 (2) Letter from PSEG to NRC, "Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated July 23, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The request would revise Technical Specification; (TS) testing frequency for the surveillance requirement (SR) in existing TS 3.1.3.2, "Control Rod Maximum Scram Insertion Times." These changes are based on TS Task Force (TSTF) change'traveler TSTF-460 (Revision 0) that has been approved generically for the boiling water reactor (BWR)

Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6) by revising the frequency of STS SR 3.1.4.2, control rod scram time testing, from "at least once per 120 days of POWER OPERATION" to "at least once per 200 days of POWER OPERATION." A notice announcing the availability of this proposed TS change using the Consolidated Line Item Improvement Process was published in the Federal Register on August 23, 2004 (69 FR 51854).

In Reference 2, PSEG corrected a typographical error in Section 6.0 "Commitments" of Attachment 1, page 12 of 14. Specifically, the section did not correctly reference the specific commitments made by PSEG in Attachment 4 of the submittal.

At the NRC's request PSEG is submitting an additional supplement to this license amendment request, which will modify the technical specification mark ups submitted to the NRC in Reference

1. The revised pages are editorial in nature and do not modify the intent of the license amendment request. To ensure there is consistency within the section and reduce confusion, the proposed change will insert the word "Deleted" to page v of the Index and page 3/4 1-8. The revised mark ups are Attachment 1 to this letter. A-0 95-2168 REV. 7/99

Document Control Desk 2 LR-N10-0310 PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in References 1 and 2. The additional information provided in this letter does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration.

There are no regulatory commitments contained in this submittal.

If you have any questions or require additional information, please do not hesitate to contact Mrs. Erin West at (856) 339-5411.

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

Executed on  ? / //10 (Date)

Sincerely, John F. Perry Site Vice President - Hope Creek Attachment Marc L, Dapas, Acting Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector- Hope Creek P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Hope Creek PSEG Commitment Coordinator - Corporate

Document Control Desk LR-N10-0310 ATTACHMENT 1 TECHNICAL SPECIFICATION PAGES: REVISED:

LICENSE AMENDMENT TO ADOPT TSTF 460, REV 0.

The following Technical Specifications for HCGS (Facility Operating License NPF-57) are the revised pages affected by this change request:

TS No. Title Page INDEX CONTROL RODS v 3.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES 3/41-8 4.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES- 3/4 1-8 SURVEILLANCE REQUIREMENTS

S LIMITING CONDITIONS FOR OPERATION INDEX AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY .......... . ....................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN..! ...................................... 3/4 1-1 3/4.1.2- REACTIVITY ANOMALIES ................................... .1-2 1-2+/-(

3/4.1.3 CONTROL RODS.

Control Rod Operability ................................... 3/4 1-3 Control Rod Maximum Scram Insertion Times ..... ......... 3/4 1-6 Control Rod-A~-vý Scram insertion Times ................. 3/4 1-7 Four Control Rod iGroup Scram Insertion Times ............ 3/4 1-8 Control Rod Scram Accumulators ............................ 3/4 1-9 Control Rod Drive Coupling ................................ 3/4 1-11 Control Rod Position Indication ........................... 3/4 1-13 Control Rod Drive Housing Support....................... 3/4 1-15 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer ...................................... 3/4 1-16 Rod Sequence Control System (Deleted) .................. 3/4 1-17 Rod Block Monitor ........... ............................ 3/4 1-18 3/4.1,5 STANDBY LIQUID CONTROL SYSTEM ........................... 3/4 1-19 Figure 3.1.5-1 Sodium Pentaborate Solution Volume/Concentration Requirements ..... 3/4 1-21 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ............. 3/4 2-1 S HOPE CREEK v Amendment No. 105

REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD GROUP' SCP)M INSERTION TIMES L

LIMITING CONDITION FOR OPERATION

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