ML112980458

Correction Letter Regarding Amendment No. 273 Technical Specification Changes to Reflect Control Rod Drive Control System Upgrade

ML112980458
Person / Time
Site:	Three Mile Island
Issue date:	10/27/2011
From:	Geoffrey Miller Plant Licensing Branch 1
To:	Pacilio M Exelon Nuclear, Exelon Generation Co
Miller G, NRR/DORL/LPL1-2, 415-2481
References
TAC MD9762
Download: ML112980458 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60SSS

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - CORRECTION LETTER REGARDING AMENDMENT NO. 273 RE: TECHNICAL SPECIFICATION CHANGES TO REFLECT CONTROL ROD DRIVE CONTROL SYSTEM UPGRADE (TAC NO. MD9762)

Dear Mr. Pacilio:

On May 27,2010, the Nuclear Regulatory Commission (NRC or Commission) issued Amendment No. 273 1 to Three Mile Island Nuclear Station, Unit 1 (TMI-1), Renewed Facility Operating License No. DPR-SO, in response to your application dated September 29, 2008. 2 Amendment No. 273 consisted of changes to the Technical Specifications (TS) including changes to pages 4-3 and 4-S.

On January 12, 2011, the Commission issued Amendment No. 274 3 to TMI-1, Renewed Facility Operating License No. DPR-SO, in response to your application dated March 24, 2010. 4 Amendment No. 274 also included changes to TS pages 4-3 and 4-S.

Amendment No. 273 was effective as of May 27,2010, and was to be implemented prior to exceeding cold shutdown following the fall 2011 (T1R19) refueling outage. Amendment No. 274 was issued on January 12, 2011, to be implemented within 120 days. Because Amendment No. 274 was planned for implementation prior to Amendment No. 273, TS pages 4-3 and 4-S, issued with Amendment No. 274, did not reflect the changes that were made in Amendment No. 273.

By letter dated March 4, 2011, 5 TS pages 4-3 and 4-S reflecting the changes made by both Amendment Nos. 273 and 274 were provided to you so that the TS will be in the proper configuration upon implementation of Amendment No. 273. Subsequently, it was identified that there was an error on TS page 4-S that was enclosed with the March 4, 2011, letter.

Specifically, the value listed in the "Calibrate" column for item 24, "Control Rod Relative Position," was left blank, where it should have been uNA." I have enclosed a corrected TS page 4-S for your implementation.

1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML092740791 2 ADAMS Accession No. ML082800174 3 ADAMS Accession No. ML103120069 4 ADAMS Accession No. ML100840205 5 ADAMS Accession No. ML110550707

M. Pacilio -2 If you have any questions, please contact me at 301-415-2481.

sincerel~, ~ j Oblltd!(tCLd(

G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

As stated cc w/encl: Distribution via ListServ

TABLE 4.1-1 (Continued)

CHANNEL DESCRIPTION CHECK(c) CALlBRATE(c) REMARKS

19. Reactor Building Emergency 3 Cooling and Isolation CD

~ System Analog Channels 0.

3 CD a. Reactor Building (1) (1 ) (1) When CONTAINMENT INTEGRITY is

-z

~

b.

4 pSig Channels RCS Pressure 1600 psig (1 ) (1 ) NA required.

(1) When RCS Pressure> 1800 psig.

!='

c. Deleted

d. Reactor Bldg. 30 psi (1) (1 ) (1) When CONTAINMENT INTEGRITY is pressure switches required.

e. Reactor Bldg. Purge (1) (1)(2) (1) When CONTAINMENT INTEGRITY is Line High Radiation required.

(AH-V-1 AID)

f. Line Break Isolation (1 ) (1 ) (1) When CONTAINMENT INTEGRITY is Signal (ICCW & NSCCW) required.

20. Reactor Building Spray NA NA System Logic Channel

~

..I 0, 21. Reactor Building Spray NA 30 psig pressure switches

22. Pressurizer Temperature NA Channels N

"'..J

~

23. Control Rod Absolute Position (1 ) NA (1) Check with Relative Position Indication

a. Zone Reference Switch NA R(1) NA (1) Verify switch functions

24. Control Rod Relative Position (1 ) NA NA (1) Check with Absolute Position Indication

25. Core Flooding Tanks

a. Pressure Channels Coolant NA NA

b. Level Channels NA NA

26. Pressurizer Level Channels NA

M. Pacilio - 2 If you have any questions, please contact me at 301-415-2833.

Sincerely, Ira!

G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

As stated cc w/encl: Distribution via ListServ DISTRIBUTION:

PUBLIC RidsAcrsAcnw_MailCTR Resource RidsNrrLAABaxter Resource LPLI-2 RtF RidsNrrPMThreeMilelsland Resource RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpll-2 Resource GHiII,OIS ADAMS Accession Number: ML112980458 OFFICE LPLI-2/PM LPLI-2/PM LPLI-2/LA LPLI-2/BC NAME GEMilier PBamford ABaxter HChernoff (w/comments)

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