BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control

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Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
ML18023A432
Person / Time
Site: Brunswick  
(DPR-062, DPR-071)
Issue date: 01/23/2018
From: William Gideon
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 18-0013
Download: ML18023A432 (7)
v • d • e


Text

William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.832.3698 January 23, 2018 Serial: BSEP 18-0013 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control

Reference:

Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, dated June 29, 2017, ADAMS Accession Number ML17180A538 Ladies and Gentlemen:

By letter dated June 29, 2017 (i.e., Reference), Duke Energy Progress, LLC (Duke Energy),

submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP),

Unit Nos. 1 and 2. The proposed amendment requested to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2. The purpose of this submittal is to provide updated Technical Specifications (TS) pages which resolve an issue identified in TSTF-542, Revision 2. This supplement also revises the implementation schedule for the amendment.

The following describes the issue that was recently identified in TSTF-542, Revision 2.

Prior to TSTF-542, NUREG-1433 TS 3.3.5.1 Table 3.3.5.1-1 Function 1.c (Core Spray Reactor Steam Dome Pressure - Low) and Function 2.c (LPCI Reactor Steam Dome Pressure - Low (Injection Permissive)) both had Note (a) for Modes 4 and 5 in the "Applicable Modes or Other Specified Conditions" column. Note (a) said, "When associated ECCS subsystem(s) are required to be Operable per LCO 3.5.2, "ECCS -

Shutdown." In TSTF 542, Functions 1.c and 2.c were transferred to Table 3.3.5.2-1 as Functions 1.a and 2.a. However, Note (a) was not transferred with the functions (although the last paragraph of the applicable Bases indicates that it had been). Without the Note, Functions 1.a and 2.a are required to be Operable for all low pressure ECCS subsystems regardless of whether the subsystem is credited to meet TS 3.5.2.

The same issue was introduced in the BSEP TSTF-542 LAR (i.e., Reference). To resolve the issue, the following note is added to Functions 1.a and 2.a of the proposed Table 3.3.5.3-1, RPV Water Inventory Control Instrumentation, for BSEP Units 1 and 2.

U.S. Nuclear Regulatory Commission Page 2 of 3 (a)

Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control."

The existing Table 3.3.5.3-1 Note (a), contained in the BSEP TSTF-542 LAA, is re-designated as Note (b). These changes are consistent with the resolution recommended by the Boiling Water Reactor Owners' Group. Enclosures 1 and 2 provide revised typed TS pages for BSEP

. Units 1 and 2.

Duke Energy has reviewed the No Significant Hazards Consideration Determination, published in the Federal Register on September 12, 2017 (i.e., 82 FR 175, page 42846), and has concluded that the determination is not impacted by this supplement. Likewise, this supplement does not impact the Environmental Evaluation provided in the BSEP TSTF-542 LAA.

In order to allow sufficient time for implementation of the proposed amendments, once approved, Duke Energy requests that the NRC authorize implementation of the TSTF-542 amendments prior to the 2019 Unit 2 refueling outage, currently scheduled to begin in March 2019. This implementation period supersedes the originally requested 180-day implementation period.

This document contains no new regulatory commitments.

I declare, under penalty of perjury, that the foregoing is true and correct. Executed on January 23, 2018.

Sincerely, UJJW William R. Gideon MAT/mat

Enclosures:

1.

Revised (Typed) Technical Specification Page - Unit 1

2.

Revised (Typed) Technical Specification Page - Unit 2

U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with Enclosures):

U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only)

P.O. Box 29510 Raleigh, NC 27626-0510 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)

Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov

BSEP 18-0013 Revised (Typed) Technical Specification Page Unit 1

RPV Water Inventory Control Instrumentation 3.3.5.3 Brunswick Unit 1 3.3-48c Amendment No. 203 Table 3.3.5.3-1 (page 1 of 1)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Core Spray System
a. Reactor Steam Dome PressureLow 4, 5 4(a)

C SR 3.3.5.3.1 SR 3.3.5.3.2 425 psig

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Steam Dome PressureLow 4, 5 4(a)

C SR 3.3.5.3.1 SR 3.3.5.3.2 425 psig

3. RHR System Isolation
a. Reactor Vessel Water LevelLow Level 1 (b) 2 in one trip system B

SR 3.3.5.3.1 SR 3.3.5.3.2 153 inches

4. Reactor Water Cleanup (RWCU)

System Isolation

a. Reactor Vessel Water LevelLow Level 2 (b) 2 in one trip system B

SR 3.3.5.3.1 SR 3.3.5.3.2 101 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control."

(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

BSEP 18-0013 Revised (Typed) Technical Specification Page Unit 2

RPV Water Inventory Control Instrumentation 3.3.5.3 Brunswick Unit 2 3.3-48c Amendment No. 203 Table 3.3.5.3-1 (page 1 of 1)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Core Spray System
a. Reactor Steam Dome PressureLow 4, 5 4(a)

C SR 3.3.5.3.1 SR 3.3.5.3.2 425 psig

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Steam Dome PressureLow 4, 5 4(a)

C SR 3.3.5.3.1 SR 3.3.5.3.2 425 psig

3. RHR System Isolation
a. Reactor Vessel Water LevelLow Level 1 (b) 2 in one trip system B

SR 3.3.5.3.1 SR 3.3.5.3.2 153 inches

4. Reactor Water Cleanup (RWCU)

System Isolation

a. Reactor Vessel Water LevelLow Level 2 (b) 2 in one trip system B

SR 3.3.5.3.1 SR 3.3.5.3.2 101 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control."

(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

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