ML120880435
| ML120880435 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/29/2012 |
| From: | Boska J Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Boska J, NRR/DORL/LPLI-1, 415-2901 | |
| References | |
| TAC ME7367 | |
| Download: ML120880435 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 29,2012 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511*0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION FOR CONTAINMENT WATER LEVEL MONITORING (TAC NO. ME7367)
Dear Sir or Madam:
On October 18, 2011, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment for Indian Point Nuclear Generating Unit No.2 which would revise the Technical Specifications on post-accident monitoring for the containment building water level.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAJ). On March 28, 2012, the Entergy staff indicated that a response to the RAI wouJd be provided within 30 days of the date of this letter.
Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely, Q~
hn P. Boska, Senior Project Manager lant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTAINMENT WATER LEVEL MONITORING ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO.2 DOCKET NO. 50-247 In a "05000286/LER-2011-005, Indain Point, Unit 3 Regarding Automatic Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps Due to Undervoltage on 480 Vac Vital Buses Due to a [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid. During a Severe Storm|letter dated October 18, 2011]] (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11297A028), Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment to the Technical Specifications (TSs) for Indian Point Nuclear Generating Unit No.2 (lP2) which would revise the TSs on post-accident monitoring for the containment building water level. The Nuclear Regulatory Commission staff is reviewing the submittal and has the following questions:
- 1.
Please provide a description of the containment and recirculation sumps including approximate volume and relative location in containment and confirm that the recirculation sump and the containment sump are independent sumps not connected below the containment floor at 46 feet.
- 2.
IP2's current configuration has redundant credited detectors co-located in the respective sumps. The proposed configuration credits one detector in each sump. Your licensing commitments with respect to Regulatory Guide (RG) 1.97 requires continuous and redundant indication for Category 1 variables. The proposed configuration is only redundant for detecting levels above the top of the respective sumps at the 46-foot elevation. Please list all required operator actions based on indicated containment level (wide range) and/or containment sump level (narrow range) and the corresponding water level(s).
- 3.
Provide an analysis describing how the proposed change appropriately fulfills the requirements for maintaining accident monitoring instrumentation in the plant TSs. List which detectors are credited for A7, B11 wide range, B11 narrow range, and C6 variables. These are the plant-specific designators which can be found in the IP2 RG 1.97 submittals, such as the letter dated August 30, 1985 (ADAMS Accession Nos.
ML100322029 and ML100322031 ).
- 4.
Entergy states in the second paragraph of Section 3.0, Technical Analysis, that "The minimum water level for the Recirculation pump to have adequate NPSH [Net Positive Suction Head] is a function of the specific type of LOCA [Loss-of-Coolant Accident] and the peak water level to keep equipment from flooding is elevation 50' 5"." Please identify the minimum water levels associated with adequate NPSH for each type of LOCA.
- 5.
The no-significant-hazards analysis takes credit for the detectors that are proposed to be removed from the plant TSs. Please provide justification for crediting the detectors that are being removed from plant TSs or provide analysis based on the detectors remaining in the TSs.
Enclosure
- See memo dated 3/12/12 OFFICE NAME DATE LPL 1-1/PM JBoska 3/29/12 LPL1-1/LA SLittie 3/29/12 EICB/BC*
JThorp 3/12/12 LPL1-1/BC GWilson (DPickett for) 3/29/12