ML20247D566

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Forwards Request for Addl Info Re Rev 13 to First 10-yr Interval Inservice Insp Program for Plant
ML20247D566
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 03/21/1989
From: Black S
Office of Nuclear Reactor Regulation
To: Kingsley O
TENNESSEE VALLEY AUTHORITY
References
TAC-59458, NUDOCS 8903310125
Download: ML20247D566 (4)


Text

- .- __

March 21, 1989

'Docke Nos. 50-327/328 Distribution eDockete Elle- MSimms NRC PDR- JDonohew }

Local PDR JRutberg:  !

Mr. Oliver D. Kingsley, Jr. Projects Reading SVarga' Senior Vice President, Nuclear Power ADSP Reading BGrimes  !

Tennessee '! alley Authority DCrutchfield- Edordan 6N 38A Lookout Place BDLiaw ACRS(10) 1101 Market Street' SBlack GPA/CA Chattanooga, Tennessee 37402-2801 RPierson GPA/PA LWatson SQN Rdg. File

Dear Mr. Kingsley:

SUBJECT:

' REQUEST FOR ADDITIONAL INFORMATION, FIRST TEN-YEAR INSERVICE INSPECTION PROGRAM, REVISION 13 (TAC 59458) - SEQUQYAH NUCLEAR PLANT, UNIT 2 By letter dated November 9, 1988, the Tennessee Valley Authority submitted Revision 13 of the' first ten-year interval inservice inspection program for Sequoyah Nuclear. Plant, Unit 2. We can not complete our review until you provide responses to the enclosed request for additional information.

You are requested to provide this information within 45 days of receipt of-this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer then ten respondents; therefore, OMB clearance is not required under P. L.96-511.

Sincerely, Original signed by Rajender Auluck for Suzanne C. Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional

! Information cc w/ enclosure:

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o _ !Mr.' Oliver D. Kingsley,- Jr. - Sequoyah Nuclear Plant

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General Counsel . Regional ~ Administrator, Region II Tennessee Valley Authority U.S. Nuclear' Regulatory Comission 400 West Summit Hill Drive' 101 Marietta Street, N.W.

Eli B33 Atlanta, Georgia 30323 Knoxyt11e, Tennessee. 37902 .

Resident Inspector /Sequoyah NPL .

.Mr. R. L.'Gridley- c/o'U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou-Ferry Road SN 1578 Lookout Place Soddy Daisy, Tennessee: 37379 i

Chattanooga, Tennessee 37402-2801 ,

-Mr. John T..LaPoint Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radiological Health Sequoyah Nuclear Plant T.E.R.R.A.. Building, 6th Floor P.O. Box 2000 150 9th Avenue North Soddy Daisy, Tennessee' 37379 Nashville, Tennessee 37219-5404 Mr. M. Burzynski Dr. Henry Myers, Science Advisor Comittee on Interior

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Tennessee Valley Authority Sequoyah Nuclear Plant and Insular Affairs P.O. Box 2000 U.S. House of Representatives Soddy Daisy, Tennessee 37379 Washington, D.C. 20515 Mr. D. L. Williams Tennessee Valley Authority-Tennessee Valley Authority Rockville Office 400 West Summit Hill Drive 11921 Rockville Pike W10 B85 SuiteL402 Knoxville, Tennessee 37902 Rockville Maryland _20852 County Judge Hamilton County Courthouse Chattanooga, Tennessee 37402 1

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<,7 ENCLOSURE' REQUEST FOR ADDITIONAL INFORMATION F

BY:THE OFFICE OF NUCLEAR REACTOR REGULATION FIRST TEN-YEAR! INTERVAL ~ INSERVICE INSPECTION PROGRAM, REVISION 13 TENNESSEE VALLEY AUTHORITY i

SEQUOYAH NUCLEAR PLANT, UNIT 2 00CKET NO. 50-238 1.0~ SCOPE / STATUS OF REVIEW The'Sequoyah Nuclear Plant Unit 2 First 10-Year Interval Inservice Inspection (ISI): Program Plan is being evaluated for compliance with 10 CFR 50.55a(g)(4). .

Specifically,'the ISI Program Plan is.bein

'the appropriate. edition-of Section XI, (b)gacceptability evaluated for of (a) compliance'with examination sample, (c)' exemption criteria, and (d) compliance with ISI-related commitments identified during the NRC's previous Preservice Inspection (PSI) and ISI reviews.

.The first inspection interval began in June 1 -1982, and ends February 21, 1995.

The. requests for relief for the first 10-year inspection interval are also being evaluated. As required by 10 CFR 50.55a(g)(5), if the licensee determines

.that certain code examination requirements are impractical and requests relief

.from them, the. licensee- shall submit information and technical justification

'to the NRC to support that determination.

2.0 ADDITIONAL INFORMATION REQUIRED The licensee.provided a revised first interval ISI plan November 9, 1988.-

Based on review of the ISI plan, the staff cannot conclude that it is in compliancewith10CFR50.55a(g)(4). The staff cannot complete review of the ISI plan until the following additional information and/or clarification is submitted:

a. Code Case N-356, proposed for use in Section 4.0 of the ISI program, is not approved for use in Regulatory Guide 1.147. Please provide justifi-

' cation for'your need to use this Code case.

b.- Relief Request ISI-3 requests relief from 100% examination of Class 1 and 2 piping welds (ASME Section XI Categories B-F, B-J, and C-F).

However, in the weld listing table attached to Relief Request ISI-3, only Class l' welds are listed. Please provide a list of all Class 2 welds for which relief is r.pested under Relief Request ISI-3.

c. NRC Safety Evaluation Reports dated March 31, 1988 (Reference 2), and May 11, 1988 (Reference 3), reviewed TVA's program for control of micro-biologically induced corrosion (MIC) in the essential raw cooling water (ERCW) system. As a result of these reviews, the NRC required a program

=_____-____________-____________-_____-___ -

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. w of augmented inservice inspection of-the ERCW system as follows:

1. A semi-annual weld-by-weld visual inspection program to identify leaking welds. Upon leakage detection, a radiographic examination to determine the extent of MIC degradation in the weld volume shall be performed. j l
2. Along with the above inspections, the.following additional items -)

.are required: (a) at the same time leakage is detected, an 1 dssessment is made to ensure the acceptance criterion is not exceeded prior to the scheduled outage or repair; (b) the -

frequency of direct visual inspection of weld specific leaks is increased to monthly; and (c) the leakage from a weld does not exceed 0.5 gpm and the total leakage from all welds does not exceed 1 gpm.

This augmented inspection for the ERCW system is not mentioned in the ISI program. Please verify that the required inspections on the ERCW system will be performed as part of the Sequoyah, Unit 2 augmented ISI plan.

3.0 REFERENCES

a. R. Gridley (TVA) to NRC, November 9, 1988; Unit 2 Inservice Inspection Program, Surveillance Instruction 114.2, Revision 13.
b. 1 G. Zech (NRC) to S. A. White (TVA),Itarch 31, 1988; Safety Evaluation of Microbiologically Induced Corrosion (MIC) Program. q
c. R. A. Hermann (NRC) to S. A. White (TVA), May 11, 1988; Safety Evaluation of request for _ relief from examination of Essential Raw Cooling Water System piping affected by MIC.

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