NG-05-0010, Request for Segmented Review of License Amendment Request (Tscr - 056)
| ML050190242 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 01/07/2005 |
| From: | Peifer M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-05-0010 | |
| Download: ML050190242 (4) | |
Text
Ni Committed to Nuclear Excellence Duane Arnold Energy Center Operated by Nuclear Management Company, LLC January 7, 2005 NG-05-0010 10 CFR 50.90 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center
-____D Docket.50-331i-License No. DPR-49
Subject:
Request for Segmented Review of License Amendment Request (TSCR - 056)
Reference:
Letter, M. Peifer (NMC) to USNRC, License Amendment Request (TSCR - 056):
'Elimination of License Condition 2.C.(2)(b) for Performance of Large Transient Tests for Extended Power Uprate'," NG-O4-01 11, dated February 27, 2004..
In the referenced letter, NMC requested an amendment to the Operating License for the Duane Arnold Energy Center (DAEC). The requested change was to remove a license condition to perform two, specific large transient tests (LTT), at specified reactor thermal power levels, as part of power ascension testing for the Extended Power Uprate (EPU) project at the DAEC. In that letter, NMC requested approval of this change prior to March 1, 2005, as modifications are planned for the upcoming refuel outage at the DAEC which will allow the
__reactor power level-to reach the license condition for performing the first of the two LTTs, the full Main Steamline Isolation Valve (MSlV)-closUrtEtest. However, these planned modifications-will not allow the reactor to achieve the thermal power level required to invoke the second of the two LTTs required by the license condition, namely the Main Generator Load Reject (MGLR) test.
Given the staggered nature of the plant modifications in the DAEC EPU project, NMC requests that the Staff issue separate license amendments, one'for each of the two LTTs, and to focus its current review of the referenced application on the 'MSIV'closure test provision of the DAEC Operating License. The purpose for this segregation is an earlier review and approval of this portion of the application to support our upcoming refueling outage, as requested in the original submittal. Accordingly, enclosed is a revised markup of th6 DAEC Operating License specific to the elimination of the MSIV closure test only.'The evaluation of 3277 DAEC Road
- Palo, Iowa 52324-9785 Telephone: 319.851.7611
Document Control Desk Page 2 Significant Hazards Considerations pursuant to §50.92 and evaluation of Environmental Considerations of this action pursuant to §51.22, submitted with the original application, included this specific change and therefore, need not be revised.
NMC will continue to work with the Staff to support review of the remainder of the original application dealing with the MGLR test, subsequent to the upcoming refuel outage.
This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 7, 2005.
ar A. Peifer Site Vice President, Duane Arnold Energy Center Nuclear Management Company, LLC Enclosure cc:
Administrator, Region ll, USNRC Project Manager, Duane Arnold Energy Center, USNRC Resident Inspector, Duane Arnold Energy Center, USNRC D. McGhee, State of Iowa
ENCLOSURE Revised Mark-up DAEC Operating License Page # 4 (a)
For Surveillance Requirements (SRs) whose acceptance criteria are modified, either directly or indirectly, by the increase in authorized maximum power level in 2.C.(1) above, in accordance with Amendment No. 243 to Facility Operating License DPR-49, those SRs are not required to be performed until their next scheduled performance, which is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment No. 243.
(b)
The licensee will perform the generator load reject and full main steomline isolation velve elosure transienktestrequired by the General Electric Licensing Topical Report for Extended Power Uprate (NEDC-32424P-A) -
ELTR-1, including the allowances described in Section L.2.4 (2) of ELTR-1 regarding credit for unplanned plant transient events, using the thermal power level (1658 MWt) to establishELTR-1 power level limiWs The the testingasl be Ce formed at an initiating power level greater than the
_ __ y-steatdyta operation poWer level _exceedlnj-We frs ELTR-1 power level limit for transient
\\the generator load rejectl (3) Fire Protection NMC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the Duane Arnold Energy Center and as approved in the SER dated June 1, 1978, and Supplement dated February 10, 1981, subject to the following provision:
NMC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(4) The licensee is authorized to operate the Duane Arnold Energy Center following installation of modified safe-ends on the eight primary recirculation system inlet lines which are described in the licensee letter dated July 31, 1978, and supplemented by letter dated December 8, 1978.
(5) Physical Protection NMC shall fully-implement and maintain -in effect all provisions of-the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Duane Arnold Energy Center Security Plan," with revisions submitted through December 17, 1987; "Duane Arnold Energy Center Guard Training and Qualification Plan," with revisions submitted through October 18, 1985; and "Duane Arnold Energy Center Safeguards Contingency Plan," with revisions submitted through December 5, 1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
Amendment No. 43, 47, 50, 63, 65, 74, 112, 152, 190, 198, 214, 223, 232, 243