ML15093A006: Difference between revisions

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| number = ML15093A006
| number = ML15093A006
| issue date = 04/02/2015
| issue date = 04/02/2015
| title = 2015/04/02 NRR E-mail Capture - Requests for Additional Information - 4th Round - ANO-1 P/T and Ltop Limits Update to 54 EFPY License Amendment Request - MF5292
| title = Requests for Additional Information - 4th Round - ANO-1 P/T and Ltop Limits Update to 54 EFPY License Amendment Request - MF5292
| author name = George A
| author name = George A
| author affiliation = NRC/NRR/DORL/LPLIV-1
| author affiliation = NRC/NRR/DORL/LPLIV-1

Revision as of 10:56, 7 February 2019

Requests for Additional Information - 4th Round - ANO-1 P/T and Ltop Limits Update to 54 EFPY License Amendment Request - MF5292
ML15093A006
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/02/2015
From: Andrea George
Plant Licensing Branch IV
To: David Bice
Entergy Nuclear Operations
References
TAC MF5292
Download: ML15093A006 (3)


Text

1 NRR-PMDAPEm Resource From: George, Andrea Sent: Thursday, April 02, 2015 3:35 PM To: BICE, DAVID B (ANO)

Cc: CLARK, ROBERT W; PYLE, STEPHENIE L

Subject:

Requests for Additional Information - 4th R ound - ANO-1 P/T and LTOP Limits Update to 54 EFPY License Amendment Request - MF5292 Mr. Clark and Mr. Bice, By application dated November 21, 2014, as supplemented by letters dated February 6, March 10, and March, 2015 (Agencywide Documents Access and Management System (ADAMS Accession Nos. ML14330A246, ML15041A065, ML15071A054, and ML15086A019, respectively), Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for Arkansas Nuclear One, Unit No. 1 (ANO-1).

The proposed changes revise TS 3.4.3, "Reactor Coolant System (RCS) Pressure and Temperature (P/T) Limits, TS 3.4.9, "Pressurizer," TS 3.4.10, "Pressurizer Safety Valves," and TS 3.4.11, "Low Temperature Overpressure Protection." to update the reactor coolant system (RCS) pressure and temperature (P/T) and low temperature overpressure protection (LTOP) system limits to 54 effective full power years (EFPYs), the end of the current period of extended operation.

Based on the U.S. Nuclear Regulatory Commission (NRC) staff review of the information provided, the NRC staff request for the following additional information:

1. The bases for the electromatic relief valve (ERV) requirements, contained in the application, stated that the ERV is signaled to open if the RCS pressure reaches a limit set in the LTOP actuation circuit. The LTOP actuation circuit monitors RCS pressure and determines when an overpressure condition is approached. When the monitored pressure meets or exceeds the setting, the ERV is signaled to open. The current LTOP-enabling ERV maximum lift setpoint is 460 pounds per square inch, gauge (psig).

NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" (ADAMS Accession No. ML070540076), Section 5.2.2, "Overpressure Protection,"

provides NRC staff review guidance for the application of pressure-relieving systems that function during low-temperature operation to ensure overpressure protection for the reactor coolant pressure boundary (RCPB) during low-temperature operation of the plant (startup, shutdown). Therefore, as a follow-on question to the third round RAI, the NRC staff requests that the licensee describe a limiting mass and energy addition analysis for the new LTOP ERV setpoint, at a level of detail consistent with

Section 5.2.2 of NUREG-0800 (the NRC staff recognizes that ANO-1 is not an SRP plant, however, this RAI is a follow-on to the third-round RAI which did not contain a sufficient level of detail). This description should include an expanded discussion of the "standalone thermal-hydraulic model of the pressurizer" which was used to determine the rate/total increase of RCS pressure for LTOP events, as discussed on Page 16 of ANP-3300Q3P, contained in the third-round RAI response dated March 25, 2015.

2. In proposed new TS Figure 3.4.3-1, the reactor coolant pump (RCP) restrictions were modified from no RCPs allowed to be operating at < 84 deg F, 2 between 84 and 225 deg F and 3 between 225 deg F and 300 deg F to 3 between 100 deg F and 300 deg F and no RCPs allowed to be operating at < 100 deg F. Please provide a justification for this change, including any impacts on the limiting mass and energy analysis.
3. In proposed new TS Figure 3.4.3-2, RCP restrictions were modified form no RCPs allowed to be operating at < 150 deg F, 2 RCPs operating between 150 deg F and 255 deg F, to no RCPs operating at < 100 deg F and 2 RCPs operating between 100 deg F and 250 deg F. In addition, Note 5 to the figure, which restricted cooldown rate to 30 deg F in 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> in the temperature range of 2 150-180 deg F was removed. Please provide a justification for these changes, including any impacts on the limiting mass and energy analysis.
4. ASME Code,Section XI, Nonmandatory Appendix G, "Fracture Toughness Criteria for Protection Against Failure," Paragraph G-2215 states, "LTOP systems shall limit the maximum pressure in the vessel to 100% of the pressure determined to satisfy Eq. (1)." Figure 1 of the licensee's March 25, 2015 RAI response shows the licensee's proposed P-T limits calculated in accordance with Eq. (1) of G-2215 along with the LTOP setpoint curve. Explain how the proposed LTOP setpoint "limits the maximum pressure in the vessel to 100% of the pressure determined to satisfy Eq. (1)" since the LTOP pressure setpoint, as shown in Figure 1, is higher that the cooldown limits calculated in accordance with Eq. (1) of G-2215.

These draft RAIs were sent to Mr. Bice and Mr. Clark of your staff on March 25, 2015, and updated via email on April 1, 2015 (the latter update added RAI #4). This email should be treated as formal transmittal of the RAIs to Entergy. A clarification call regarding these RAIs was held on April 1, 2015. A date of response to these RAIs was agreed to be April 7, 2015, given the requested accelerated review schedule. If you have any issues meeting the agreed-to date, please email or call.

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: 1967 Mail Envelope Properties (Andrea.George@nrc.gov20150402153400)

Subject:

Requests for Additional Information - 4th Round - ANO-1 P/T and LTOP Limits Update to 54 EFPY License Amendment Request - MF5292 Sent Date: 4/2/2015 3:34:38 PM Received Date: 4/2/2015 3:34:00 PM From: George, Andrea Created By: Andrea.George@nrc.gov Recipients: "CLARK, ROBERT W" <RCLARK@entergy.com> Tracking Status: None "PYLE, STEPHENIE L" <SPYLE@entergy.com> Tracking Status: None "BICE, DAVID B (ANO)" <DBICE@entergy.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 5200 4/2/2015 3:34:00 PM

Options Priority: Standard Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received: