ML12193A516
| ML12193A516 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/19/2012 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Pickett D | |
| References | |
| TAC ME8750 | |
| Download: ML12193A516 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 19, 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 Uf\\IIT NO.3 SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: OPERABILITY OF ATMOSPHERIC DUMP VALVES (TAC NO.
ME8750)
Dear Sir or Madam:
By letter dated May 23, 2012, Entergy Nuclear Operations, Inc., the licensee, submitted a license amendment request for Indian Point Nuclear Generating Unit No.3. The proposed amendment would revise Technical Specification 3.7.4, "Atmospheric Dump Valves (ADVs)," to require all four ADVs to be operable. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff'S acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by August 6, 2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review actives associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
Vice-President, Operations
- 2 The information requested and associated time frame in this letter were discussed with Mr. Steve Prussman of your staff on July 17, 2012.
If you have any questions, please contact me at (301) 415-1364.
Sincerely, Douglas Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
As stated cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO.3 DOCKET NO. 50-286
- 1. The atmospheriC dump valves (ADVs) are credited in the steam generator tube rupture (SGTR) analysis. The proposed revision to TS Bases Section 3.7.4 states that no failure of a second ADV is postulated. In addition, the SGTR analysis in both the Indian Point Unit 3 Updated Final Safety Analysis and the NRC's safety evaluation for the 4.85 percent stretch power uprate dated March 24, 2005, did not address single active failures of ADVs. Please provide the licensing basis for not assuming a single active failure for the SGTR analysis.
- 2. The proposed revision to TS Bases 3.7.4 describes how 4 ADVs must be OPERABLE to ensure that at least 3 ADVs are available to conduct a plant cooldown following a SGTR. Please confirm the number of ADVs required for plant cooldown in the analysis of record, and discuss whether it is possible to cool the plant down safely following a SGTR with fewer ADVs.
- 3. Revision 2 to Indian Point emergency operating procedure 3-E-3 (page 12 of 56) describes available operator actions to vent the faulted steam generator to the atmosphere. While this version of the emergency operating procedure may be out of date, please clarify the conditions under which plant operators would vent the faulted steam generator to atmosphere and whether such actions would be bounded by the dose analysis of record.
Enclosure
ML12193A516 II OFFICE LPL 1-1/PM LPL1-1/LA SBPB/BC i SRXB/BC(A) LPL1-1/BC NAME DPickett KGoldstein GCasto ISMiranda GWilson i~
DATE
. 07 117 : 12 J07 116/12 07/19/12 107/19/12 07/19/12
-