ML16309A081

From kanterella
Jump to navigation Jump to search

Regulatory Audit Summary Related Amendment Request Regarding Installation of the Upper Containment Pool Gate in Modes 1, 2, or 3 and the Drain-Down of the Upper Containment Pool During Mode 3 (CAC No. MF7476)(L-16-083)
ML16309A081
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 11/09/2016
From: Kimberly Green
Plant Licensing Branch III
To: Hamilton D
FirstEnergy Nuclear Operating Co
Green K
References
CAC MF7476, L-16-083
Download: ML16309A081 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 9, 2016 Mr. David B. Hamilton Site Vice President 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 - REGULATORY AUDIT

SUMMARY

RELATED TO AMENDMENT REQUEST REGARDING INSTALLATION OF THE UPPER CONTAINMENT POOL GATE IN MODES 1, 2, OR 3 AND THE DRAIN-DOWN OF THE UPPER CONTAINMENT POOL DURING MODE 3 (CAC NO. MF7476) (L-16-083)

Dear Mr. Hamilton:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 15, 2016, FirstEnergy Nuclear Operating Company (FENOC) submitted a license amendment request that proposed changes to the technical specifications to permit the installation of the upper containment pool gate in MODES 1, 2, or 3, and the drain-down of the reactor well portion of the upper containment pool during MODE 3, for the Perry Nuclear Power Plant, Unit No. 1.

To enhance the NRC review of the request, the staff conducted an audit of supporting documents during the week of September 6, 2016. The staff reviewed the documents and held discussions with members of FENOC and its contractor, Zachry Group. The regulatory audit summary is enclosed.

While the NRC review team did not identify any significant issues during its audit or during the discussions with FENOC and its contractor, the team indicated that the review was ongoing and that any additional information necessary to support the review would be formally requested.

D. Hamilton If you have any questions, please contact me at (301) 415-1627.

Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

Regulatory Audit Summary cc w/encl: Distribution via ListServ

REGULATORY AUDIT

SUMMARY

RELATED TO LICENSE AMENDMENT REQUEST REGARDING UPPER CONTAINMENT POOL GATE INSTALLATION IN MODES 1, 2, AND 3, AND DRAIN-DOWN OF REACTOR CAVITY PORTION OF THE UPPER CONTAINMENT POOL IN MODE 3 FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 Date of Audit: September 6 - 9, 2016 Audit Location: NRC Headquarters The audit was conducted remotely at the U.S. Nuclear Regulatory Commission's (NRC)

Headquarters in Rockville, Maryland, via access through an electronic portal. Access to the licensee's documents via the electronic portal was controlled in accordance with the following conditions:

  • The online reference portal is password-protected and passwords are assigned to those directly involved in the review on a need-to-know basis;
  • The online reference portal is sufficiently secure to prevent staff from printing, saving, or downloading any documents; and
  • Conditions of use of the online reference portal are displayed on the login screen and require concurrence by each user.

NRC Audit Team Members:

Kim Green, Project Manager Fred Forsaty, Technical Reviewer FENOC and Contractor

Participants:

Ted Hilston, FirstEnergy Nuclear Operating Company (FENOC)

Al Widmer, FENOC Al Rabenold, FENOC Phil Lashley, FENOC Dave Pribyl, Zachry Group Glenn (Skip) Denny, Zachry Group Enclosure

Documents Audited:

Calculation 2.2.1.10, Revision 0, "Containment Response for LOCA [loss-of-coolant accident]

When Draining Upper Containment Pool in MODE 3," January 14, 2016 Letter from Michael D. Lyster, Centerior Energy, to NRC Document Control Desk, "Technical Specification Change, Request: Containment Response Analysis Improvements Necessary Due to Increased Ambient Air and Lake Temperatures," PY-CEl/NRR-151 O L, dated June 24, 1992 Calculation B21-C10, Revision 2, "Reactor Vessel High Level 8 RCIC/HPCS Trip," May 12, 1999 Instruction Number EOP-01, Revision 6, "RPV [reactor pressure vessel] Control," Effective Date:

October 22, 2015 Instruction Number EOP-01A, Revision 8, "Level Power Control," Effective Date: October 26, 2015 Perry Nuclear Power Plant, Unit 1, Updated Safety Analysis Report, Revision 19, October 2015 Summary of Audit Activities:

The NRC staff conducted a regulatory audit of the licensee's documents to increase the efficiency of the license amendment request (LAR) review. The staff also conducted discussions with the licensee and its contractor regarding the following topics during this audit:

  • Discussions related to general design criteria (GDCs) 16, 38, and 50.
  • Discussions related to the design bases for current requirements.
  • Discussions on the safety analysis of the proposed change.

o Post-accident vent coverage o Hydrodynamic loads o Emergency core cooling system net positive suction head requirements o Long term heat sink

  • Discussions related to input assumptions used in the GOTHIC code calculations for this LAR.
  • Comparison of the analysis of record (method and results) and the analysis used in this LAR.
  • The band on operator action for Level 8.
  • Original assumptions for sizing of the upper containment pool, specifically, break size and location.

Request for Additional Information:

The audit of the documents resulted in a request for additional informational that was transmitted to FENOC separately from this report.

ML16309A081 *via email/memo dated OFFICE NRR/DORL/LPL3-1 /PM NRR/DORL/LPL3-1 /LA NRR/DSS/SRXB/BC* N RR/DORL/LPL3-1 /BC NRR/DORL/LPL3-1 /PM NAME KGreen SRohrer EOesterle DWrona KGreen DATE 11/7/16 11/7/16 11/8/16 11/8/16 11/9/16