ML20056D470

Forwards Request for Addl Info Re Util Response to GL 92-01, Rev 1, Reactor Vessel Structural Integrity, for Plant

ML20056D470
Person / Time
Site:	Sequoyah
Issue date:	07/27/1993
From:	Labarge D Office of Nuclear Reactor Regulation
To:	Medford M Tennessee Valley Authority
References
GL-92-001, TAC-M83513, TAC-M83514 NUDOCS 9308160266
Download: ML20056D470 (4)

Text

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e July 27, 1993 f

Docket Nos. 50-327 and 50-328 j

Tennessee Valley Authority ATTN:

Dr. Mark 0. Medford, Vice President Technical Support 3B Lookout Place 1101 Market Street

i Chattanooga, Tennessee.37402-2801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - RESPONSE TO GENERIC LETTER 92-01, REVISION 1 - SEQUOYAH NUCLEAR PLANT UNITS-1 AND 2 (TAC N05. M83513 AND M83514) l 1

By letter dated July 7, 1992, TVA responded to Generic Letter (GL) 92-01,.

Revision 1, " Reactor Vessel Structural Integrity," for the Sequoyah Nuclear Plant Unit I and Unit 2.

The purpose of the GL is to obtain'information needed to assess compliance with requirements set forth'in Appendices'G.and H

~

of 10 CFR Part 50 and commitments made,in response to GL 88-11 regarding reactor vessel structural integrity.

As a result of our review of the submittal,.the staff has identified the'need for additional information'in order to complete our review, as described in the enclosure. We request that you provide a response to the attached I

questions within 60 days of receipt of this request.

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires May 31, 1994.

Sincerely, Original' signed by l

David E. LaBarge, Sr. Project Manager l

Project Directcrate II-4 Division of Reactor Projects - I/Il l

Office of Nuclear Reactor Regulation

Enclosure:

RAI, GL 92-01 y

cc w/ enclosure:

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l Tennessee Valley Authority Sequoyah Nuclear Plant ATTN: Dr. Mark 0. Medford cc:

'Mr. W. H. Kennoy, Director County Judge Tennessee Valley Authority Hamilton County Courthouse ET 12A Chattanooga, Tennessee.37402 400 West Summit Hill Drive Knoxville, Tennessee 37902 Regional Administrator U.S.N.R.C. Region 11 Mr. R. M. Eytchison, Vice President 101 Marietta Street, N.W.

Nuclear Operations Suite 2900 Tennessee Valley Authority Atlanta, Georgia 30323 3B Lookout Place 1101 Market Street

^

Chattanooga, Tennessee 37402-2801 Mr. William E. Holland Senior Resident Inspector Sequoyah Nuclear Plant Mr. B. S. Schofield, Manager U.S.N.R.C.

Nuclear Licensing and Regulatory Affairs

.2600 Igou Ferry Road 1

Tennessee Valley Authority Soddy Daisy, Tennessee 37379 58 Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Mr. Robert Fenech, Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, Tennessee 37379 TVA Representative Tennessee Valley Authority 11921 Rockville Pike Suite 402 Rockville, Maryland 20852 Mr. Ralph Shell, Site Licensing Manager 1

Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000

- Soddy Daisy, Tennessee 37379 Mr. Michael H. Mobley, Director Division of Radiological Health 3rd Floor, L and C Annex 401 Church Street Nashville, Tennessee 37243-1532 General Counsel Tennessee Valley Authority ET 11H 400 West Summit Hill Drive Knoxville, Tennessee 37902 i

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1 A

7 ENCLOSURE RE0 VEST FOR ADDITIONAL INFORMATION RESPONSE TO GENERIC LETTER 92-01

(

Reference:

Question 2b in GL 92-01) 1.

Sequoyah Unit I response:

Table 2 indicates that the initial RT,3 value of the a.

Intermediate Shell forging 05 is -4*F, a value different from that of 40*F reported.in all previous submittals, including the latest pressure / temperature (P/T) limits submittal dated.

September 6, 1993'.

Explain this discrepancy.

b.

Table 1 indicates that the initial RT[Yongitudinal Charpy value of the Lower Shell Forging 04 is either 5'F data) or 73"F (transverse Charpy data).

Confirm that the value of 73"F will be used as the initial RT,g of the Lower Shell Forging 04.

c.

Table 2 indicates that the nickel content for the Intermediate Forging 05 is 0.86 percent, which is consistent with the value reported in the latest P/T limits submittal, but is quite different from the nickel content of 1.0 percent in the pressurized thermal ~ shock (PTS) submittal dated January 21, 1986.

Expl'ain this discrepancy.

2.

Sequoyah Unit 2 response:

a.

Table 5 indicates that the initial ~ RT value of the LowerShellForging04is-31*F,avalgue different from that of -22*F reported in all previous submittals, including the latest P/T limits submittal dated September 6, 1993.

Explain the discrepancy.

b.

Table 5 indicates that the nickel content of the Lower Shell forging 04 is 0.75 percent, which is close'to the value of 0.76 percent reported in the latest P/T limits submittal, but is quite different from the nickel content i

of 1.0 percent in the PTS submittal dated January 21, 1986.

Explain the discrepancy.

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