ML19332F161
| ML19332F161 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 12/08/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | Kingsley O Tennessee Valley Authority |
| References | |
| TAC-59457 NUDOCS 8912130480 | |
| Download: ML19332F161 (4) | |
Text
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E Oecember 8, 1989 l
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Docket No. 50-327 Distribution
-Jisii43Hii-JBrady NRC PDR JDonohew 1
Local PDR DSmith Mr. Oliver D. Kingsley, Jr.
SQN Reading DTerao Senior Vice President, Nuclear Power ADSP Reading OGC i
Tennessee Valley Authority DCrutchfield BGrimes 6N 38A Lookout Place BDLiaw EJordan i
1101 Market Street SBlack ACRS(10) l Chattanooga, Tennessee 37402-2801 RPierson GPA/CA BWilson l
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Dear Mr. Kingsley:
LWatson
SUBJECT:
REQUEST FOR INFORMATION - INSERVICE INSPECTION PROGRAM, FIRST 1
10-YEARINTERVAL(TAC 59457).SEQUOYAHNUCLEARPLANT, UNIT 1 By letter dated May 5,1989, the Tennessee Valley Authority submitted the first 10-year interval inservice inspection (ISI) program Revision 14. for Sequoyah Nuclear Plant, Unit 1.
We can not complete our. review of the report 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 than ten respondents; therefore, OMB clearance is not required under P. L. 97 511.
.i Sincerely, j
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uzanne C. B1
, Assistant Director i
for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information l
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General Counsel Mr. Kenneth M. Jenison Tennessee Valley Authority Senior Resident Inspector 400 West Summit Hill Drive Sequoyah Nuclear Plant ET llB 33H U.S. Nuclear Regulatory Comission Knoxville, Tennessee 37902 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Mr. F. L. Moreadith Vice President, Nuclear Engineering Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive T.E.R.R.A. Building, 6th Floor WT 12A 12A 150 9th Avenue North Knoxville, Tennessee 37902 Nashville, Tennessee 37219-5404 Dr. Mark 0. Medford Dr. Henry Myers, Science Advisor Vice President and Nuclear Canmittee on Interior Technical Director and Insular Affairs Tennessee Valley Authority U.S. House of Representatives 6N 38A Lookout Place Washington, D.C.
20515 Chattanooga, Tennessee 37402-2801 Tennessee Valley Authority Manager, Nuclear Licensing Rockville Office and Regulatory Affairs 11921 Rockville Pike Tennessee Valley Authority Suite 402 SN 157B Lookout Place Rockville Maryland 20852 Chattanooga, Tennessee 37402-2801 Mr. Joseph Bynum Acting Site Director Sequoyah Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Soddy Daisy, Tennessee 37379 Mr. Mark J. Burzynski Site Licensing Manager Sequoyah Nuclear Plant P. O. Box 2000 Soddy Daisy, Tennessee 37379 County Judge Hamilton County Courthouse Chattanooga, Tennessee 37402 Regional Administrator, Region II V.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Atlanta, Georgia 30323
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1 REQUEST FOR ADDITIONAL INFORMATION l'
BY THE OFFICE OF NUCLEAR REACTOR REGULATION FIRST 10 YEAR INTERVAL INSERVICE INSPECTION PROGRAM, REVISION 14 SEQUOYAH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-327 i
1.0 Scope / Status of Review-The first 10-Year interval of the Inservice Inspection (ISI) Program Plan for SequoyahUnit1isbeingevaluatedforcompliancewith10CFR50.55a(g)(4).
Specifically, the ISI Program Plan is being evaluated for (a) compliance with j
the appropriate edition of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) and, (b) compliance with ISI-related commitments identified during the NRC's previous Preservice Inspection (PSI) and ISI reviews.
The first inspection interval began on July 1, 1981, and ends on June 30, 1991.
The requests for relief from Code requirements for the first 10-year inspection interval are also being evaluated.
As required by 10 CFR 50.55a(g)(5), if the Tennessee Valley Authority (licensee) determines that certain Code examination r
requirements are impractical and requests relief from them, the licensee must submit information and technical justification to the Nuclear Regulatory Commission (NRC) to support that determination.
2.0 Additional Information Required The licensee provided Revision 14 of the first 10-year interval of the ISI plan for Sequoyah Unit 1 in a letter dated May 5,1989 (Reference 1).
Based on its review of the ISI plan, the staff cannot conclude that it it in corrpliance with 10CFR50.55a(g)(4).
In order to complete its review, the following additional information and/or clarification is required:
1.
Relief Request ISI-8, submitted in Reference 1, requests relief from volumetric examination of pressure retaining reactor coolant pump welds.
The basis for Relief Re ultrasonic testing (UT) quest ISI-8 is that the present capability of is not sufficient to examine the cast 304 stainless steel pump material and achieve meaningful results.
The staff and the nondestructive testing industry are in general agreement that perfoming ultrasonic testing of cast stainless steel (CSS) is diffi-cult because of poor acoustical properties of the materials of construc-tion.
However, the staff has always taken the position that the licen-see should stay abreast of the latest state-of-the-art developments in performing UT on the CSS.
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1 The latest ultrasonic testing systems, developed for inspection of welds in cast austenitic pumps, use large-diameter focused beam probes and low frequency compression waves to ultrasonically examine the total wall thickness of the pump.
In a recent field application of such a technique at a foreign nuclear plant, approximately 70% of the pump weld volume was successfully inspected without disassembly of the pump (Reference 2).
t Please discuss the possibility of performing an ultrasonic examination of the reactor coolant pump casing weld at Sequoyah Unit 1 by the end of the current 10-year interval using this technique or any other state-of-the-art techniques deemed appropriate.
2.
Section 20.11 of Reference 1 discusses the accelerated field weld inspection program implemented at Sequoyah Unit 1.
Relief Request 151-14 related to this augmented inspection program was submitted in the Sequoyah Unit 2 ISI plan, Revision 13 (Reference 3), but a similar relief request has not been submitted for Sequoyah Unit 1.
Please discuss the applicability of Relief Request 151-14 to Sequoyah Unit 1.
References 1.
C.H. Fox (TVA) to NRC, May 5, 1989; Sequoyah Nuclear Plant Unit 1 ISI Program (Surveillance Instruction 114.1), Revision 14, 2.
"UT Inspection of Coolant Pump Welds at Tihange-l", Nuclear News, Vol. 32 No. 10, August 1989, pp.44.
3.
R. Gridley (TVA) to NRC, November 9, 1988; Sequoyah Nuclear Plant Unit 2 ISI Program (Surveillance Instruction 114.2)
Revision 13.
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