ML100290023

Correction of Errata for Technical Specifications Change 07-05 - Upgrade of Emergency Core Cooling System Requirements

ML100290023
Person / Time
Site:	Sequoyah
Issue date:	01/26/2010
From:	Krich R M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME1115, TAC ME1116
Download: ML100290023 (4)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 January 26, 2010 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Correction of Errata for Technical Specifications Change 07-05 -Upgrade of Emergency Core Cooling System Requirements (TAC No. MEl115 and MEl116)

Reference:

Letter from TVA to NRC dated April 21, 2009, "Sequoyah Nuclear Plant (SQN) -Units 1 and 2 -Technical Specification (TS) Change No. 07-05, Emergency Core Cooling System (ECCS)" By letter dated April 21, 2009 (Reference), Tennessee Valley Authority (TVA) submitted a license amendment application to NRC to revise the Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specifications (TSs) to upgrade the emergency core cooling system TS.The enclosure provides a correction of errata that was inadvertently included in the application as described below.The Index Page for Unit 2 did not include mark-ups showing a revision to the TS Bases page numbering.

The enclosure provides the corrected marked-up page. TVA has determined that the additional information provided by this letter does not affect the no significant hazards considerations associated with the proposed TS changes. The proposed TS changes still qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9).

Printed on recycled paper U.S. Nuclear Regulatory Commission Page 2 January 26, 2010 There are no new regulatory commitments in this letter. If you have any questions about this change, please contact Beth A. Wetzel at (423) 843-7170.I declare under the penalty of perjury that the foregoing is true and correct.Executed on this 26th day of January, 2009.Respectfully, /R. M. Krich Vice President Nuclear Licensing

Enclosure:

Marked-up Index page for TS Change 07-05 cc (Enclosure):

Regional Administrator

-NRC Region II NRC Senior Resident Inspector

-Sequoyah Nuclear Plant Director, Division of Radiological Health -State of Tennessee ENCLOSURE SUPPLEMENTAL INFORMATION CONCERNING TECHNICAL SPECIFICATION CHANGE 07-05 -UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS MARKED-UP PAGE E-1 INDEX BASES SECTION PAGE 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE ......................................................................

B 3/4 4-4 3/4.4 .7 C H E M IS T R Y (D eleted) .....................................................................................................

B 3/4 4-4 r 3/4 .4 .8 S P E C IFIC A C T IV IT Y .........................................................................................................

B 3/4 4-5 3/4.4.9 RCS PRESSURE AND TEMPERATURE (P/T) LIMITS ....................................................

B 3/4 4-7 3/4.4.10 STRUCTURAL INTEG RITY (Deleted)

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B 3/4 4-14 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS (Deleted)

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B 3/4 4-14 3/4.4.12 LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEM ................

B 3/4 4-15 3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS-Operating 3/4.5.1 ACCUMULATORS

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3/45-3/4..2 amdd- -3 GGSS-118--YsT

....... (Dletd) .................

B 3/4 5-X' 2 3/4. .BO RO N INJECTIO N SYSTE M ........................................................................................

B 3/4 5-Z 15 3/4.5.5 REF GWATER STORAGE TANK .......................................................................

B3/4 5-15 3/4 .5.6 S EA L IN JEC T IO N ...........

_.....................................................................................

B 3/4 5-W ."16 3/4.6 CONTAINMENT SYSTEMS 3/4 5 3 ECCS -Shutdown.......

B 3/4 512 3/4.6.1 PR IM A R Y C O N TA IN M EN T ...................................................................................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ..........................................................

B 3/4 6-3 3/4.6.3 CONTAINM ENT ISOLATION VALVES ..............................................................................

B 3/4 6-3 3/4.6.4 CO M BUSTIBLE GAS CO NTRO L ......................................................................................

B 3/4 6-4 3/4 .6 .5 IC E C O N D E N S E R ..............................................................................................................

B 3/4 6-4 3/4.6.6 VA C U U M R ELIEF VA LV ES ...............................................................................................

B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4 .7 .1 T U R B IN E C Y C L E ...............................................................................................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION (Deleted)

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B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM ...................................................................

B 3/4 7-3a December 28, 2005 SEQUOYAH -UNIT 2 XIII Amendment No. 147, 188, 250, 284, 295 E-2