ML092570367

Correction to Technical Specifications

ML092570367
Person / Time
Site:	Prairie Island
Issue date:	09/15/2009
From:	Thomas Wengert Plant Licensing Branch III
To:	Schimmel M Northern States Power Co
Wengert, Thomas J, NRR/DORL, 415-4037
References
TAC MD9142, TAC MD9143
Download: ML092570367 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 15, 2009 Mr. Mark A. Schimmel Site Vice President - Acting Prairie Island Nuclear Generating Plant Northern States Power - Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUB..IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CORRECTION TO TECHNICAL SPECIFICATIONS (TAC NOS. MD9142 AND MD9143)

Dear Mr. Schimmel:

On July 1, 2009 (Agencywide Documents Access and Management System Accession No. ML091460809), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 192 to Facility Operating License No. DPR-42 and Amendment No. 181 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP),

respectively. The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated June 26,2008, as supplemented by letters dated August 4, August 26, and November 14, 2008, and January 30, February 9, February 20, March 12, and May 4 (2 letters) 2009.

The amendments revised the PINGP TSs to allow the use of Westinghouse 422 VANTAGE+

nuclear fuel and made changes to certain references identified in the Design Features section of the TSs.

TS page 2.0-1, issued with the amendments, contained two editorial errors. In TS section 2.1.1.1, the phrase "... for OFA fuel" was inadvertently retained in the issued TS page. The marked-up TS page submitted with the June 26, 2008, application, correctly showed the change to remove these words from the sentence. Also, in TS Section 2.1.1.2 (b), the abbreviation for weight percent (w/o) was erroneously notated in subscript font.

TS page 2.0-1 has been revised to correct the editorial errors that were inadvertently introduced when the NRC processed Amendment Nos. 192 and 181. Please replace the corresponding page from the TS with the corrected page 2.0-1 enclosed with this letter.

M. Schimmel

-2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue.

Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR and the following SLs shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained> 1.17 for WRB-1 DNB correlation.

2.1.1.2 The peak fuel centerline temperature shall be maintained as follows:

a) <5080 of, decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing U02; b) <<5080 OF minus 6.75 OF per wlo Gdz0 3), decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing gadolinia; 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained

s 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

Prairie Island Unit 1 - Amendment No. ~ ~ 192 Units land 2 2.0-1 Unit 2 - Amendment No. -l-49 BJ. 181 Revised hy letter dated Septe~her 15, 200Q

M. Schimmel

-2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue.

Sincerely, IRA by M. Chawla fori Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC LPL3-1 rlf RidsNrrPMPrairielsland Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource RidsRgn3MailCenter Resource RidsOgcRp Resource RidsNrrDirsltsb Resource ADAMS Accession No ML092570367 OFFICE NRRlLPL3-11 PM NRRlLPL3-11 LA NRRlLPL3-1/(A)BC NAME TWengert BTuily TWengert (M. Chawla for)

(T. Harris for)

DATE 09/15/09 09/15/09 09/15/09 OFFICIAL RECORD COpy