ML20235Z780

Forwards Rev 1 to Supplemental Info Re Miscellaneous & Structural Steel Thermal Growth,Per Util 870526 Submittal. Encls Include Commitment Re Calculation Completion & Calculations SCG1S81 & SCG1S81X2

ML20235Z780
Person / Time
Site:	Sequoyah
Issue date:	07/20/1987
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235Z781	List: ML20235Z780 ML20236A017 ML20236A039
References
NUDOCS 8707270401
Download: ML20235Z780 (12)

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot SN 157B Lookout Place JUL 201987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - REVISION 1 TO SUPPLEMENTAL INFORMATION REGARDING MISCELLANEOUS AND STRUCTURAL STEEL THERMAL GROWTH On May 26, 1987, TVA supplied supplemental information to NRC on platform and miscellaneous steel thermal growth. This letter was in response to an NRC request of April 22, 1987.

Subsequently, several questions were asked relative to the material and references cited in the May 26, 1987 letter.

As clarification, we are enclosing revision 1 to this supplemental information regarding thermal effects on miscellaneous and structural steel. It supersedes enclosure 1 of our previous submittal, pages Therm.NRC one through four.

Enclosure 2 lists a new commitment made by SQN. Enclosure 3 provides a _.

copy of requested calculations SCGlS81 and SCG1S81X2 for your information.

If any questions exist, please telerhone M. R. Harding at (615) 870-6422.

Very truly yours, TENNESSEE VALLEY AUTHORITY R. Gridley, Di ctor Nuclear Safety and Licensing Enclosures cc: See page 2 1

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3 no a gg72;gs$38(27 An Equal Opportunity Employer

U.S. Nuclear Regulatory. commission JUL 201987 cc (Enclosures):.

Mr. C. G. Zech, Assistant Director for Inspection Programs

' Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, suite 2900

' Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant. Director for Projects Division of TVA Projects Office of Special Projects U.S;. Nuclear Regulatory Commission 4350 East West Highway EWW 322 Bethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379

4 ENCLOSURE 1

- REVISION 1 l

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SUPPLEMENICL INFORMATION RESARDING THERM 2L EFFECTS ON NISCELLANEDUS AND STRUCTURAL STEEL

1. STATUS )

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The design has been completed. The design effort was performed primarily between December 11, 1986 and January 30, 1987.

Approximately 2000 man-hours were expended on this project.

The resolution of all unverified assumptions contained in R the calculations is scheduled for completion by June 30, 1987. 1 The implementation of modifications to four miscellaneous steel features is in progress.

2. BACKGROUND This condition was written as a result of Employee Concern Report 220.11 SQN R1. The actions to resolve this condition will be

, tracked and reviewed by the Employee Concern Program. This activity is also teneked as a Condition Adverse to Quality. .

A memo was written (Attachment B) to ensure that the condition described by Significant Condition Report SCRSQNCEBB5103 R

, is resolved as part of Employee Concern Report 220.11 SQN R1. 1

3. DESCRIPTION This condition is described by Significant Condition Report C SCRSQNCE886103 which states:

Some miscellaneous and structural steel structures were designed and installed without proper consideration of thermal load. The requirement to consider thermal load is specified by design criteria SDN-DC-U-1.3.3.1.

Definitions Ductility is defined as the amount of permanent strain up to thel l point of fracture (Salmon and Johnson, Steel Structures - DesionlR and Behavior Second Edition (1980) p.42). 1 The Standard Review Plan - NUREG-0800 - Section 3.B.4 -states that thermal loads can be neglected (for load combinations for R h steel structures) where it can be shown that they are secondary 1 and self-limiting in nature and where the material is ductile.

Thermal stresses are an example of secondary stresses as described by ANSI /AISC N690-1984 Commentary paragraph CQ 1.S.7.2. The commentary further stipulates that sufficisnt ductility must exist corresponding to a stress component for j that component to be classified as secondary. TVA is not [R1 THERMR1.NRC Page 1 of 6

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SUPPLEMENTAL IN ORM TION REGARDING THERMAL EFFECTS ON MISCELLANEOUS AND STRUCTURAL STEEL committed to ANSI /AISC NSSO-1984. This statement is provided R as an example of an industry standard which addresses thermal 1 loads.

4. SCOPE A thorough drawino review was performed by experienced design engineers who are familiar with thermal evaluations (See Attachment A). The purpose of this review was to identify all structural and miscellaneous steel structures which appear lR1 to be thermally restrained to the point that the resulting thermal growth might damage the structure or adjacent structures.

The results of this evaluation are documented in DNE-CEB Calculation SCG1SB1.

A thermal evaluation was performed for each of those structures which were identified in the drawing review. The primary function of the evaluation was to determine if the structure was ductile and if the stresses were secondary and self-limiting.

For those structures which were shown to meet this criteria, no further action is required.

C For those structures which did not iaeet this criteria, the connections were modified to allow thernei growth in key members so that the thermal load could be accomadated by the structure.

The drawings were revised and the modifications shall be implemented by ECN L6848.

S. PRDCEDURES The procedures are documented as part of the calculations for the identification and evaluation of thermal effects on miscellaneous and structural steel. Attachment A outlines the procedures contained in the calculations.

6.8 7.-EXAMPLES AND MODIFICATIONS Example No.1 " Worst-case" The framing shown on 4BNS37-1 was identified as being thermally restrained. The connections to concrete at the, ends of the tangential beams were determined to be non-ductile. Also, there was a potential for the radial beams to damage the concrete columns. Modifications to correct both conditions were implemented. This is considered as the worst case thermal condition found in the evaluation. It was determined that-without the modifications, the thermal load would reach equilibrium before failure would occur, however the stresses would be outside the THERNR1.NRC Page 2 of 6

E SUPPLEMENTftL INFORMATION,REGARDiNG THERMAL EFFECTS ON MISCELLANEOUS RND STRUCTURRL STEEL design criteria. (See drawings 4BNS37-1,4,S and calculation SCG1SB1XS)

Example No.2 " Typical modification" The platform shown on MONSOS was identified as being thermalig

. restrained. The evaluation concluded that the connections for the beams which intersected the crane well at azimuths 310, 230 and 218 would be subjected to a inrge shear during a thermal event. -Modifications wers recommended. It was determined that without the modifications, the thermal load would reach ~

equilibrium before failure would occur, however'the stresses would be outside the design critoria. (See drawings 48NSOS and 48NSOS-1 and calculation SCG1SG1X4 for modifications)

Example No.3 "No modification required" The fonture shown on 48NS28 was identified as being thermally restrained but was determined to exhibit ductility under thermal loading. HNo modification was required. (See drawings 4BNS28)

8. QUALITY CONTROL The calculations process is controlled by the Nuclear Engineering Procedure 3.1.

C 17e following calculations were developed:

DNE Calculations - SCG1581 - RINS 82S870128800 - Selection of miscellaneous and structural steel which require thermal evaluation -SCRSQNCEB06103 DNE Calculations - SCG1581X2 - RIMS B2SB70128801 - Thermal

-evaluation of structures identified to resolve SCRSONCEBBS103 DNE Calculations - SCG1581X3 - RIMS B2S870127801 - Modify instrument room access platform to provide thermal. releases for SCRSONCEB86103 -4BNSO2 DNE Calculations - SCG1SB1X4 - RIMS BES870128812 - Modify RCP access platform loop 3 & 4 to provide thermal releases for SCRSONCEB86103 - 48NSOS Cunit 2)

DNE Calculations - SCG1SB1XS - RIMS B2SB701E8811 - Modify pipe support framing in accumulator room 4 (Unit 2) to provide therm releases required for SCRSONCEB06103 - 4BNS37-1 The calculations required to resolve the thermal issue were approved by:

C.N. Jahrtson -

Lead Civil Engineer, Sequoyah Nuclear Plant.

B.S.C.E. Indiana Institute of Technology.

Professional Engineer State of Tennessee.

THERNR1.NRC Page 3 of 5

SUPPLEMENTAL INFORMATION RESARDiNG THERMAL EFFECTS DN MISCELLANEOUS AND STRUCTURAL STEEL The calculations required to resolve the thermal issue were reviewed by:

L.A.' Rather -

Principal Engineer, Supervisor of Civil Structural Section No. 1 at Sequoyah Nuclear Plant.

B.S.C.E. University of Mississippi, 1962.

Nineteen years of nuclear related experience.

The drawings review was performed by the following engineers:

J.R. Dickey -

B.S.C.E. Auburn University.

M.S.C.E. Auburn University.

Seventeen Years af Nuclear Related Design Experience.

Dr. Chennagiri U. Char - '

B.S.CCivil) - University of Mysore, Bangalore.

N.S.CAerospace) - Indian Institute of Science, Bengalers.

M.S.CStructure) - Louisiana State University, Baton Rouge, La.

Ph.D. (Engg. Mechanics) - Louisiana State University, Baton Rouge, La.

Professional Engineer State of Louisiana, North Caroline.

Member ASCE, ACI, ASME.

Gera P. Sinkovics -

M.S. Architectural and Structural Engineering - Royal Jozsef Nador Technical University, Budapest, Hungary Professional Engineer State of Pennsylvania The thermal evaluation of miscellaneous and steel was performed by the following engineers:

Leonard Madison -

B.S.C.E. Virginia Tech 1969.

M.S.C.E. University of Tennessee 1973.

Professional Engineer State of Tennessee.

Member ASCE..

Twenty years of Nuclear Related Experience.

Ray R. Funk -

B.S.C.E. University of Tennessee.

Professional Engineer State of Tennessee.

Member ACI 349 Committee.

Member ACI 355 Committee. ..

Member ASCE Task Committee on Steel Chimney Liners.

Thirty three years of structural design experience.

THERNR1.NRC Page 4 of 6

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. SUPPLEt1 ENTAL INFORf1ATION REGARD!'NG THERMAL EFFECTS ON MISCELLANEOUS AND STRUCTURAL STEEL S. ATTACHMENTS INCLUDED IN THE TRANSf1ITIAL

. Engineering Report SCRSONCEBBS103 Rev 1 TUR Design Criteria SQN-DC-U-1.3.3.1 Rev 4 TVA Drawing MBNSOS Rev 26, 4BNS05-1 Rev'O TUA Drawing MONSES Rev 10 TVA Drmwing 4BNS37-1 Rev 7; 4BNS37-5 Rev 0; 4BNS37-6 Rev 0 DNE Calculations - SCG1561X4 - Rev 0 - RINS B25870128812 DNE Calculations - SCG1SB1XS - Rev 0 - RIMS B25870128811 Attachment B - riemo from J. B. Hosmer to R.C.Denney R dated 6/19/87 RIris B25 870619 022 1

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THERf1R1.NRC Page S of G m__.__ _ _ _ . - _ _ ._ _ _ _ _.___ ___-_

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• SUPPLEMENTAL INFORMATION REGARDING . .

THERMAL EFFECTS ON MISCELLANEOUS AND STRUCTURAL STEEL ATTACHMENT A

-REUIEW EACH STRUCTURAL AND MISCELLANEOUS

' STEEL FEATURE IN THE REACTOR AND AUXILIARY BUILDINGS '

THIS REVIEW'IS DOCUMENTED BY CALCULATION SCG1SB1 l

-YES- IS THE STRUCTURE OBUIDUSLY AXIALLY RESTRAINED 40-WITH REGARD TO THERMAL GROWTH 7 j l

DOES THE STRUCTURE APPEAR TO HAVE A HIGH DEGREE OF INTERNAL RESTRAINT -NO WITH REGARD TO THERMAL GROWTH 7 YkS THERMAL LOADS MAY BE NEGLECTED I

CLASSIFIED AS GROUP I CLASSIFIED AS GROUP II HIGH DEGREE OF AXIAL- HIGH DEGREE OF INTERNAL

( RESTRAINT.

I RESTRAINT ASSIGN A PRIORITY TO THE DESCRIBE I

. SEVERITY OF THE CONDITION-1 I A THERMAL EUALUATION WAS PERFORMED TO DETERMINE:

1) IS THE STRUCTURE IN A HARSH THERMAL ENVIRONMENT

2) WILL THE STRUCTURE EXHIBIT DUCTILE AND SELF LIMITING BEHAVIOR 7 THIS EUALUATION IS CONTAINED IN CALCULATION SCG1SB1XE EUALUATE ALL EUALUATE HIGH PRIORITY GROUP I STRUCTURES GROUP II STRUCTURES l

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NONE MODIFIED L RECOMMEND MODIFIED BOUNDARY CONDITIONS SO.THAT l THERMAL LDAD MAY BE ACCOMMODATED BY THE STRUCTURE L ,

MODIFY FOUR STRUCTURES L

THERNR1.NRC o-c - , - e

TV A*64 (18 945) ,

• UNITED STATES GOVERNMENT QA Record iMemorandum TENNESSEE VALLEY AUTHORITY 022 B25 '870619 To  : R. C. Denney Employee Concerns Program Manager, DSC-P, Sequoyah Nuclear Plant FROM  : J. B. Hosmer, Project Engineer Sequoyah Engineering Project DSC-E, fc<voyah Nuclear Plant

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JUN 191987 SUDJECT: SEQUOYAH NUCLEAR PLANT (SQN) - EMPLOYEE CONCERN TASK GROUP (ECTG) ELEMENT REPORT 220.11 - CORRECTIVE ACTION PLAN - SUPPLEMENTAL INFORMATION

Reference:

My memorandum to you dated October 27, 1986 (B25 861027 005)

The condition adverse to quality (CAQ) described by SCR SQNCEB86103 should be included as part of the resolution of employee concern element report No. 220.11. This is not a change in the previously specified scope and corrective action plan of the listed reference. The condition described by SCR SQNCEB86103 represents the miscellaneous steel and platform portions of the corrective action plan.

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..y f'B.Hosmer M k FST:KAS cca RIMS, SL 26 C-K G. P. Cooper, 5-215 SB-K R. O. Hernandez , W9 C127 C-K C. N. Johnson, DSC-A, Sequoyah

'T. C. Price, 5-233 SB-K R. D. Rudder, DSC-E, Sequoyah L. Tummel, DSC-E, Sequoyah F._S. Taylor, DSC-G, Sequoyah i

' SQEP - June 16, 1987 f DE01;KS7162.03 Buy .S. Savings Bonds Regularly on the Payroll Savings Plan.

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ENCLOSURE 2

1. . The resolution of' all unverified assumptions contained in the structural steel thermal growth calculations is scheduled for completion by July 31,.,1987.

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ENCLOSURE 3 l

l l CALCULATION SCG1S81 l

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CALCULATION SCC 1S81X2 l

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