ML16007A176
| ML16007A176 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/12/2016 |
| From: | Geoffrey Miller Plant Licensing Branch II |
| To: | Henderson K Duke Energy Carolinas |
| Miller G | |
| References | |
| CAC MF5293, CAC MF5294 | |
| Download: ML16007A176 (4) | |
Text
Mr. Kelvin Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 297 45 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 12, 2016
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2, ISSUANCE OF AMENDMENTS REGARDING NON-CONSERVATIVE TECHNICAL SPECIFICATION ALLOWABLE VALUE (CAC NOS. MF5293 AND MF5294)
Dear Mr. Henderson:
By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15320A333), the Nuclear Regulatory Commission issued Amendment No. 277 to Renewed Facility Operating License NPF-35 and Amendment No. 273 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments revised the Technical Specifications (TSs) to correct non-conservative setpoints. Specifically, the Allowable Value and Nominal Trip Setpoint for the Auxiliary Feedwater Loss of Offsite Power (Function 6.d) was modified. Additionally, the values in the associated Surveillance Requirement 3.3.5.2 were modified to the same values. As part of the change, the amendment also added the applicable footnotes in accordance with TSTF-493, Revision 4, "Clarify Application of Setpoint Methodology for LSSS Functions."
Subsequent to issuance, your staff identified that the amendment numbers were inadvertently omitted from one of the issued pages. Specifically, TS Page 3.3.5-2 did not include the amendment numbers 277 and 273 listed on the page. Accordingly, I have enclosed TS Page 3.3.5-2 with the amendment numbers included.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
If you have any questions, please call me at 301-415-2481.
Docket Nos. 50-413 and 50-414
Enclosure:
1. Corrected TS Page cc w/encls: Distribution via Listserv Sin~re5
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G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LOP DG Start Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3. 3. 5. 1
N 0 TE--------------------------------
SR 3.3.5.2 T esti n g shall consist of voltage sensor relay testing excluding actuation of load shedding diesel start, and time delay times.
Perform T ADOT.
Perform CHANNEL CALIBRATION with NOMINAL TRIP SETPOINT and Allowable Value as follows:
- a.
Loss of voltage Allowable Value.::::. 3396 V.
Loss of voltage NOMINAL TRIP SETPOINT =
3450 V.
- b.
Degraded voltage Allowable Value.::: 3738 V.
Degraded voltage NOMINAL TRIP SETPOINT =
3766 V.
Catawba Units 1 and 2 3.3.5-2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment Nos._.,~ 7 7, 2 7 3
ML16007A176 Sincerely,
/RA/
G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE NRR/LPL2-1 /PM NRR/LPL2-1/LA NRR/LPL2-1/PM NRR/LPL2-1/PM NAME GEMiller SFigueroa MMarkley GEMiller DATE 01/12/16 01/07/16 01/12/16 01/12/16