ML082660339
ML082660339 | |
Person / Time | |
---|---|
Site: | Arkansas Nuclear |
Issue date: | 10/01/2008 |
From: | Wang A Plant Licensing Branch IV |
To: | Entergy Operations |
Wang, A B, NRR/DORL/LPLIV, 415-1445 | |
References | |
TAC MD9535 | |
Download: ML082660339 (5) | |
Text
October 1, 2008 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 1 - AMENDMENT RE: SODIUM HYDROXIDE (NAOH) TANK SOLUTION CONCENTRATION (TAC NO. MD9535)
Dear Sir or Madam:
By application dated July 30, 2008 to the U.S. Nuclear Regulatory Commission (NRC), Entergy Operations, Inc, (Entergy, the licensee) submitted a license amendment request to modify the Technical Specifications (TSs) for the Arkansas Nuclear One, Unit 1 (ANO-1). The proposed amendment would revise TS 3.6.6.3, Spray Additive System Surveillance Requirements.
TS 3.6.6.3 currently requires the NaOH tank solution concentration to be between 5.0 percent and 16.5 percent. Entergy proposes to change the concentration to be between 6.0 percent and 8.5 percent. The purpose of this letter is to provide the results of the NRC staff acceptance review of this amendment. 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 TSs) 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 NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request 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 Entergy supplement the application to address the information requested in the enclosure by October 3, 2008. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the
NRC staff 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 activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff detailed technical review by separate correspondence.
The information requested and associated time frames in this letter were discussed with Ms.
Natalie Mosher of your staff on September 11, 2008.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313
Enclosure:
As stated cc w/encl: See next page
ML082660339 OFFICE NRR/DORL/PM NRR/DORL/LA DCI/CSGB/BC NRR/DORL/BC NRR/DORL/PM NAME AWang GLappert ABW AHiser MMarkley AWang for DATE 10/1/08 9/24/08 9/11/08 10/1/08 10/1/08 Arkansas Nuclear One (6/19/08) cc:
Senior Vice President Pope County Judge Entergy Nuclear Operations Pope County Courthouse P.O. Box 31995 100 W. Main Street Jackson, MS 39286-1995 Russellville, AR 72801 Vice President, Oversight Senior Resident Inspector Entergy Nuclear Operations U.S. Nuclear Regulatory Commission P.O. Box 31995 P.O. Box 310 Jackson, MS 39286-1995 London, AR 72847 Senior Manager, Nuclear Safety Regional Administrator, Region IV
& Licensing U.S. Nuclear Regulatory Commission Entergy Nuclear Operations 612 E. Lamar Blvd., Suite 400 P.O. Box 31995 Arlington, TX 76011-4125 Jackson, MS 39286-1995 Senior Vice President
& Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Associate General Counsel Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Manager, Licensing Entergy Operations, Inc.
Arkansas Nuclear One 1448 SR 333 Russellville, AR 72802 Section Chief, Division of Health Radiation Control Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Section Chief, Division of Health Emergency Management Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867
BY THE OFFICE OF NUCLEAR REACTOR REGULATION IDENTIFICATION OF INFORMATION INSUFFICIENCY REGARDING SODIUM HYDROXIDE TANK SOLUTION CONCENTRATION LICENSE AMENDMENT REQUEST ARKANSAS NUCLEAR ONE, UNIT NO. 1 DOCKET NOS. 50-313 By application dated July 30, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082130343), to the U.S. Nuclear Regulatory Commission (NRC),
Entergy Operations, Inc, (Entergy, the licensee) submitted a license amendment request to modify the Technical Specifications (TS) for the Arkansas Nuclear One, Unit 1 (ANO-1). The proposed amendment would revise TS 3.6.6.3, Spray Additive System Surveillance Requirements. TS 3.6.6.3 currently requires the Sodium Hydroxide (NaOH) tank solution concentration to be between 5.0 percent and 16.5 percent. Entergy proposes to change the concentration to be between 6.0 percent and 8.5 percent. As part of the acceptance review process the NRC staff has concluded that the information delineated below is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment:
- 1. To enable the NRC staff to evaluate that reducing the maximum concentration will reduce the amounts of GSI-191 chemical precipitates, the NRC staff requires more information. Show that the reduction in maximum NaOH concentration will result in reduced chemical effects and provide the calculated quantity of chemical precipitates, by species, before and after the proposed change. Use NRC document, NRC Staff Review Considerations For Buffer Changes (ADAMS Accession No. ML0712803501),
for guidance.
- 2. To enable the NRC staff to evaluate that the sump pH will remain greater than 7 over the period of 30 days post-LOCA, the licensee is requested to provide the following information. Please refer to Comanche Peaks license amendment request (ADAMS Accession No. ML073410318) as it is similar.
- Provide the maximum concentration of strong acid concentrations in the sump for a period of 30 days post-LOCA.
$ Describe the analysis methodology used to determine the pH in the sump water during a period of 30 days post-LOCA. Include detailed calculations of the minimum pH values in the sump during a 30 day period post-LOCA to demonstrate that the pH remains greater than 7 throughout this time period.
- If a computer program was used, describe the code and provide the input and output data of the program.