ML19169A031

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Withdrawal of Various Licensing Actions Involving Three Mile Island Nuclear Station, Unit 1
ML19169A031
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/17/2019
From: Jim Barstow
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TMl-19-061
Download: ML19169A031 (3)


Text

Exelon Generation fl)

Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 10 CFR 50.55(a)

TMl-19-061 June 17, 2019 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:

Withdrawal of Various Licensing Actions Involving Three Mile Island Nuclear Station, Unit 1

References:

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

Nuclear Regulatory Commission, "License Amendment Request (LAR) for One-Cycle Extension of Appendix J Type A Integrated Leakage Rate Test," dated December 14, 2018

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

Nuclear Regulatory Commission, "License Amendment Request -

Administrative Changes to Tendon Surveillance Program Technical Specifications," dated September 20, 2018

3. Letters from James Barstow (Exelon Generation Company, LLC) to U.S.

Nuclear Regulatory Commission, "Proposed Alternative to Utilize Code Cases N-878 and N-880," and "Proposed Alternative to Utilize Code Case N-879", both dated May 30, 2018

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

Nuclear Regulatory Commission withdrawing Code Case N-879, dated July 26, 2018

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

Nuclear Regulatory Commission, "Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds," dated February 15, 2019

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

Nuclear Regulatory Commission, "Proposed Alternative to Utilize Code Case N-879," dated April 30, 2019 The purpose of this letter is to withdraw several Licensing Actions currently under NRC review for Three Mile Island Nuclear Station - Unit 1 (TMl-1 ).

Withdrawal of Various Licensing Actions Involving TMl-1 June 17, 2019 Page 2 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Renewed Facility Operating License No. DPR-50 for TMl-1 to allow for a one-cycle extension to the 10-year frequency of the TMl-1 containment leakage rate test (i.e.,

Integrated Leakage Rate Test (ILRT) or Type A test). This test is required by Technical Specification (TS) 6.8.5, "Reactor Building Leakage Rate Testing Program." The proposed change would permit the existing ILRT to be extended from 10 years to 11. 75 years.

In Reference 2, EGC requested an amendment to Renewed Facility Operating License No.

DPR-50 for TMl-1 to revise Technical Specification (TS) 4.4.2.1 ("lnservice Tendon Surveillance Requirements"). The surveillance requirements and inspection frequencies for the tendons are mandated by 10 CFR 50.55a. Currently, the TS does not allow exceptions to the requirements of 10 CFR 50.55a. This administrative change would add the words "except where an alternative, exemption, or relief has been authorized by the NRC" to allow NRG-approved exceptions to the 10 CFR 50.55a requirements.

In the Reference 3 letters, EGC requested proposed alternatives to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," on the basis that compliance with the code results in hardship without a compensating increase in quality. Specifically, these proposed alternatives requested the use of: 1) Code Case N-879, "Use of Micro-Alloyed Carbon Steel Bar in Patented Mechanical Joints and Fittings, Classes 1, 2, and 3 Section Ill, Division 1," which would allow the use of a material that does not comply with the limitations on material specifications and grades mandated by ASME Section Ill, and; 2) Code Case N-878 ("Alternative to QA Program Requirements of IWA-4142 Section XI, Division 1") and N-880 ("Alternative to Procurement Requirements of IWA-4143 for Small Nonstandard Welded FittingsSection XI, Division 1"), which address the procurement of material from a material supplier that does not possess ASME accreditation as a Quality System Certificate Holder or an NPT Certificate Holder.

Subsequently, in Reference 4, EGC withdrew the request to utilize Code Case N-879.

In Reference 5, EGC requested a proposed alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," on the basis that the proposed alternative provides an acceptable level of quality and safety. Specifically, the request related to the use of encoded phased array ultrasonic examination techniques in lieu of radiography for ferritic and austenitic piping welds.

In Reference 6, EGC requested a proposed alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," on the basis that the proposed alternative provides an acceptable level of quality and safety, equivalent to compliance with ASME Section Ill and XI requirements. Specifically, the proposed alternative concerned the use of Code Case N-879, "Use of Micro-Alloyed Carbon Steel Bar in Patented Mechanical Joints and Fittings, Classes 1, 2, and 3 Section Ill, Division 1." This Code Case permits use of a material that does not comply with the limitations on material specifications and grades mandated by ASME Section Ill, NB/NC/ND-2121(a).

Withdrawal of Various Licensing Actions Involving TMl-1 June 17, 2019 Page 3 On May 8, 2019, EGC announced that TMl-1 will permanently shut down by September 30, 2019, as previously announced in May 2017. As a result of this decision, the requested license amendments described above and the requested relief requests described above are no longer necessary since these proposed changes were only needed to support operation beyond the current operating cycle, which will not occur. Therefore, EGC hereby withdraws the proposed TMl-1 license amendment requests (References 1 and 2), and the proposed TMl-1 relief requests (References 3, 5, and 6). These withdrawals apply only to TMl-1. All other TMl-1 Licensing Actions currently under review by NRC are unaffected by this withdrawal letter.

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

paragraph (b}, EGC is notifying the State of Pennsylvania of these withdrawals by transmitting a copy of this letter to the designated State Official.

There are no regulatory commitments contained in this letter.

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

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 17th day of June 2019.

Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC cc: USNRC Regional Administrator, Region I USNRC Project Manager, TMl-1 USNRC Senior Resident Inspector TMl-1 Director, Bureau of Radiation Protection - PA Department of Environmental Resources