ML23005A170
| ML23005A170 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/17/2023 |
| From: | Geoffrey Miller NRC/NRR/DORL/LPL2-1 |
| To: | Stoddard D Dominion Energy Nuclear Connecticut |
| References | |
| EPID L-2021-LLA-0186 | |
| Download: ML23005A170 (1) | |
Text
January 17, 2023 Mr. Daniel G. Stoddard Seniour Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION UNIT NO. 3 CORRECTION TO ISSUANCE OF AMENDMENT NO. 283 TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-569, REVISION OF RESPONSE TIME TESTING DEFINITION (EPID L-2021-LLA-0186)
Dear Mr. Stoddard:
On March 1, 2022 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML22041A010), the U.S. Nuclear Regulatory Commission issued Amendment No. 283 to Renewed Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3.1 These amendments were in response to your application dated October 7, 2021 (ML21280A328). The amendment revised the Technical Specifications (TSs) to adopt Technical Specification Task Force (TSTF) Traveler TSTF-569, Revise Response Time Testing Definition, to revise the TS definitions for the engineered safety feature response time and reactor trip system response time.
During the review of your current application for TSTF-554, the NRC recognized that it did not issue all TS pages included in your request for TSTF-569.
The NRC staff has determined that the error was made inadvertently during issuance of the amendment and is only applicable to the amendment for Millstone Power Station, Unit No. 3. The error does not change any of the conclusions associated with the issuance of Amendment No. 283 to Renewed Facility Operating License Nos. NPF-49 the Millstone Power Station, Unit No. 3 and does not affect the no significant hazards consideration published in the Federal Register on November 30, 2021 (86 FR 67987). Accordingly, to this letter provides the corrected amendment attachment and Enclosure 2 provides the correct TS pages.
1 The request was submitted as a fleet request and was also issued as Amendment Nos. 291 and 274 to Renewed Facility Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station (North Anna), Unit Nos. 1 and 2, respectively, and Amendment No. 221 to Renewed Facility Operating License No. for the Virgil C. Summer Nuclear Station, Unit No. 1. This letter does not affect those issuances.
D. Stoddard If you have any questions, please contact me at 301-415-4032, or via e-mail at Ed.Miller@nrc.gov.
Sincerely,
/RA/
G. Edward Miller, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-423
Enclosure:
- 1. As stated cc: Listserv
ATTACHMENT TO MILLSTONE POWER STATION, UNIT NO. 3 LICENSE AMENDMENT NO. 283 RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert NPF-49, page 4 NPF-49, page 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 1-3 1-3 1-4 1-4 1-5 1-5 1-6 1-6 1-7 1-7
ENCLOSURE 2 Corrected, Issued, Technical Specification Pages
MILLSTONE - UNIT 3 DEFINITIONS DOSE EQUIVALENT XE-133 1.11 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microCurie/gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, External Exposure to Radionuclides in Air, Water, and Soil.
1.12 DELETED ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e.,
the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC, or the components have been evaluated in accordance with an NRC approved methodology.
1.14 DELETED FREQUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
LEAKAGE 1.16 LEAKAGE shall be:
1.16.1 CONTROLLED LEAKAGE CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals, and 1.16.2 IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE shall be:
a.
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or Amendment No. 84, 87, 126, 187, 216, 220, 238, 246, 283 1-3
MILLSTONE - UNIT 3 DEFINITIONS
- b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.
Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);
1.16.3 PRESSURE BOUNDARY LEAKAGE PRESSURE BOUNDARY LEAKAGE shall be LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in a RCS component body, pipe wall, or vessel wall, and 1.16.4 UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all LEAKAGE which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include continuity check of each associated slave relay.
MEMBER(S) OF THE PUBLIC 1.18 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
The term REAL MEMBER OF THE PUBLIC means an individual who is exposed to existing dose pathways at one particular location.
OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
Amendment No. 238, 283 1-4
MILLSTONE - UNIT 3 DEFINITIONS OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
1.22 DELETED PURGE - PURGING 1.23 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
QUADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.
RATED THERMAL POWER 1.27 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3709 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC, or the components have been evaluated in accordance with an NRC approved methodology.
Amendment No. 60, 187, 188, 238, 242, 280, 283 1-5
MILLSTONE - UNIT 3 DEFINITIONS REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
SHUTDOWN MARGIN 1.30 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY 1.31 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SLAVE RELAY TEST 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.
SOURCE CHECK 1.33 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.
STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
THERMAL POWER 1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TRIP ACTUATING DEVICE OPERATIONAL TEST 1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.
Amendment No. 238, 283 1-6
MILLSTONE - UNIT 3 DEFINITIONS 1.37 DELETED UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTING 1.39 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
1.40 Deleted 1.41 Deleted CORE OPERATING LIMITS REPORT (COLR) 1.42 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.6. Unit Operation within these operating limits is addressed in individual specifications.
1.43 Deleted 1.44 Deleted Amendment No. 39, 50, 60, 72, 100, 189, 268, 273, 283 1-7
ML23005A170 OFFICE NRR/DORL/
LPL2-1/PM NRR/DORL/
LPL2-1/LA NRR/DORL/
LPL1/BC NRR/DORL/
LPL2-1/PM NAME GEMiller KGoldstein HGonzalez GEMiller DATE 1/10/2023 01/05/2023 1/12/2023 1/17/2023