ML14161A142
| ML14161A142 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 08/22/2014 |
| From: | Wang A Plant Licensing Branch IV |
| To: | Entergy Operations |
| Orenak M | |
| References | |
| TAC MF3230 | |
| Download: ML14161A142 (4) | |
Text
Vice President, Operations Entergy Operations, Inc.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 22, 2014 Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADDRESS MULTIPLE ADMINISTRATIVE ISSUES WITH THE TECHNICAL SPECIFICATIONS (TAC NO. MF3230)
Dear Sir or Madam:
By letter dated December 9, 2013, Entergy Operations, Inc. (the licensee), proposed changes to the Waterford Steam Electric Station, Unit 3, Technical Specifications (TSs), which would improve clarity, correct administrative and typographical errors, or establish consistency with NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 4.0.
Specifically, the licensee requested changes toTS 3.3.1, Reactor Protective Instrumentation; TS 3.1.3.5, Shutdown CEA [Control Element Assembly] Insertion Limit, Applicability; TS 3.3.2, Engineered Safety Features Actuation System Instrumentation; TS 3.3.3.1, Radiation Monitoring Instrumentation; TS 3.3.3.6, Accident Monitoring Instrumentation; TS 3.3.3.11, Explosive Gas Monitoring Instrumentation; TS 4.8.2.1, D.C. Sources; TS 6.1, Responsibility; TS 6.2.1, Offsite and Onsite Organizations; TS 6.2.2, Unit Staff; and TS 6.12, High Radiation Area.
After reviewing your request, the Nuclear Regulatory Commission staff has determined that additional information is required to complete the review. On June 19, 2014, we discussed this information with your staff during a conference call. As discussed on the telephone, please provide additional information requested in the enclosure within 30 days of receipt of this letter.
If you have any questions, please contact me at 301-415-1445 or via e-mail at alan.wang@nrc.gov.
Docket No. 50-382
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely,
~w~
Alan B. Wang, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADDRESS MULTIPLE ADMINISTRATIVE ISSUES WITH THE TECHNICAL SPECIFICATIONS ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 By letter dated December 9, 2013 (Agencywide Documents A~cess and Management System Accession No. ML13345A686), Entergy Operations, Inc. (the licensee), proposed changes to the Waterford Steam Electric Station, Unit 3 (Waterford),Technical Specifications (TSs), which would improve clarity, correct administrative and typographical errors, or establish consistency with NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 4.0.
Specifically, the licensee requested changes toTS 3.3.1, Reactor Protective. Instrumentation; TS 3.1.3.5, Shutdown CEA [Control Element Assembly] Insertion Limit, Applicability; TS 3.3.2, Engineered Safety Features Actuation System Instrumentation; TS 3.3.3.1, Radiation Monitoring Instrumentation; TS 3.3.3.6, Accident Monitoring Instrumentation; TS 3.3.3.11, Explosive Gas Monitoring Instrumentation; TS 4.8.2.1, D.C. Sources; TS 6.1, Responsibility; TS 6.2.1, Offsite and Onsite Organizations; TS 6.2.2, Unit Staff; and TS 6.12, High Radiation Area.
The following question was developed as a result of the U.S. Nuclear Regulatory Commission staff's review of the licensee's license amendment request.
- 1.
Waterford's TS 4.8.2.1, D.C. Sources, Surveillance Requirement (SR) c.3, sets the limit of 150 x 1 o-6 ohms, for the resistance of cell-to-cell and terminal connection. On page 10 of Attachment 1 of the December 9, 2013, request, the licensee stated that this SR, by itself, does not ensure the battery is demonstrated to be operable. The licensee is proposing to add a provision to the SR indicating that the total battery inter-cell resistance value that maintains the battery terminal Voltage above the required operating voltage of the emergency loads also needs to be met. However, the provision does not contain a numerical total battery inter-cell resistance value.
According to Section 50.36 of Title 10 of the Code of Federal Regulations (1 0 CFR), TSs must contain Limiting Conditions for Operation (LCOs) and SRs.
LCOs are the lowest functional capability or performance levels of equipment,
required for safe operation of the facility. SRs ensure that the LCOs are met.
The licensee stated that the current SRs do not ensure the battery would be operable, meaning that the lowest functional capability or performance level might not be met with successful surveillance testing.
Please provide additional justification for why adding the provision in the surveillance procedure, instead of a numerical total battery inter-cell resistance value into the SRs, meets the intent of the LCOs.
Enclosure
ML14161A142 OFFICE NRR/DORLILPL4-2/PM NAME MOrenak DATE 06/19/14 OFFICE NRR/DE/EEEB/BC NAME JZimmerman*
DATE 5/20/14 Sincerely, IRA/
Alan B. Wang, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- memo dated NRR/DORLILPL4-2/PM NRR/DORLILPL4-2/LA A Wang JBurkhardt 06/24/14 6/11/14 N RR/DORLILPL4-2/BC NRR/DORLILPL4-2/PM DBro*addus A Wang 08/20/14 08/22/14