TMI-15-072, Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts

Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts

ML15161A333
Person / Time
Site:	Three Mile Island
Issue date:	06/10/2015
From:	David Helker Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-15-072
Download: ML15161A333 (6)

Text

200 Exelon Way Kennett Square, PA 19348 Exelon Generation www.exeloncorp.com 10 CFR 50.90 TMl-15-072 June 10, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits

References:

1. Letter from James Barstow (Exelon Generation Company, LLC) to U.S.

NRC, "License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits," dated October 30, 2014 Pursuant to 10 CFR 50.90, Exelon Generation Company, LLC (Exelon) is submitting a supplement to the October 30, 2014, (Reference 1) request for an amendment to the Technical Specifications (TS) for Three Mile Island Nuclear Station (TMI}, Unit 1.

In the Reference 1 submittal, two items believed to be typographical errors were proposed for correction. It was subsequently determined that the errors exist in the Exelon Electronic Document Management System (EDMS) but do not exist on the controlled copies of the TMI Technical Specifications. Therefore, the proposed correction of typographical errors in TS 3.1.6.1 O.a (LIPS) and TS Table 3.1.6.1 (CF-V~A) is being withdrawn. The errors in the EDMS file have been entered into Exelon's Corrective Action Program for correction. provides a new mark-up of TS Page 3-15b. Attachment 2 is the final clean TS Page 3-15b for this license amendment request. With the exception of the typographical error, no other changes affected TS Section 3.1.6.1 O.a. Therefore, TS Page 3-13 has been removed from this submittal. No other revisions have been made to the proposed changes in the October 30, 2014, submittal.

U.S. Nuclear Regulatory Commission Supplement to LAR - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits June 10, 2015 Page 2 Exelon has determined that the information provided in this supplemental letter does not impact the conclusions of the No Significant Hazards Consideration or Environmental Consideration as stated in Reference 1.

There are no regulatory commitments contained in this submittal.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), Exelon is notifying the Commonwealth of Pennsylvania of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official.

Should you have any questions concerning this letter, please contact Frank Mascitelli at (610) 765-5512.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 10th day of June 2015.

Respectfully, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC

Attachment:

1. Proposed Technical Specification Marked-Up Page, Revised

2. Proposed Technical Specification - Clean Page cc: USNRC Region I, Regional Administrator USNRC Project Manager, TMI, Unit 1 USNRC Senior Resident Inspector, TMI, Unit 1 Director, Bureau of Radiation Protection, PA Department of Environmental Resources Chairman, Board of County Commissioners, Dauphin County, PA Chairman, Board of Supervisors, Londonderry Township, PA R.R. Janati, Commonwealth of Pennsylvania

Attachment 1 Three Mile Island Nuclear Station, Unit 1 Supplement to License Amendment Request Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits Proposed Technical Specification Marked-Up Page, Revised

CONTROLLED COPY TABLE 3.1.6.1 PRESSURE ISOLATION CHECK VALVES BETWEEN THE PRIMARY tooLXNT stsTEM I LPls System Valve No.

Low Pressure Injection INSERT Train A CF-YSA DH-Y22A Train B CF-YSB DH-Y228 Leakage rates less than or equal to 1.0 gpm are consfdered acceptable.

2. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are consfdered acceptable ff the latest measured rate has not exceeded the rate detel'll1ned by the prevfous test by an amount that reduces the margf n between measured leakage rate and the maximum perwisstble rate of 5.0 gpm by SOI or greater.

3. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are consfdered unacceptable 1f the latest ...sured rate exceeded the rate detennined by the previous test by an amount that reduces the margin between ..asured leakage rate and the *axfmum pe,.f ssf ble rate of 5.0 gpm by SOS or greater.

4. Leakage rates greater than 5.0 gpm are considered unacceptable.

9PdeP 9e-ted 4/29/81 Amendment No. -141 3-15b

Attachment 2 Three Mile Island Nuclear Station, Unit 1 Supplement to License Amendment Request Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits Proposed Technical Specification - Clean Page

TABLE 3.1.6.1 PRESSURE ISOLATION CHECK VALVES BETWEEN THE PRIMARY COOLANT SYSTEM & LPIS Maximum System Valve No.

Allowable Leakage Low Pressure Injection Train A CF-VSA ss.O GPM DH-V22A S5.0 GPM Train B CF-VSB S5.0 GPM DH-V22B ss.O GPM 3-15b Order Dated 4/20181 Amendment No . .+4+,