ML18037A912

Provides Response to NRC ,Requesting That Util Confirm plant-specific Applicability of TR NEDO-32205,Rev 1 & Verification of Plant Specific Info Entered Into NRC Computerized Rv Integrity Database Re GL 92-01,Rev 1

ML18037A912
Person / Time
Site:	Browns Ferry
Issue date:	05/23/1994
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NUDOCS 9406010285
Download: ML18037A912 (12)

Text

ACCELERATED DI UTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9406010285 DOC.DATE: 94/05/23 NOTARIZED:

NO DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION SALAS,P.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides response to NRC 940419+Or re GL 92-01,Rev 1,

"Reactor Vessel Structural Integrity."

DISTRIBUTION CODE: A028D COPIES RECEIVED:LTR ENCL J SIZE:

S TITLE: Generic Letter 92-01 Responses (Reactor Vessel S ructural Integrity 1 /

NOTES:

RECIPIENT ID CODE/NAME PD2-4-PD WILLIAMS,J.

INTERNAL: ACRS NRR/DORS/OGCB NRR/DRPW OC/LFDCB G FILE 01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1

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1 RECIPIENT ID CODE/NAME TRIMBLE,D NRR/DE/EMCB NRR/DRPE/PDI-1 NUDOCS-ABSTRACT OGC/HDS3 RES/DE/MEB NSIC COPIES LTTR ENCL 2

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NOTE TO ALL"RIDS" RECIPIENTS:

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PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISI'RIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 23 ENCL 21

Tennessee Valley Authority. Post Office Box 2000. Decatur. Alabama 35609

'NAY 23 594 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In,the.Matter Of Tennessee Valley Authority Docket Nos.

50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)

TVA 8 RESPONSE TO NRC 8 LETTER DATED APRIL 19'994~

GENERIC LETTER (GL) 92-01/

REVISION 1~

"REACTOR VESSEL STRUCTURAL INTEGRITY/"

The purpose of this letter is to provide TVA's response to NRC's April 19, 1994, letter.

In that letter, NRC requested that TVA provide additional information regarding GL 92-01.

Specifically, NRC requested that TVA confirm the plant-specific applicability of topical report NED0-32205, Revision 1, and request approval of the NEDO document as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G.

Also, NRC requested that TVA verify the BFN plant specific information entered into NRC's computerized Reactor Vessel Integrity Database (RVID).

TVA's response to the requested information and corrections to the RVID are contained in Enclosure 1.

Additionally, in the April 19, 1994 letter, NRC states that one open issue remains for Unit 1.

Specifically, NRC has not validated the initial RT>>Yvalues for the Unit 1 reactor vessel because NRC has not approved General Electric's (GE) initial methodology used in the RT>>~ calculation.

NRC also considers that the Boiling Water Reactor Owners Group (BWROG) report GE-NE-523-109-0893, "Basis for GE RT>>T Estimation Method," is not sufficient to resolve this issue.

As a

result, NRC requested that TVA either commit to the BWROG's effort to resolve this issue, or provide a schedule for a plant specific analysis.

In response to NRC's request, TVA is committing to the BWROG's effort.

(

9406010285 940523 PDR ADOCK 0500025'P P

.:PDR

U.S. Nuclear Regulatory Commission Page 2

NAY 23 1994 Enclosure 2 contains the commitments contained in this letter. If you have any questions, please telephone me at (205) 729-2636.

Sincerel Pe ro Salas Manager of Site Licensing Enclosure cc:

See page 3

I J

U.S. Nuclear Regulatory Commission Page 3

NAY 23 1994 Enclosure cc (Enclosure):

Mr. Mark S. Lesser, Section Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637

Athens, Alabama 35611 Mr. J.

F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. D.

C. Trimble, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

~ c~

)

I A

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ENCLOSURE 1

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1i 2q AND 3 GENERIC LETTER (GL)92-01i REVISION 1

RESPONSE

TO NRC APRIL 19'994'EQUEST FOR ADDITIONAL INFORMATION I.

Introduction During NRC's review of TVA's responses to GL 92-01, Revision 1, NRC identified the need for additional information.

Specifically, by letter dated April 19,

1994, (Reference 1)

NRC requested certain information regarding topical report NED0-32205, Revision 1.

NRC also requested that TVA verify the information contained in NRC's Reactor Vessel Integrity Database (RVID).

The specific information requested and TVA's responses are provided below.

II'ESPONSE TO NRC REQUESTS NRC Request Provide confirmation of the plant-specific applicability of topical report NED0-32205, Revision 1, as specified in Appendix B to the NEDO.

TVA Response, TVA's review of NED0-32205, Revision 1, indicates that the end-of-life (EOL) upper shelf energy (USE) drops (predicted by Regulatory Guide 1.99, Revision 2) for the limiting plates or limiting welds for BFN Units 1, 2,

and 3 are smaller than the corresponding values contained within the topical report.

Since no surveillance capsule data exists at this time for BFN, TVA considers BFN to be bounded by the equivalent margin analysis as defined in the topical report.

TVA will confirm full applicability following removal and analysis of the surveillance capsules for each unit.

TVA will inform NRC of the results within 90 days of issuance of the final surveillance capsule analysis report.

NRC Request Submit a request for approval of topical report NEDO-32205, Revision 1, as the basis for demonstrating compliance with 10 CFR Part 50, Appendix G, Paragraph IV.A.1.

ii"

TVA Response In the enclosure of the Reference 3 letter, Item 2.a

response, TVA stated that it plans to use NED0-32205, "BWR Owners'roup Topical Report on Upper Shelf Energy Equivalent Margin Analysis," as its licensing basis to demonstrate that beltline materials maintain adequate USE margins.

Since this response was submitted, the NEDO report was revised.

TVA hereby requests approval of Revision 1 of this NEDO as the basis for demonstrating compliance with 10 CFR 50, Appendix G, Paragraph IV.A.1 for BFN Units 1, 2, and 3.

NRC Request Verify that the information provided for BFN Units 1, 2, and 3 was accurately entered in the Reactor Vessel Integrity database.

TVA Response TVA has reviewed the BFN Units 1, 2, and 3 specific information entered into NRC's Reactor Vessel Integrity database.

The data for BFN is accurate with the following exceptions:

1.

Reference 1, Enclosures 1 and 2, BFN Unit 2, the Heat Number for one of the Lower Shell Courses is incorrectly identified as C2460-1.

The reference 2 letter defines the correct Heat Number as C2460-2.

2.

Reference 1, Enclosure 1,

BFN Unit 3, incorrectly identifies Circumferential Weld (Heat Number D51852) as having the same percent nickel concentration (0.66 percent nickel) and Chemistry Factor (117.1) as Heat Number D55733.

The reference 2 letter defines the percent nickel for Circumferential Weld (Heat Number 51852) as 0.67, which provides a Chemistry Factor of 117.45.

3.

Reference 1, Enclosure 2,

BFN Units 1, 2,

and 3

states that the material type is A 302B for the lower and intermediate shell courses.

Although, the Reference 2 letter also specified the material type as A 302B, NED0-32205, Revision 1

now differentiates between material types A 302B and A 302B Modified.

Accordingly, TVA provides clarification that BFN Unit 1, 2,

and 3 material type for the lower and intermediate shell courses is A 302B Modified.

E1-2

I

,III'EFERENCES 1.

Letter from NRC to TVA dated April 19, 1994 Generic Letter (GL) 92-01, Revision 1, "Reactor Vessel Structural Integrity," Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2,

and 3

(TAC Nos.

M83438, M83439, and M83440) 2.

Letter from TVA to NRC dated July 7,

1992, Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN),

and Watts Bar Nuclear Plant (WBN)

Response

to Generic Letter 92-01 (Reactor Vessel Structural Integrity) 3.

Letter from TVA to NRC dated August 2,

1993, BFN

Response

To Request For Additional Information, Generic Letter 92-01, Revision 1

4.

Letter from TVA to NRC dated December 1,

1992, BFN Completion Of Commitment Made In Response To Generic Letter 92-01, "Reactor Vessel Structural Integrity" E1-3

ENCLOSURE 2

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1I 2i AND 3 GL 92-01 REVISION 1 RESPONSE TO APRIL 19~

1994/

REQUEST FOR ADDITZONAL INFORMATION LIST OF COMMITMENTS 2 ~

3 ~

TVA will confirm full applicability of NED0-32205, Revision 1, "BWR Owners Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis," following removal and analysis of the surveillance capsules for each Unit.

TVA will inform NRC of the applicability of NEDO 32205, Revision 1, to each Unit within 90 days of issuance of the final surveillance capsule analysis report.

TVA is committed to the BWROG effort to validate the GE methodology for resolving the initial RT>> issue for BFN Unit 1.