ML20034B672
| ML20034B672 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/20/1990 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| TAC-66753, TAC-66754, NUDOCS 9004300173 | |
| Download: ML20034B672 (4) | |
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i Doc kets Nos. 50-413 and 50 414 Mr. H. B. Tucker, Vice President Nuclear Production Departnent Du ke Power Conpary 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE RUPTURE OPERATOR ACTIONS. CATAWABA NUCLEAR STATION, UNITS 1 AND 2 (TACS 66753/66754)
By letter dated December 7,1987, and supplenented Decenber 29,1987, March 29, May 4 and 18, Jure 16, July 1. August 8 and 24, and Decenber 15, 1988, October 23, and Decenber 8,1989, you submitted tre steam generator tube rupture (SGTR) accident analysis for Catawba Nuclear Station in response to License Conditions 2.C.(16) and (10) for Units 1 and 2, respectively.
The NRC staff has reviewed your submittals and finds that your response to the enclosed request for additional information is needed by May 31, 1990, in order that the review may be con please contact ne at (301)pleted in a tinely nenner. If you have questions, 492-1496.
The reporting and/or recordkeeping requirenents contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L. 96 511.
Sincerely, j3I Kahtan N. Jabbour, Project Manager Project Directorate II-3 Division of Reactor Projects. I/II Office of Nuclear Reactor Regulation Enclo sure:
As stated l
l cc w/ enclosure:
l See next page DISTRIBUTION.
Docket File S. Va rg a OGC NRC & Local PDRs G. Lainas E. Jordan PDII.3 r/f R. Ingram ACRS(10)
Catawba Plant File K. Jabbour OFC
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DATE
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- 04/M/90
- 04/to/90 OFFICIAL ECORD COPY O
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A.V. Carr, Esq.
North Carolina Electric Membership Duke Power Company Corp.
4?2 South Church Stroet 3400 Sumner Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 Raleigh, North Carolina 27611 J. Michael McGarry, 111. Esq.
Bishop, Cook. Purcell and Reynolds Saluda River Electric Cooperative, l
1400 L Street, N.W.
Inc.
Washington, D. C.
20005 P.O. Box 929 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident inspector i
Suite 600 Route 2. Box 179N 3100 Smoketree Ct.
York, South Carolina 29745 P.O. Box 29513 Raleigh, North Carolina 27626 0513 Regional Administrator, Region 11 U.S. Nuclear Regulatory Commission Ms. S. S. Kilborn 101 Marietta Street, NW, Suite 2900 Area Manager, Mid South Area Atlanta, Georgia 30323 ESSD Projects Westinghouse Electric Corp.
Mr. Heyward G. Shealy, Chief MitC West Tower - Bay 239 Bureau of Radiological Health P.O. Box 355 South Carolina Department of Health Pittsburgh, Pennsylvariin 15230 and Environmental Control 2600 Bull Street County Manager of Yori County Columbia, South Carolina 29201 i
York County Courthoust l
York, South Carolina 29745 Ms. Karen E. Long Assistant Attorney General nichard P. Wilson, Est.
N.C. Department of Justice Assistant Attorney Geteral P.O. Box 629 S.C. Attorney General's Office Raleigh, North Carolina 27602 P.O. Box 11549 l
Columbia, South Caroltna 29211 Mr. Robert G. Morgan i
Nuclear Production Department Piedmont Municipal Power Agency Duke Power Company 121 Village Drive P.O. Box 33189 Greer, South Carolina 29651 Charlotte, North Carolina 28241 Mr. Alan R. Herdt, Chief Project Branch #3 U.S. Nuclear Regulatory Commission 101 Marietta Street,I!W, Suite 2900 Atlanta, Georgia 30323 i
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l ENCLOSURE REQUEST FOR ADDITIONAL INFORMAT101.
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l The staff has reviewed the licensee's submittals regarding operator actions and times & ring a steam generator tube ruptum (SGTR).
The licensee's letter l
of Decenber 7,1987, indicated that, demonstration runs will be perfomed to show that the SGTR event can be mitigated within a period of time conpatible with overfill prevention, using design basis assunptions regarding available
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j equipnent, and to denonstrate that the operator action times assumed in the analysis are realistic.
The staff finds that the information subsequently l
provided is inmnplete.
l The times reported in Table 15.6.3-1 of the August 24, 1988, submittal do not appear to be operator times resulting from denonstration runs.
The recovery actions listed in the August 8,1988, submittal do not include response times for the following:
cooldown, depressurization, operator action time to initiate safety injection (SI) temination, and $1 termination and pressure equa liz ation.
The submittal does not specify the operator response time for identifying and isolating the ruptured generator prior to its narrow range level exceeding 33 percent.
Further, the response times reported in the submitt61 do not provide sufficient assurance that they represent most operators arrently at the plant.
Lastly, no total response time is reported i
1 for recovering from the SGTR event.
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The licensee is requested to provide additional information regarding operator response times & ring a SGTR at the Catawaba Nuclear Station, Units 1 and 2.
Specifically, the licensee is requested to provide the response times for the following recovery actions, identified in Table 2.3-1 (page 2-24) of the l
Westinghouse (htners Group WCAP 10698:
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Identify and isolate ruptured SG.
i Operator action time to initiate cooldwn.
t Cooldown.
Operator action time to initiate depressurization.
Dep ressuriz ation.
Operator action time to initiate SI termination j
SI termination and pressure equalization.
Assuming a sinulated as-close-to-design-basis-as-possible scenario, the licensee should provide operator response time (1) demonstrating that the SGTR event can be mitigated within a period of time coppatible with overfill i
prevention and (2) assuring that response times are representative of most, if not all, the operators currently at the plant.
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