ML20034A324
| ML20034A324 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/13/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9004230052 | |
| Download: ML20034A324 (5) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOG A. TENNESSEE 37401 SN 1578 Lookout Place APR 131990 U.S. Nuclear Regulatory Commission ATIN: 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) UNITS 1 AND 2 - TECHNICAL SPECIFICATION (TS)
CHANGE 89 ADDITIONAL INFORMATION
Reference:
TVA letter to NRC dated January 12, 1990, "Sequoyah Nuclear Plant (SQN) - Technical Specification (TS) Change 89 Vantage 5 Hybrid (V5H) Fuel Upgrade" A telephone conference call was held on April 4, 1990, to allow TVA to respond to NRC questions concerning the referenced TS change request.
During that telephone call, NRC staff requested that TVA docket the enclosed information concerning fuel failure criteria used for the locked rotor' analysis performed to support the use of V5H fuel at SQN.
No commitments are contained in this submittal.
Please direct questions concerning this issue to Bruce S. Schofield at (615) 843-6172.
Very truly yours, TENNESSEE VALLEY AUTHORITY-O
' %. < 71 E. G. H& lace, Manag r Nuclear Licensing and Regulatory Affairs Enclosure cc:
See page 2 Q4230032 yon 433 p
ADOCK 05000327 PDC pf0
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An Equal opportunity Employer I
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~2-U.S. Nuclear Regulatory Commission APR 131990 cc (Enclosure):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector i
Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Mr. B. A. H11 son, Assistant Director for Inspection Programs TVA Projects Division l
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l
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ENCLOSURE ~
TENNESSEE VALLEY AUTHORITY-
- SEQUOYAH NUCLEAR PLANT-(SQN)-
RESPONSE TO NRC' QUESTION ON~THE SQN
.. VANTAGE $H PLANT SAFETY EVALUATION-t.
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04/13/1990 12:35 SON SITE DIRNSITE LIC 615 B43 7129 P,C2 g3g 9 9 M fod 4
Westinghouse CommercialNuclear am ni Electric Corporation Fuel Division Pmsbesh Pe**rtes 16730 212 April 5, 1990 901V*MP0035 Mr. T. A.
, Marager Ob ruel ard Utilisation
/MS*d Tennesses Valley Autthority 1101 Market street df
b IR 6N 60A Omt.M. ey, Ttenesses 37401 Dear Mr. Meyst T1INNIISSEE VAUM AUIh0RITY SEQUDDN AND NNITS 3AR NUCfJinR PONI!R PIANIS RE85GBE TO NRC QUSRTON CN THit 5BOUDDH VANIME !Bt PIANT BhPEIY EVAURTZtaf Listad below is our response to NRC Condition 9 w.. caning the Icdoed Rotor analysis for the sequoyah VANIME SN Upgrade.
Nac annaition With regard to the Ros punp shaft seisure accident,.the fuel failure criterion should be the 95/95 DUR limit. 'Iha mechanistic method mentioned in McAP-10444 is not acomptable.
Baspcmme The mechanistic method for quantifying foal failure was not used for the McB puup ahatt salture (lodkad rotor) =TiA=1t performed for the sequoyah Naclamr Unita 1 and 2 VANIME 5H fuel transition.
Westdaghouse satse two separate and distinct analyses for the icdood rotor event.
The first analysis, using the IDr!RAN and FACTRAN ondas, was pertermed to determine the peak PCS trossure, the clad tanperatureg and the amount of airc-$ater reaction. A conservatite
==~ tion in the clad t.weture oniculation is that DNB is asstaned to ocx*2r at the beginning of the trarmient. The results of this analysis are presented in Section 51 of Referenos 1 and were net used in any way to determine the numker of rods-in-INB. 'Jha limit.ing critaria for the peak Clad Lgetutt (PCT) la described in neference 2.
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04/13/1990- -12:36-SON SITE DIFbSITE LIC ~
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- 901V*<r 0035 A secend analysis, using the 10PTRAN, FACIRAN etd DUNC ocuputer _
ocdes, was also performed for VANDGE SH fuel transition to dotarains the number of rods Wildi emperience WB during the lodkod rotor t
accident. Any rods whis violated the 95/95 DGR limit were assutand to fall. 'Ihe resulta showed that less than-10% of the rods were predicted to be below the 95/95 DGR limit. To reitersta, the mamanistic apptoads Mantified in Anference 9 (NUREFC562) of:
NChP-11157 was nob used. '!he cenclusions in PSAR 8ection 15.4.4.2 -
rumm h valid.
Referennes 1.
Plant safety Evaluation for Sequoyah Nuclear Plant thits 1-ard 2 -
VAN BGE SH Fuel t we, November, 1989 and Revisien 1, December 1989.
2.
NS400-89-3466, "Dee of 2700 degF PCT Qc.ii, Idmit in i
Non-IOCA Accidents," Lee fran W. J. Johnson (Nestirughouse) to i
Mr. Debort C. Jones (NRC), Octclxa* 23,-1989.
i Should you have ary questions regarding this subject, please do ntit I
hesitate to call or write.
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N. R. Natcalf.
Proja:st Engineer CHFD Projects NRN mid 1
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I. R. Hilliamson i
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