L-17-052, Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3

Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3

ML17038A114
Person / Time
Site:	Perry
Issue date:	02/06/2017
From:	Hamilton D FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CAC MF7476, L-17-052
Download: ML17038A114 (6)

Text

FENOC Perry Nuclear Power Plant PO Box 97 10 Center Road FirstEnergy Nuclear Operating Company PenY< Ohl° 44081 David B. Hamilton 440-280-5382 Vice President February 6, 2017 L-17-052 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (UCP) Gate Installation in MODEs 1. 2. and 3. and Drain-Down of the Reactor Cavity Portion of the UCP in MODE 3 (CAC No. MF7476)

By letter dated March 15, 2016 (Accession No. ML16075A411), FirstEnergy Nuclear Operating Company (FENOC) submitted to the Nuclear Regulatory Commission (NRC) a license amendment application for the Perry Nuclear Power Plant (PNPP).

The proposed amendment would modify Technical Specification (TS) 3.6.2.2, "Suppression Pool Water Level," and TS 3.6.2.4, "Suppression Pool Makeup (SPMU)

System," to allow installation of the reactor well to steam dryer storage pool gate in MODEs 1, 2, and 3. The proposed amendment would also create a new Special Operations TS, TS 3.10.9, "Suppression Pool Makeup - MODE 3 Upper Containment Pool Drain-Down," to allow draining of the reactor well portion of the upper containment pool in MODE 3.

Upon further review, FENOC has identified the need for an update to the TS Table of Contents page iv to reflect new Special Operations TS, 3.10.9. The proposed mark up for that page is provided in Attachment 1, and the retyped page is provided in Attachment 2. FENOC requests that the updated table of contents page be included in the aforementioned license amendment application.

Perry Nuclear Power Plant L-17-052 Page 2 of 2 There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 315-6810.

I declare under penalty of perjury that the foregoing is true and correct. Executed on February 6 , 2017.

Sincerely, 7

David B. Hamilton Attachments:

1 Proposed Technical Specification Table of Contents Change (Mark-Up) 2 Proposed Technical Specification Table of Contents Change (Retyped) cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

Attachment 1 L-17-052 Proposed Technical Specification Table of Contents Change (Mark-Up)

(1 page follows)

TABLE OF CONTENTS 3.9 REFUELING OPERATIONS {continued) 3.9.5 Control Rod OPERABIUTY-Refueling 3.9-7 3.9.6 Reactor Pressore Vessel (RPV) Water Level-Irradiated Fuel 3.9-8 3.9.7 Reactor Pressure Vessel (RPV) Water Level - New Fuel or Control Rods 3.9-9 3.9.8 Residual Heat Removal (RHR)- High Water Level 3.9-10 3.9.9 Residual Heat Removal (RHR)- Low Water Level 3.9-13 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing 3.10-4 3.10.3 Single Control Rod Withdrawal-Hot Shutdown 3.10-6 3J0.4 Single Gontrol Rod Withdrawal- Cold Shutdown 3.10-9 3.10.5 Single Control Rod Drive (CRDJ Removal-Refueling 3.10-13 3.10.6 Multiple Control Rod Withdrawal-Refueling 110-16 3J0.7 Control Rod Testing-Operating 3.10-18 3J0.8 SHUTDOWN MARGIN (SDM) Test-Refueling 3.10-19 3.10.9 Suppression Pool Makeup - MODE 3 Upper Containment Pop!

3.10^-23 4.0 DESIGN FEATURES 4.1 Site Location 4.0-1 4.2 Reactor Core 4.0-1 4.3 Fuel Storage 4.0-2 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility. 5.0-1 5.2 Organization 5.0-2 5.3 Unit Staff Qualifications 5.0-4 5.4 Procedures 5.0-5 5.5 Programs and Manuals 5.0-6 5.6 Reporting Requirements 5.0-16 5.7 High Radiation Area 5.0-19 PERRY - UNIT 1 iv Amendment No.

Attachment 2 L-17-052 Proposed Technical Specification Table of Contents Change (Retyped)

For Information Only (1 page follows)

Information Only TABLE OF CONTENTS 3.9 REFUELING OPERATIONS (continued) 3.9.5 Control Rod ORERABIL1TY-Refueling 3.9-7 3.9.6 Reactor Pressure Vessel (RPV) Water Level - Irradiated Fuel 3.9-8 3.9.7 Reactor Pressure Vessel (RPV) Water Level - New Fuel or Control Rods 3 9-9 3.9.8 Residual Heat Removal (RHR)-High Water Level 3.9-10 3.9.9 Residua! Heat Removal (RHR)-Low Water Level 3.9-13 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing 3 10-4 3.10.3 Single Control Rod Withdrawal -Hot Shutdown 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown 3 10-9 3J0.5 Sngle Control Rod Drive {CRD} Removal -Refueling 3.10-13 3.10.6 Multiple Control Rod Withdrawal- Refueling. 3.10-16 3.10.7 Control Rod Testing -Operating 3 10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test -Refueling 3.10-19 3.10.9 Suppression Pool Makeup - MODE 3 Upper dontainment Pool Drain-Down 3.10-23 4.0 DESIGN FEATURES 4.1 Site Location 4.0-1 A2 Reactor Core 4.0-1 4.3 Fuel Storage 4.0-2 5.0 ADMINISTRATIVE CONTTRCLS 5.1 Responsibility 5.0-1 5.2 Organization 5.0-2 5.3 Unit Staff Qualifications 5.04 5.4 Procedures 5.0-5 5.5 Programs and Manuals 5.0-6 5.6 Reporting Requirements 5.0-16 5.7 High Radiation Area 5.0-19 PERRY - UNIT 1 iv Amendment No.