ML18302A257

Correction to Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems and Components (CAC Nos. MG0181 and MGO182; EPID L-2017-LLA-0281)

ML18302A257
Person / Time
Site:	Peach Bottom
Issue date:	11/01/2018
From:	Jennifer Tobin Plant Licensing Branch 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Tobin J, NRR/DORL/LPL1
References
CAC MG0181, CAC MGO182, EPID L-2017-LLA-0281
Download: ML18302A257 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C. 20555-0001 November 1, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3-CORRECTION TO AMENDMENT NOS. 321 AND 324 TO ADOPT 10 CFR 50.69, "RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS" (CAC NOS. MG0181 AND MG0182; EPID L-2017-LLA-0281)

Dear Mr. Hanson:

On October 25, 2018 (Agencywide Documents Access and Management System Accession No. ML18263A232), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos.

321 and 324 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (Peach Bottom), Units 2 and 3, respectively. These amendments were issued in response to your application dated August 30, 2017, as supplemented by letters dated October 24, 2017; May 7, 2018; June 6, 2018; August 10, 2018; and August 22, 2018.

These amendments added a new license condition to the Renewed Facility Operating Licenses to allow the implementation of risk-informed categorization and treatment of structures, systems, and components for nuclear power reactors in accordance with Title 10 of the Code of Federal Regulations Section 50.69.

Shortly after these amendments were issued, it was noted that there was an inadvertent typographical error on license page 7g for Unit 3. Rather than the language in paragraph ( 17) on license page 7g for Unit 3 referring to License No. DPR-56 for Peach Bottom Unit 3, it referred to License No. DPR-44 for Peach Bottom Unit 2. The corrected page 7g is enclosed with a change bar showing the line of text that has been corrected.

Please replace page 7g of Renewed Facility Operating License No. DPR-56 for Unit 3 with the enclosed page. The NRC staff regrets any inconvenience this may have caused.

B. Hanson If you have any questions, please contact me at 301-415-2328 or Jennifer.Tobin@nrc.gov.

Sincerely,

~) ~

Jenni!~, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosure:

Corrected page 7g for Renewed DPR-56 cc: Listserv

Enclosure Corrected page 7g for Renewed DPR-56

(e) The results of the power ascension testing to verify the continued structural integrity of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall include a final load definition and stress report of the steam dryer, including the results of a complete re-analysis using the end-to-end B/Us from Peach Bottom Unit 2 benchmarking at EPU conditions. The report shall be submitted within 90 days of the completion of EPU power ascension testing for Peach Bottom Unit 3.

(f) During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be conducted of the steam dryer as described in the inspection guidelines contained in WCAP-17635-P.

(g) The results of the visual inspections of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.

(h) Within 6 months following completion of the second refueling outage, after the implementation of the EPU, the licensee shall submit a long-term steam dryer inspection plan based on industry operating experience along with the baseline inspection results.

The license condition described above shall expire: (1) upon satisfaction of the requirements in paragraphs (f) and (g), provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw(s) or unacceptable flaw growth that is due to fatigue, and; (2) upon satisfaction of the requirements specified in paragraph (h).

( 16) Maximum Extended Load Line Limit Analysis Plus (MELLLA+) Special Consideration The licensee shall not operate the facility within the MELLLA+ operating domain with a feedwater heater out of service resulting in more than a 10°F reduction in feedwater temperature below the design feedwater temperature.

(17) Adoption of 10 CFR 50.69, "Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants" In support of implementing License Amendment No. 321 permitting the adoption of the provisions of 10 CFR 50.69 for Renewed Facility Operating License No. DPR-56 for Peach Bottom Unit 3, the license is amended to add the following license condition:

Renewed License No. DPR-56 Amendment No. 324 Page 7g

ML18302A257 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DORL/LPL 1/BC DORL/LPL 1/PM NAME JTobin PTalukdar/LRonewicz JDanna JTobin DATE 10/30/2018 10/28/2018 10/31/2018 11/01/2018