ML19135A050

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Correction to Safety Evaluation for Amendment No.268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement
ML19135A050
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/21/2019
From: Kimberly Green
Plant Licensing Branch III
To:
Entergy Nuclear Operations
Green K,
References
EPID L-2018-LLA-0153
Download: ML19135A050 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 21, 2J19 Vice President, Operations Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530

SUBJECT:

PALISADES NUCLEAR PLANT-CORRECTION TO SAFETY EVALUATION FOR AMENDMENT NO. 268 REGARDING REVISION TO DIESEL GENERATOR UNDERVOLTAGE START SURVEILLANCE REQUIREMENT (EPID L-2018-LLA-0153)

Dear Sir or Madam:

On May 13, 2019, the U.S. Nuclear Regulatory Commission issued Amendment No. 268 to Renewed Facility Operating License No. DPR-20 for the Palisades Nuclear Plant (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19107A053).

On May 15, 2019, you notified the NRC of an error in Section 4.0 of the safety evaluation (SE).

The SE erroneously refers to the Illinois State official as being contacted and having no comments. The NRC staff contacted and received confirmation that the Michigan State official had no comments via email dated February 21, 2019. The SE should reflect that the Michigan State official was contacted and had no comments.

The NRC staff concludes that the error is entirely editorial in nature. The proposed correction does not change any of the conclusions in the SE associated with the amendment and does not affect the associated notice to the public. Enclosed, please find the corrected SE page.

Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255

Enclosure:

As stated cc: via Listserv

ENCLOSURE PALISADES NUCLEAR PLANT DOCKET NO. 50-255 RENEWED FACILITY OPERATING LICENSE NO. DPR-20 CORRECTED PAGE TO LICENSE AMENDMENT NO. 268 SAFETY EVALUATION PAGE 9

deviations from as-found and as-left values are tracked and controlled per the plant calibration procedures. The measurement and test instrumentation is tested and controlled per the plant administrative procedures to ensure that the test and measurement equipment is calibrated within the required accuracies.

The NRC staff reviewed the setpoint methodology and determined that it meets the intent of RG 1.105, Revision 3. The revised setpoints in the calculation resolve the calculation deficiencies identified in the LAR with regard to 10 CFR 50.36(c)(3).

3.5 Technical Conclusion Based on analyses provided in LAR Attachments 7 and 8, the NRC staff finds that the combined time delay setpoint of~ 6.2 seconds ands 7.1 seconds, as proposed in TS SR 3.3.5.2a.2, is acceptable. Based on the proposed degraded voltage relay (SLUR) settings, safety-related loads would be able to start and run, and provide their safety-related functions under accident conditions; therefore, the licensee will continue to meet the intent of GDCs 17 and 18.

3.6 Evaluation of Proposed TS Changes The NRC staff reviewed the proposed changes to TS SR 3.3.5.2a. As noted in the LAR, the existing TS SR 3.3.5.2a would be retained as TS SR 3.3.5.2a.1 and a description of the relay would be added in parentheses. The new TS SR for the combined time delay (degraded voltage sensing relay and time delay relay) would be added as SR 3.3.5.2a.2. As concluded above, the staff finds that the combined time delay setpoint of~ 6.2 seconds ands 7.1 seconds for proposed SR 3.3.5.2a.2 is acceptable. The frequency of TS SR 3.3.5.2 is not affected by the proposed change. The renumbering of SR 3.3.5.2a to 3.3.5.2a.1 and addition of the parenthetical description of the relay are administrative changes needed to accommodate the addition of the SR 3.3.5.2a.2, and therefore, are acceptable. The addition of SR 3.3.5.2a.2 for the combined time delay (degraded voltage sensing relay and time delay relay) resolves a nonconservative TS in accordance with the guidance in AL 98-10. Therefore, the NRC staff finds that the addition of TS SR 3.3.5.2a.2 is acceptable. The NRC staff has determined that SR 3.3.5.2a, as revised, represents a test of the degraded voltage relay settings to assure that the necessary quality of the degraded voltage relay settings will be maintained so that facility operation will be within the safety limits and the limiting conditions for operation will be met.

Therefore, revised SR 3.3.5.2a will meet 10 CFR 50.36(c)(3). As noted in AL 98-10, once any amendment correcting the TS is approved, the licensee must update the final safety analysis report, as necessary, to comply with 10 CFR 50.71(e).

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment on February 21, 2019. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes an inspection or a surveillance requirement. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no

ML19135A050 OFFICE NRR/DORL/LPL3/PM N RR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORLE/LPL3/PM NAME KGreen SRohrer DWrona KGreen DATE 05/15/19 05/15/19 05/21/19 05/21/19