ML15065A084
| ML15065A084 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/04/2015 |
| From: | Andrea George Plant Licensing Branch IV |
| To: | David Bice Entergy Nuclear Operations |
| References | |
| TAC MF5292 | |
| Download: ML15065A084 (4) | |
Text
1 NRR-PMDAPEm Resource From:
George, Andrea Sent:
Wednesday, March 04, 2015 3:28 PM To:
BICE, DAVID B (ANO); CLARK, ROBERT W Cc:
PYLE, STEPHENIE L
Subject:
Request for Additional Information (2nd Round) - Arkansas Nuclear One, Unit 1 - LAR to Revise Pressure-Temperature Limits to 54 EFPY - TAC No. MF5292 Attachments:
MF5292 - RAIs-2.pdf Mr. Clark and Mr. Bice, By letter dated November 21, 2014 (Agencywide Documents Access and Management System (ADAMS)
Accession Number ML14330A249), Entergy Operations, Inc. (Entergy, the licensee), submitted a license amendment request (LAR) to revise the Technical Specifications (TS) for the Reactor Coolant System Pressure and Temperature Limits (TS 3.4.3), Pressurizer (TS 3.4.9), Pressurizer Safety Valves (TS 3.4.10),
and Low Temperature Overpressure Protection System (TS 3.4.11) at Arkansas Nuclear One, Unit 1 (ANO-1).
The proposed revision would extend the applicability of the current limits from 31 effective full power years (EFPY) to 54 EFPY. The U.S. Nuclear Regulatory Commission (NRC) staff requested additional information via email dated January 21, 2015 (ADAMS Accession No. ML15021A428). By letter dated February 6, 2015 (ADAMS Accession No. ML15041A073), the licensee responded to the staffs request for additional Information (RAI).
Based on the continued review of the license amendment request (LAR), the NRC staff has determined that additional information is required to complete its review. The formal requests for additional information (RAIs) are attached to this email. A clarification call was held on Wednesday, March 4, 2015, and during that call, it was decided that Entergy would respond to these RAIs by Friday, March 13, 2015, or sooner, given the requested expedited review schedule for the LAR. If you encounter any issues with this schedule, please call or email.
Sincerely, Andrea George Project Manager Nuclear Regulatory Commission Division of Operating Reactor Licensing andrea.george@nrc.gov 301-415-1081
Hearing Identifier:
NRR_PMDA Email Number:
1921 Mail Envelope Properties (Andrea.George@nrc.gov20150304152700)
Subject:
Request for Additional Information (2nd Round) - Arkansas Nuclear One, Unit 1 -
LAR to Revise Pressure-Temperature Limits to 54 EFPY - TAC No. MF5292 Sent Date:
3/4/2015 3:27:30 PM Received Date:
3/4/2015 3:27:00 PM From:
George, Andrea Created By:
Andrea.George@nrc.gov Recipients:
"PYLE, STEPHENIE L" <SPYLE@entergy.com>
Tracking Status: None "BICE, DAVID B (ANO)" <DBICE@entergy.com>
Tracking Status: None "CLARK, ROBERT W" <RCLARK@entergy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1749 3/4/2015 3:27:00 PM MF5292 - RAIs-2.pdf 123358 Options Priority:
Standard Return Notification:
No Reply Requested:
Yes Sensitivity:
Normal Expiration Date:
Recipients Received:
Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE AND LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM LIMITS TO 54 EFFECTIVE FULL POWER YEARS ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET NO. 50-313 By letter dated November 21, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14330A249), Entergy Operations, Inc. (Entergy, the licensee), submitted a license amendment request (LAR) to revise the Technical Specifications (TS) for the Reactor Coolant System Pressure and Temperature Limits (TS 3.4.3), Pressurizer (TS 3.4.9), Pressurizer Safety Valves (TS 3.4.10), and Low Temperature Overpressure Protection System (TS 3.4.11) at Arkansas Nuclear One, Unit 1 (ANO-1). The proposed revision would extend the applicability of the current limits from 31 effective full power years (EFPY) to 54 EFPY.
The AREVA report ANP-3300, Rev.1, "Arkansas Nuclear One (ANO) Unit 1 Pressure-Temperature Limits at 54 EFPY," provided as Attachment 4 to the LAR (ADAMS Accession No. ML14330A250), contains the technical basis for the proposed revised pressure-temperature (P-T) limits for ANO-1.
The U.S. Nuclear Regulatory Commission (NRC) staff requested additional information via email dated January 21, 2015 (ADAMS Accession No. ML15021A428). By letter dated February 6, 2015 (ADAMS Accession No. ML15041A073), the licensee responded to the staffs request for additional Information (RAI). After reviewing the licensees LAR as supplemented, the NRC staff has determined that additional information is required, as stated below.
EVIB-RAI-5 For the analysis of the reactor pressure vessel beltline region P-T limits, provide tabulations of the metal temperatures at the one quarter of wall thickness (1/4t) and three-quarters of wall thickness (3/4t) locations, the thermal stress intensity factor (KIt) at the 1/4t and 3/4t locations and coolant temperature, all as a function of the transient time for the following transients:
a) Three heatup transients, as defined in Section 4.6.1 of ANP-3300, Rev. 1, of 50 deg/hr, 70 deg/hr, and 90 deg/hr.
b) Two cooldown transients with last reactor coolant pump trip at 255 deg F, as defined in ANP-3300, Rev. 1, Section 4.6.2, for both ramp and step transients.
EVIB-RAI-6 For the analysis of the outlet nozzle P-T limits, provide tabulations of the metal temperature at the 1/4T location, the thermal stress intensity factor (KIt), and coolant temperature, all as a function of the transient time, for the same transients listed in EVIB-RAI-5.
EVIB-RAI-7 For the analysis of the outlet nozzle, provide the values of Ri, t, a, ri, rc, rn, and the resulting value of F(a/rn) as described in ANP-3300, Rev. 1, Section 5.4.
EVIB-RAI-8 Describe how was it demonstrated that the outlet nozzles bound the inlet nozzles and core flood nozzles as described in ANP-3300, Rev.1, Section 4.2.b.
EVIB-RAI-9 a) Confirm that the limiting location pressure correction factors for ANO-1 provided in Table 6-1 of ANP-3300, Rev. 1, are applied by subtracting them from the calculated allowable pressures, and that this correction was applied to the data listed in Tables 7-1, 7-2, 7-3, and 7-4.
b) Confirm that the beltline is the limiting location at all temperatures and pressures for all the transients evaluated and that the limiting location pressure correction factor for the beltline (for the applicable temperature range) was subtracted for all calculated allowable pressures.