ML20049J557
| ML20049J557 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 03/03/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-82 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8203180358 | |
| Download: ML20049J557 (2) | |
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U.S. Nuclear Regulatory Commission 8
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. Region II' Attn:
Mr. James P. O'Reilly, Regional Administra1g aggg27/cgA
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Dear Mr. O'Reilly:
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A BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - ANALYSIS -FOR LCSS OF FEEDWATER EVENT '
BLRD-50-438/81-24, BLRD-50-439/81 THIRD INTERIM REPORT The s' abject deficiency was initially reported to NRC-0IE Inspector J. Cr15njak on March 16, 1981, in accordance with 10 CFR 50.55(e)'a's NCR BLN NEB 8102.
This was followed by our interim reports dated April 13'.and November 16, 1981.-
Enclosed is our third interim report. We expect to.submitIour.next report by October 7, 1982.
We consider 10 CFR Part 21 applicable to this deficiency.
If you have any questions concerning this matter, please get in touch with-R. H. Shell at FTS 858-2688.
'Very truly yours,
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L. M. Mills, Manager Nuclear Regulation and Safety-- %
I Enclosure cc : -
Mr.~ Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. James McFarland (Enclosure)
Senior Project Manager Babcock & Wilcox Company P.O. Box 1260 Lynchburg, Virginia 24505 4
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An Equal Opportunity Employer
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,n' ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 ANALYSIS /OR LOSS OF FEEDWATER EVENT BLRD-50-438/81-24, BLRD-50-439/81-26
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10 CFR 50.55(e)
THIRD INTERIM REPORT Description of Condition The Bellefonte Final Safety Analysis Report (FSAR) analysis for the loss of normal feedwater event (section 15.2.7) may not be conservative. The Bellefonte FSAR analysis predicts that the ASME Section III Code limits for overpressurization of the Reactor Coolant System will not be exceeded following a loss of normal feedwater. The Babcock and Wilcox (B&W)
Company has performed a more recent analysis for the Washington Public Power Supply System (WPPSS) which predicts that the ASME Code limits for overpressurization will be exceeded following a loss of feedwater (LOFW).
A B&W representative stated, during a March 12, 1981 meeting of the B&W Nonoperating Owners Group, that B&W analysts had reason to suspect a nonconservatism in the B&W computer codes when the Bellefonte analyses were being performed. B&W has several computer codes, including " POWER TRAIN,"
"CADDS," and " TRAP 2," which can be used to predict Reactor Coolant System pressure following a decrease in heat removal by the secondary system. The computer code "CADDS" was used by B&W for the Bellefonte loss of feedwater analyses. Apparently, "CADDS" predicts a lower Reactor Coolant System pressure than one or more of the other computer codes available to B&W.
TVA notes that the NRC has also raised a concern about the adequacy of "CADDS" in NUREG-0560.
This nonconformance report (NCR) was deemed reportable because if a nonconservative computer analysis is used a potential exists for r
overpressurization of the Reactor Coolant System. This NCR also indicates a possible failure of B&W's Quality Assurance program to resolve a known discrepancy in the analyses used to calculate Reactor Coolant System pressure following an LOFW.
Interim Progress TVA is continuing to work with B&W toward resolution of the subject deficiency. This resolution 'is dependent on an LOFW analysis to be performed by B&W. This analysis will show that either the FSAR is correct as is or the FSAR is incorrect and must be revised. The Bellefonte FSAR analysis is unique to B&W, and therefore no other TVA nuclear plants are affected.
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