ML18060A416

Attachment - Vogtle Electric Generating Plant Unit 4 LAR 17-034

ML18060A416
Person / Time
Site:	Vogtle
Issue date:	03/28/2018
From:	Jordan Hoellman NRC/NRO/DNRL/LB4
To:	Whitley B Southern Nuclear Operating Co
hoellman j/415-5481
Shared Package
ML18060A411	List: ML18060A412 ML18060A413 ML18060A414 ML18060A415 ML18060A416 ML18060A417
References
EPID L-2017-LLA-0102, LAR 17-034
Download: ML18060A416 (5)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 116 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-92 REMOVE INSERT 7 7 Appendix A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.0-2 3.0-2

--- 3.1.10-1 3.4.8-1 3.4.8-1

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b) SNC shall report any violation of a requirement in Section 2.D.(3),

Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 116, are hereby incorporated into this license.

(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).

(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:

(a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program

1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 116

Technical Specifications LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the test required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, additional evaluations and limitations may be required in accordance with Specification 5.5.7, Safety Function Determination Program (SFDP). If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support systems Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCOs 3.1.8 and 3.1.10 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

VEGP Units 3 and 4 3.0 - 2 Amendment No. 117 (Unit 3)

Amendment No. 116 (Unit 4)

Technical Specifications Rod Withdrawal Test Exception

- MODE 5 3.1.10 3.1 REACTIVITY CONTROL SYSTEMS 3.1.10 Rod Withdrawal Test Exception - MODE 5 LCO 3.1.10 During the performance of rod movement and rod drop time testing, the requirements of LCO 3.4.4, RCS Loops, may be suspended provided boron concentration of the reactor coolant system is greater than the all rods out (ARO) boron concentration that provides keff < 0.99.

APPLICABILITY: MODE 5 with LCO 3.4.4 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Initiate action to fully insert Immediately LCO not met. all rods.

AND A.2 Place the Plant Control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> System in a condition incapable of rod withdrawal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.10.1 Verify boron concentration of the reactor coolant 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> system is greater than the ARO boron concentration providing keff < 0.99.

VEGP Units 3 and 4 3.1.10 - 1 Amendment No. 117 (Unit 3)

Amendment No. 116 (Unit 4)

Technical Specifications Minimum RCS Flow 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Minimum RCS Flow LCO 3.4.8 At least one Reactor Coolant Pump (RCP) shall be in operation with a total flow through the core of 3,000 gpm.

- NOTES -

1. a. All RCPs may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period for the purpose of testing; or

b. With no RCPs in operation, an unborated water source through the chemical mixing tank may be unisolated under administrative controls for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for the purpose of chemical addition to the pressurizer; provided:

i. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and ii. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. No RCP shall be started when the RCS temperature is 350°F unless pressurizer level is < 92%.

3. No RCP shall be started with any RCS cold leg temperature 350°F unless the secondary side water temperature of each steam generator (SG) is 50°F above each of the RCS cold leg temperatures and the RCP is started at 25% of RCP speed.

APPLICABILITY: MODES 3, 4, and 5 with unborated water sources not isolated from the RCS.

VEGP Units 3 and 4 3.4.8 - 1 Amendment No. 117 (Unit 3)

Amendment No. 116 (Unit 4)