ML13226A074

NRR E-mail Capture - Sequoyah 1 and 2 - Acceptance Review of LAR Modification of Ice Condenser TS (MF2446 and MF2447)

ML13226A074
Person / Time
Site:	Sequoyah
Issue date:	08/12/2013
From:	Siva Lingam Plant Licensing Branch II
To:	Mackaman C Tennessee Valley Authority
References
TAC MF2446, TAC MF2447
Download: ML13226A074 (1)

Text

From: Lingam, Siva To: Mackaman, Clyde Douglas (cdmackaman@tva.gov)

Cc: Broaddus, Doug; Dennig, Robert; Sallman, Ahsan; Bucholtz, Kristy

Subject:

Sequoyah 1 and 2 - Acceptance Review of License Amendment Request Regarding Modification of Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) (TAC Nos. MF2446 and MF2447)

Date: Monday, August 12, 2013 4:24:00 PM By letter dated July 3, 2013 (ADAMS Accession No. ML13199A281), Tennessee Valley Authority submitted a license amendment request (LAR) for Sequoyah Nuclear Plant, Units 1 and 2. The LAR would revise the Technical Specifications (TSs) 3/4.6.5, Ice Condenser. The proposed changes would revise TS Limiting Condition for Operation 3.6.5.1.d and TS Surveillance Requirement 4.6.5.1.d.2 to raise the overall ice condenser ice weight from 2,225,880 pounds (lbs) to 2,540,808 lbs and to raise the minimum TS ice basket weight from 1145 lbs to 1307 lbs, respectively. These changes are necessary to address the issues raised in Nuclear Safety Advisory Letter (NSAL) 11-5, Westinghouse LOCA [loss-of-coolant accident] Mass and Energy Release Calculation Issues. The issues identified in NSAL 11-5 affected plant-specific LOCA mass and energy release calculation results that are used as input to the containment integrity analyses. The basis for the proposed changes is provided in WCAP-12455, Revision 1, Supplement 2R, Tennessee Valley Authority Sequoyah Nuclear Plant Units 1 and 2 Containment Integrity Reanalyses Engineering Report. The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this LAR. 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.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed LAR in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.

If you have any questions, please contact me.

Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL2-2)

Sequoyah Nuclear Plant St. Lucie Plant Location: O8-D5; Mail Stop: O8-G9a Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov