ML20205P399

Forwards Request for Addl Info Re Amends on Radiological Aspects of Operation at Reduced Feedwater Temperature & Operation with Replacement SG for Plant,Units 1 & 2

ML20205P399
Person / Time
Site:	South Texas
Issue date:	04/14/1999
From:	Alexion T NRC (Affiliation Not Assigned)
To:	Cottle W HOUSTON LIGHTING & POWER CO.
References
TAC-MA3820, TAC-MA3821, NUDOCS 9904200163
Download: ML20205P399 (4)

Text

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l Mr. William T. Cottle April 14, 1999 President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX '/7463

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PROPOSED AMENDMENTS ON RADIOLOGICAL ASPECTS OF OPERATION AT REDUCED FEEDWATER TEMPERATURE AND OF OPERATION WITH REPLACEMENT STEAM GENERATORS, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP)

(TAC NOS. MA3820 AND MA3821)

Dear Mr. Cottle:

The Nuclear Regulatory Commission staff is reviewing STP Nuclear Operating Company's September 30,1998, amendment application associated with the Replacement Steam Generator Project.

On the basis of its review, the stav has determined that additional information is needed as discussed in the enclosed request for additional information (RAl). This request was discussed with Mr. Mark VanNoy of your staff on April 8,1999, and a mutually agreeable response of within 30 days from the date of this letter was established. The staff appreciates the efforts expended with respect to this matter.

Sincerely, ORIGIllAL SIGNED BY:  !

Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation.

Docket Nos. 50-498 and 50-499

Enclosure:

/ stated cc w/ encl: See next page '

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• • • • • 1. April 14, 1999

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1 Mr. William T. Cottle President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric l

Generating Station i P. O. Box 289 I l Wadsworth,TX 77483

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PROPOSED AMENDMENTS ON RADIOLOGICAL ASPECTS OF OPERATION AT REDUCED FEEDWATER l TEMPERATURE AND OF OPERATION WITH REPLACEMENT STEAM l

GENERATORS, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP)

(TAC NOS. MA3820 AND MA3821)

I

Dear Mr. Cottle:

The Nuclear Regulatory Commission staff is reviewing STP Nuclear Operating Company's September 30,1998, amendment application associated with the Replacement Steam Generator Project.

On the basis of its review, the staff has determined that additional information is needed as discussed in the enclosed request for additional information (RAI). This request was discussed with Mr. Mark VanNoy of your staff on April 8,1999, and a mutually agreeable response of within 30 days from the date of this letter was established. The staff appreciates the efforts expended with respect to this matter.

, Sincerely, 4f}M28 *I k  ;

i Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosure:

As stated cc w/ encl: See next page -

i _ _ _ ~

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I Mr. William T. Cottle <

STP Nuclear Operating Company South Texas, Units 1 & 2 cc:

Mr. Cornelius F. O'Keefe Jack R. Newman, Esq.

Senior Resident inspector Morgan, Lewis & Bocklus U.S. Nuclear Regulatory Commission 1800 M Street, N.W.

P. O. Box 910 Washington, DC 20036-5869 Bay City, TX 77414 Mr. T. H. Cloninger Vice President A Ramirez/C. M. Canady Engineering & Technical Services i Cityof Austin STP Nuclear Operating Company Electric Utility Department P. O. Box 289 l 721 Barton Springs Road Wadsworth, TX 77483 )

Austin,TX 78704 '

Office of the Governor l Mr. M. T. Hardt ATTN: John Howard, Director I Mr. W. C. Gunst Environmental and Natural i City Public Service Board Resources Policy P. O. Box 1771 P. O. Box 12428 j San Antonio, TX 78296 Austin,TX 78711  ;

l Mr. G. E. Vaughn/C. A. Johnson Jon C. Wood  !

Central Power and Light Company Matthews & Branscomb j P. O. Box 289 One Alamo Center '

Mail Code: N5012 106 S. St. Mary's Street, Suite 700 Wadsworth,TX 74483 San Antonio, TX 78205-3692 INPO Arthur C. Tate, Director Records Center Division of Compliance & Inspection 700 Galleria Parkway Bureau of Radiation Control Atlanta, GA 30339.3064 Texas Department of Health '

1100 West 49th Street Regional Administrator, Region IV Austin,TX 78756 U.S. Nuclear Regulatory Commission i 611 Ryan Plaza Drive, Suite 400 Jim Calloway Arlington,TX 76011 Public Utility Commission of Texas Electric Industry Analysis D. G. Tees /R. L Balcom P. O. Box 13326 Houston Lighting & Power Co. Austin, TX 78711-3326 P. O. Box 1700 l

Houston,TX 77251 Judge, Matagorda County Matagorda County Courthouse 1700 Seventh Street Bay City, TX 77414

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Reauest for Additionalinformation Radiolooical Asoects of Ooeration at Reduced Feedwater Temoerature and of Ooeration with Reolacement Steamjenerators South Texas Project. Units 1 and 2

1. Why do the consequences of a locked rotor and rod ejection accident result in an increase only in the whole body and skin doses and not the thyroid?

2. Explain what the *MSIV [ main steam isol %n valve] above seat drains" leak rate is?

3. Why wasn't an analysis performed for the pre-existing spike case for the voltage-based analysis? j

4. Why was the duration of the accident for the revised main steam line break (MSLB) analysis 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and that for the voltage-based repair criteria 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />?

5. For the steam generator tube rupture (SGTR) accident, was an analysis performed of the impact of the reduced feedwater temperature on steam generator overfill, flashing fraction, and break flow?

6. For the voltage-based MSLB analysis, what is the accident-induced primary-to-secondary leakage value?

7. Have the control room X/ O values in Table 5.21 included the occupancy factors?

8. Does this plant have extended burnup fuel?

9. Explain why it takes only 862 seconds to cool the plant down via the secondary side in the event of an SGTR7 1

10. What is the basis for halting the iodine spike at 11676 Ci for the SGTR accident-initiated spike case?

11. Please provide a Table (s) with break flow and flashing fraction as a function of time for the SGTR.

ENCLOSURE

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