ML19330C314

Forwards Response to NRC 800729 Request for Info on Containment Analysis.Comments on R&D Associates Rept, Sequoyah Containment Analysis & Viewgraphs from Util 800709 & 11 Presentations Encl

ML19330C314
Person / Time
Site:	Sequoyah
Issue date:	08/05/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8008080227
Download: ML19330C314 (25)

Text

• '

TENNESSEE VALLEY AUTHORITY cs ATrAr;qqog. n:tmessrc~n sor '" 8,['

400 Chestnut 5treet Tower II u.

August 5, 1980 e.

Director of Nuclear Reactor Regulation

?

' Attention:

Mr. A. Schwencer, Chief

~

Licensing Branch No. 2

.1 Division of Licensing L!

4 U.S. Nuclear Regulatory Commission

~

Washington, DC 20555

Dear Mr. Schwencer:

In the Matter of the Application of

)

Docket Nos. 50-327 Tennessee Valley Authority

)

50-328 In response to R. L. Tedesco's letter to H. G. Parris dated July 29, 1980, we are enclosing the requested information on the Sequoyah Nuclear Plant Containment Analysis. Enclosure 1 is TVA's comments on the R&D Associates report "Sequoyah Containment Analyses."

TVA presented analyses of the structural ability of the Sequoyah containments to withstand the effects of hydrogen ignition / detonation to the ACRS subcommittee and full committee meetings with TVA on July 9 and July 11, 1980, respectively. The transcripts of the TVA presentation on July 9 (subcommittee) are pages 185 through 239, with eleven slides (Enclosure 2A). The transcript of the TVA presentation on July 11 (full committee) are pages 437 through 459, with eleven slides (Enclosure 23).

On July 29, 1980, TVA met with the NRC staff to present additional material on our current studies of effects of hydrogen ignition / detonation. At this meeting, NRC. requested that TVA address additional questions. The responses to these questions and the documentation of our meeting presentations will be submitted by August 8,1980.

If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.

Very truly yours, TENNESSEE VALLEY AUTHORITY n

M /llfilalk &

d L. M. Mills, Manager d

Nuclear Regulation and Safety p

5

)

Enclosures IHIS. DOCUMENT CONTAINS zi. P00R QUAUTY PAGES 8003060 N

=

w.. n

ENCLOSURE 1 COMMENTS ON R&D ASSOCIATES REPORT SEQUOYAH CONTAINMENT ANALYSIS In the critique of the AMES analyses, R&D Associates (R&D) performed

~

separate analyses on the Sequoyah containment and compared their results with the results reported by AMES.

Our comments are made on R&D analyses as we do not have the Ames report.

Basically, in their letter report to Commissioner Gilinsky, R&D addressed the following.

1.

Location of the critical section or weakest portion of the vessel 2.

The effects of vertical and circumferential stiffening on maximum internal pressure 3.

The maxi =um internal pressure the containment can withstand based on developing:

a.

. Yield strength of the shell plate b.

Ultimate strength of the shell plate 4.

Comparison of their results with those reported by Ames We agree with R&D that the weakest section in the containment is the 1/2-inch thick shell plate between stiffeners at elevations 778 feet 6 inches and 788~ feet. We also agree with R&D's assessment of the con-tribution and effects of stiffening on the maximum internal pressure the containment can sustain In the report, R&D calculated critical internal y

pressures of 23.2 lb/in g based on the minimum yield strength of 8A 516 grade 60 material at 100 degrees Fahrenheit (using maxigum shear stress failure criteria) and a critical pressure of 26.8 lb/in g based on minimus-yield stress of the material and von Mises failure criterion. R&D also calculated thq critical internal pressure based on minimum ultimate ' stress of 43.5 lb/in'g (maximum shear stress criterion) and 50.3 lb/in~g (von Mises failure criterion).

2 TVA calculated critica4 internal pressures of 33.1 lb/in g (maximum shear stress) and 38.2 lb/in'g(von Mises) on exactly the same basis as R&D except that TVA used actual minimum yield stresses from the certifjed test reports I

for the' material at Sequoyah. = Comparable values based on the actual mini-mum ultimate stress from CTR's are 47.7 lb/in'g (maximum shear stress) and 54.9 (von Mises).

TVA in their communications with the Nuclear Regulatory Ccemission reported-the capacity of the Nuclear Regulatory Conmission reported the capacigy of Ethe Sequoyah containment as 33.1 lb/in'g (minimum yield) and

- 43.5 lb/in g (minimum ultimate). As can be seen, the critical internal i

' pressure at ultimate has approximately a 10 to 25 percent margin over our reported value' depending upon whether the maximum shear stress or von Mises failure criterion is used.

R&D based their recommendation of use of von 4

Mises criterion.

'1

(e In summary, we are in general. agreement with the approach and results given in the R&D report to Commissioner Gilinsky. We would only add

'that actual material ~ properties be used for determining the strength

- of the Sequoyah containment vessels.

R&D and TVA calculated strength differs only by the ratio of boiler. code yield stress to the minimum yield stress from actual te,sts of the' plate material.

One further note: twe do not-believe the two flat place analyses add'

' c.-'dence to R&D's analyses results of the cylindrical containment structures'and, consequently, we seriously doubt that further analyses and experimental verification of 10-foot by 4-foot panels will be helpful.

O O

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SUMMARY

-iVDROGEN STUDIED ASOUT NINE MONTHS sEQUOYAH CAN WITHSTAND SUSSTANTIAL AMOUNTS OF

-!YDROGEN ABOVE DESIGN BASIS

igb[iF! CANT MODIFICATIONS HAVE BEEi\\J-OR ARE BE!NG

.NCLUDED TO REDUCE POTENTIAL FOR DEGRADING

VENTS

.(g)

LIMITED RISK ASSESSMENT SHOWS SEGUOYAH COMPAR.

ABLE TO THE WASH 1400 STUDY REFERENCE PLANT 1

?ROPOSED CONCEPTS FOR RESOLUTION OF HYDROGEN ISSUE EVALUATED INTERIM D!STP.!SUTED IGNITION SYSTEM CHOSEN FOR IMPLEME?iTAT' IGM AT SEQU.OYAH. DEVELOPMENT V!ORK ON CONTROLLED IGNITION IS PROCEEDING FOR l

Fi JAL IMPLEMENTAT!ON AT SEQUOYAH. H ALO N

(

o ' P PRESSION IS ALSO BE!NG STUDIED.

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CAPABI;LITY OF THE SEQUOYAH CONTAINMENT MINIMUM CONTAINMENT PRESSURE CAPABILITY YlELD 7

~ ~

'33 PSIG ULTIM ATE -

42.5 PSIG

~

~

~

~

VOLUME - 1.2 X 106 FT3

i.,NTAINMENT CAPABILITY TO WITHSTAND HYDROGEN

~

. COMBUSTION ASS-UMPTIONS:

~.

- BURN IS INSTANTANEOUS AND COMPLETE '

~

.-- BURN IS ADI ABATIC

- - NO RADIATIVE TRANSFER RESU LT:

- SEQUOYAH CAN' WITHSTAND A HYDROGEN BURN O

EQUlVALENT TO APPROXIMATELY 25 PERCENT METAL-WATER REACTION (USING ULTIMATE

~

(3 STRENGTH OF MATERIALS) 9 t.

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.7 CONCEPTS STUDIED FOR M!T!GATiON CONTROL,.OR CnNw O. Na.m a, 4 m,iv'l u,v,r r,.,^ c'.,i CP cc c, s sR w_ t

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I INTED CONTAINMENT

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ESiiF5ATED DOSE IN LOW POPULATION ZONE IS IN

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POTENTIAL FOR UNNECESSARY BYPASS OF CONTA!NMENT i,

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CONCEPTS - ASSESSMENT (CUNT.)

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NOT'EFFECT VE FOR RAPID PRESSURE TRANSIENTS POTENTI AL FOR DEGRAD!NG SAFETY OF SECOND UNIT LARGE OPERAT!ONAL PENALTY FOR SECOND UNIT min!MiZED RADIATION RELEASE TO THE PUBLIC

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O CONCEPTS - ASSESSMENT (CONT.)

- CONTROL COMBUST 10N

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1.HIGH POThNTI AL FOR EFFECTIVENESS DURING MOST ACCIDENTS LEADING TO CLAD OXIDhT1ON 2.- NO EFFECT ON PLANT OPERATION 3.

TECHNICAL DEVELOPMENT REQUIRED 4.

REQUIRE LOCAL HYDROGEN MONI.TORING 5.

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-WE ARE IMPLEMENTING IMMEDIATELY Tile DESIGN AND INSTALLATION OF AN INTERIM DISTRIBUTED IGNITION SYSTEM (PilASE d) TO BE OPERAT.10NAL WIT!!IN TWO.T0 TilREE MONTilS.

WE ARE IMPLEMENTING IMMEDIATELY DEVELOPMENT WORK TO UPGRADE Tile INTERIM DISTRIBUTED IGNITION SYSIEh (PilASE~2) AS IMPROVED ASPEclS OF Tile SYSTEM CAN BE DEVELOPED.

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• 5 WE WILL COMPLETE A LONG-TERM STUDY AND DEVELOPMElli EFFECT FOR C0lllROLLED IGNITION SYSTEMS WillCil WILL LEAD 10 DACKFITTING Tile PilASE 1 & 2 _dslEMS, IF NEEDED.

(PilASE 3)

Tile LENGTil 0F. Tile ST.UDY..Sil0ULD BE APPROXIFA1ELY TWO -YEARS.

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SUMMARY

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HYDROGEN STUDIED ABOUT NINE MONTHS

- S'EQUOYAH CAf'.! WITHSTAND SUESTANTIAL AMOUNTS OF HYDROGEN ABOVE DESIGN BAS!S

~

S' N!FiCANT MODIFICATIONS HAVE BEEN OR ARE EEiNG (NCLUDED TO REDUCE POTENTIAL FOR DEGRADING pV u.-icn..}re

v c..

- L!M!TED RISK ASSESSMENT SHOWS SEGUOYAH COMPAR -

>ABLE TO THE WASH 1400 STUDY REFERENCE PLANT

- PROPOSED CONCEPTS FOR-RESOLUTION OF HYDROGEN

.lSSUE EVALUATED fis3.pn;P..]

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n wa 7-g CAPAS!LITY OF THE SEQUOYAH CONTAINMENT

- M(NiMUM CONTA!NMENT PRESSURE CAPABILITY Y! ELD -

33 PSIG

' ULTIMATE -

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- VOLUME - 1.2 X 106 FT,o

- CTJTAINMENT CAPAS!LITY TO WITHSTAND HYDROGEN COMBUSTION A

n CO ASSUMPTIONS:

s.

- BURN IS INSTANTANEOUS AND COMPLETE

- BURN IS ADIABATIC

- NC RADIATI's/E TRANSFER RESU LT:

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EQUIVALENT TO APPROXiMATELY 25 PERCENT VA-~

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