ML031490355

Revised Information Regarding TS Change 02-07, One Time Frequency Extension for Type a Test Containment Integrated Leak Rate Test

ML031490355
Person / Time
Site:	Sequoyah
Issue date:	05/19/2003
From:	Salas P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MB6987, TAC MB6988
Download: ML031490355 (4)

Text

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 May 19, 2003 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-328 Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT (SQN) - REVISED INFORMATION REGARDING TECHNICAL SPECIFICATION (TS) CHANGE 02-07, "ONE-TIME FREQUENCY EXTENSION FOR TYPE A TEST (CONTAINMENT INTEGRATED LEAK RATE TEST [CILRT])," TAC NOS. MB6987 AND MB6988

References:

1. TVA letter to NRC dated October 4, 2002, "Sequoyah Nuclear Plant (SQN) - Units 1 and 2 Technical Specification (TS) Change No.

02-07, "One-Time Frequency Extension for Type A Test (Containment Integrated Leak Rate Test [CILRT])"

2. TVA letter to NRC dated February 19, 2003, "Response to Request for Additional Information (RAI) Regarding Technical Specification (TS) Change No. 02-07,

'One-Time Frequency Extension for Type A Test (Containment Integrated Leak Rate Test

[CILRT])' (TAC Nos. MB6987 and MB6988)"

3. TVA letter to NRC dated April 14, 2003, "Sequoyah Nuclear Plant (SQN) -

Supplemental Information Regarding Technical Specification (TS) Change No. 02-07, "One-Time Frequency Extension for Type A Test (Containment Integrated Leak Rate Test [CILRT])," TAC Nos. MB6987 and MB6988 Pnnted on ecyWed paper

-DO '

A1 2

U.S. Nuclear Regulatory Commission Page 2 May 19, 2003 This letter provides a revised proposed TS page (enclosed) for Unit 2. This change, as NRC suggested, modifies a previously proposed revision (TVA' s referenced letters) to the TS language for Unit 2 regarding the frequency extension for performing a Type A test. NRC explained that the revision will eliminate possible ambiguity as a result of a one-cycle extension for Unit 2 that NRC approved on May 7, 2002. This revision is editorial in nature and does not change the "No Significant Hazard Determination" contained in the referenced letters.

This letter is being sent in accordance with NRC RIS 2001-05.

There are no commitments contained in this submittal.

Please direct questions concerning this issue to me at (423) 843-7170 or J. D. Smith at (423),843-6672.

I declare under penalty of perjur that the oregoing is true and correct. Executed on this l\day of _2i3 Licenn5tp and Industry Affairs Manager Enclosure cc (Enclosure):

Mr. Michael L. Marshall, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop O-8G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE

'- : REVISED INFORMATION FOR TECHNICAL SPECIFICATION (TS)

CHANGE NO. 02-07, ONE-TIME FREQUENCY EXTENSION FOR TYPE A TEST CONTAINMENT INTEGRATED LEAK PATE TEST E-1

ADMINISTRATIVE CONTROLS 6.8.4 f. Radioactive Effluent Controls Proaram (Cont.)

of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY SHALL BE LIMITED to the following:

1. For noble gases: Less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and

2. For lodine-1 31, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/yearto any organ.

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine-1 31, lodine-1 33, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

g. Radiological Environmental Monitoring Prociram (DELETED)

h. Containment Leakage Rate Testina Proaram fall 2003 A program shall be established to implement the akage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 endix J, Option B, as modified by approved exemptions. Visual examination and testin including test intervals and extensions, shall be in accordance with Regulatory Guide (RG) .63, "Performance-Based Containment Leak-Test Program," dated September 1995 with ceptions provided in the site implementing instructions. Performance of the spiig 202 containment integrated leakage rate (Type A) test may be deferred up to efie reyGe bUt no later than fall 2O0-. _____

LAJff3 N ' ___ -le n t spring 2007 The peak calculated containment intemal pressure for the design basis loss of coolant accident, P8, is 12.0 psig.

The maximum allowable containment leakage rate, La, at Pa, is 0.25% of the primary containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criteria is f 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the combined Type B and Type C tests, and < 0.75 La for Type A tests; May 2, 2002 SEQUOYAH - UNIT 2 6-9 Amendment No. 28, 50, 64, 66,134, 165, 202, 207, 223,265 E-2