ML17055A421
| ML17055A421 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/27/2017 |
| From: | Kimberly Green Plant Licensing Branch III |
| To: | Hamilton D FirstEnergy Nuclear Operating Co |
| Green K, NRR/DORL/LPLIII, 415-1627 | |
| References | |
| CAC MF7476 | |
| Download: ML17055A421 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David B. Hamilton Site Vice President February 27, 2017 FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - CORRECTION TO SAFETY EVALUATION FOR LICENSE AMENDMENT NO. 174 (CAC NO. MF7476)
Dear Mr. Hamilton:
On February 16, 2017, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 17 4 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17033A014). The amendment revised Technical Specifications (TS) 3.6.2.2, "Suppression Pool Water Level, as well as TS surveillance requirements (SRs) 3.6.2.4.1 and 3.6.2.4.4 associated with TS 3.6.2.4, "Suppression Pool Makeup (SPMU) System, and created new Special Operations TS 3.10.9, "Suppression Pool Makeup - MODE 3 Upper Containment Pool Drain-Down, in response to FirstEnergy Nuclear Operating Company's (FENOC) request dated June 30, 2015 (ADAMS Accession No. ML15181A366), as supplemented by letter dated January 18, 2016 (ADAMS Accession No. ML16018A003).
During FENOC's review of the amendment, it identified an error in the NRC staff's safety evaluation on page 19. In the safety evaluation, the following paragraph reads:
The bases for the LCO for suppression pool water level states that the LCO meets Criterion 1 and Criterion 3 of the Final Policy Statement for TSs (now codified in 10 CFR 50.36(c)(2)(ii)). The NRC staff determined LCO 3.10.9 would satisfy these same criteria during drain down evolutions when under the provisions of LCO 3.10.9.
The paragraph erroneously refers to Criterion 1. Instead, the paragraph should refer to Criterion 2.
The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendment, and does not affect the associated notice to the public.
Enclosed, please find corrected safety evaluation page 19.
If you have any questions regarding this matter, I can be reached at (301) 415-1627 or Kimberly.Green@nrc.gov.
Docket No. 50-440
Enclosure:
Corrected Page 19 to the Safety Evaluation cc w/encl: Distribution via ListServ Sincerely, K~JG~
Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ENCLOSURE PERRY NUCLEAR POWER PLANT, UNIT NO. 1 FACILITY OPERATING LICENSE NPF-58 DOCKET NO. 50-440 AMENDMENT NO. 174 CORRECTED PAGE 19 OF THE SAFETY EVALUATION compliance with suspended MODE 3 LCO requirements within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If Condition B is not met, Condition C requires entry into MODE 4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The SRs associated with LCO 3.10.9 include verification of suppression pool temperature, reactor steam dome pressure, levels in the Acceptable range of Figure 3.10.9-1, levels in the steam dryer storage pool and the fuel transfer pool areas of the UCP are sufficiently above the reactor vessel flange, location of the IFTS carriage, and closure of the IFTS transfer tube shutoff valve.
The bases for the LCO for suppression pool water level states that the LCO meets Criterion 2 and Criterion 3 of the Final Policy Statement for TSs (now codified in 10 CFR 50.36(c)(2)(ii)).
The NRC staff determined LCO 3.10.9 would satisfy these same criteria during drain down evolutions when under the provisions of LCO 3.10.9.
Compliance with the requirements in LCO 3.10.9 is optional - i.e., compliance with the normal MODE 3 LCOs is an acceptable alternative. The NRC staff reviewed the proposed requirements and determined that the proposed requirements reflect the major assumptions supporting the engineering analyses discussed in this SE, and are, therefore, appropriate. The SRs associated with LCO 3.10.9 provide verification that the major assumptions of the supporting engineering analyses are continually met while relying on the provisions of this LCO.
For the reasons described above, the staff finds that revised TS continue to satisfy the requirements of 10 CFR 50.36(c)(2) and 50.36(c)(3).
The licensee provided a description of the proposed changes to the TS Bases in its initial application for information only. The licensee stated that the TS Bases are controlled by TS 5.5.11, "TS Bases Control Program."
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 1 O CFR Part 20 or changes the surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (81 FR 28898; dated May 10, 2016). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by
ML17055A421 OFFICE DORL/LPL3/PM DORL/LPL3/LA DORL/LPL3/BC(A)
NAME KGreen SRohrer JWiebe DATE 2/27/17 2/27/17 2/27/17