ML20236U749
| ML20236U749 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/27/1998 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | Cottle W HOUSTON LIGHTING & POWER CO. |
| References | |
| TAC-MA0350, TAC-MA0351, TAC-MA350, TAC-MA351, NUDOCS 9807300413 | |
| Download: ML20236U749 (4) | |
Text
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.,4 Mr. William T. Cottia July 27, 1998 Prasid3nt and Chitf Exscutiva Officer STP Nuc!aar Operating Company South Texas Project Electric l
Generating Station P O. Box 289 Wadsworth, TX 77483
SUBJECT:
REQUEST FOR ADDITIONAL !NFORMATION ON ALTERNATE OPERATION WITH REDUCED MEASURED REACTOR COOLANT SYSTEM FLOW, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP) (TAC NOS. MA0350 AND MA0351)
Dear Mr. Cottle:
The Nuclear Regulatory Commission (NRC) staff is reviewing STP Nuclear Operating Company's (STPNOC's) December 31,1997, application for a license ameridment to revise Technical Specification 2.1 (Safety Limits),2.2 (Limiting Safety System Settings), and 3/4.2.5 (Departure
- from Nucleate Boiling Parameters) by including altemate operating criteria to allow continued plant operation with a reduced measured reactor coolant system flow rate, if necessary.
Based on its review, the staff has determined that additional information is needed, as discussed in the enclosure.
l Sincerely, ORIGINAL SIGNED BY:
i Thomas W. Alexion, Project Manager Project Directorate IV-1 i
Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation j
Docket Nos. 50-498 and 50-499.
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Enclosure:
Request for Additional Information 3
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July 27, 1998 Mr. William T. Cottle President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth,TX 77483
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATE OPERATION WITH REDUCED MEASURED REACTOR COOLANT SYSTEM FLOW, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP) (TAC NOS. MA0350 AND MA0351)
Dear Mr. Cottle:
The Nuclear Regulatory Commission (NRC) staff is reviewing STP Nuclear Operating Company's (STPNOC's) December 31,1997, application for a license amendment to revise Technical Specification 2.1 (Safety Limits),2.2 (Limiting Safety Gystem Settings), and 3/4.2.5 (Departure from Nucleate Boiling Parameters) by including attemate operating criteria to allow continued plant operation with a reduced mecsured reactor coolant system flow rate, if necessary.
Based on its review, the staff has determined that additionalinformation is needed, as discussed in the enclosure.
Sincerely, i
SiEV
^ OV L
Thomas W. Alexion, Project Manager Project Directorate (V-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Request for Additionalinformation cc w/ encl: See next page i
L-___
Mr. William T. Cottle STP Nuclear Operating Company South Texas, Units 1 & 2 cc:
Mr. David P. Loveless Jack R. Newman, Esq.
Senior Resident inspector Morgan, Lewis & Bockius U.S. Nuclear Regulatory Commission 1800 M Street, N.W.
P. O. Box 910 Washington, DC 20036-5869 Bay City, TX 77414 Mr. Lawrence E. Martin A. Ramirez/C. M. Canady Vice President, Nuc. Assurance & Licensing City of Austin STP Nuclear Operating Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth, TX 77483 Austin, TX 78704 Office of the Govemor Mr. M. T. Hardt ATTN: John Howard, Director I
Mr. W. C. Gunst Environmental and Natural City Public Service Board Resources Policy P. O. Box 1771 P. O. Box 12428 San Antonio, TX 78296 Austin,TX 78711 Mr. G. E. Vaughn!C. A. Johnson Jon C. Wood Central Power and Light Company Matthews & Branscomb 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 R6gional Administrator, Region IV Austin, TX 78756 U.S. Nucicar Regulatory Commission 611 Rysn 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 Houston,TX 77251 Judge, Matagorda County Matagorda County Cour1 house 1700 Seventh Street "ay City, TX 77414 Ic
. ~
l REQUEST FOR ADDITIONAL INFORMATION 1.
Regarding the reanalysis for the new conditions:
What is the limiting departure from nucleats boiling ratio (DNBR) accident and a.
what is the DNBR value? Whst is the required DNBR value? What codes were used for the DNBR analyses, and what correlation was used? If a sensitivity analysis was used please explain the parameters used as requested in Question 2 of the April 8,1998, request for additionalinformation and justify.
b.
You indicate in Table 4 of Reference 1 that in place of a recalculation, sensitivity l
studies were used for the large and small break loss-of-coolant accident (LOCA) analysis and that there were minor changes that are bounded by the current analys!s. Please explain the use of the sensitivity studies and justify the use of i
the paremeters. As requested in Questions 2 and 3 of the April 8,1998, request for additionalinformation, please provide the ney peak clad temperature for the i
large and small break LOCAs if possible, or the bounding value. Also, provide the j
peak clad temperature limit value. Discuss how the sensitivity study was I
performed, c.
What is the limiting pressure event and what is the pressure for this event? What i
is the acceptance value of pressure for this event (usually 110% of reactor coolant system design pressure)? What codes were used?
I d.
Where esdes were used, were all the analyses made with approved codes?
2.
In Reference 2, there is a discussion on steam generator tube rupture (SGTR) evaluation.
However, in Reference 1 you have not tabulated information on your method of evaluation on SGTR as you have for other Updated Final Safety Analysis Report (UFSAR)
LOCA events in Table 4. Please supply this information for the appropriate table.
3.
Provide a brief description of the bounding analyses that is discussed in Section 2.6 of Reference 1. Wh.1t are the maximum stresses and fatigue usage factors from the bounding analyses (mentioned in Reference 1, Section 2.6), including the Code allowable limits at criticallocations for the components on page 8 of 12 of Reference 2? Correlate the maximum stresses and fatigue usage factors from the bounding analyses to the bounding conditions identified on Table of Reference 1.
References:
1.
Letter from T.H. Cloninger, STP Nuclear Operating Company, to U.S. Nuclear F.egulatory Commission, dated June 30,1998 (proprietary se '1on-proprietary versions).
2.
Letter from T.H. Cloninger, STP Nuclear Operating Company, to U.S. Nuclear Regulatory Commission, dated December 31,1997.
ENCLOSURE l
.