ML20079L343

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Fifth Interim Deficiency Rept Re Analysis for Loss of Feedwater Event.Initially Reported on 810316.Preliminary Review of B&W Rept Indicates FSAR Analysis Conservative.Next Rept Expected by 830624.Also Reported Under Part 21
ML20079L343
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 02/16/1983
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8302230234
Download: ML20079L343 (2)


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TENNESSEE VALLEY AUTHORITY -

- CHATTANOOGA. TENNESSEE 374o1

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400 Chestnut Street Tower.II February 16,.1983- D n

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BLRD-50-438/81-24 ,; c BLRD-50-439/81-26 - -

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U.S. Nuclear' Regulatory Commission. E: ..,

. Region II -

Attn: Mr. James P. O'Reilly, Regional Administrator #

'101 Marietta Street,-Suite 3100 #

Atlanta, Georgia- 30303 ~

Dear Mr. O'Reilly:

^

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - ANALYSIS FOR LOSS OF FEEDWATER EVENT - BLRD-50-438/81-24, BLRD-50-439/81 FIFTH INTERIM REPORTL The subject deficiency was initially reported to NRC-OIE Inspector J. Crlenjak on March 16', 1981 in accordance with 10.CFR 50.55(e) as NCR BLN NEB 8102. This was followed by our interim reports dated April-13 and.

November'16, 1981 and March 3, and October 5, 1982. Enclosed is our.fifth.

interim report. We expect to submit our next report by June 24, 1983 . 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, TENNESSEE VALLEY AUTHORITY ~

L. M. Mills, Manager

j. Nuclear Licensing

{ Enclosure

cc: Mr. Richard C. DeYoung, Director.(Enclosure) i- Office of Inspection and Enforcement
U.S. Nuclear Regulatory Commission Washington, D.C. 20555

! Mr. James McFarland (Enclosure)

L Senior Project Manager l' Babcock & Wilcox Company l P.O. Box 1260

Lynchburg, Virginia '24505 i

f i OFFICIAI. COPY u

! 8302230234 830216

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DR ADOCK 05

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An Equal opportunity Employer

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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 ANALYSIS FOR LOSS OF FEEDWATER EVENT NCR BLN NEB 8102 BLRD-50-438/81-24, BLRD-50-439/81-26 10 CFR 50.55(e)

FIFTH INTERIM REPORT Description of Condition The Bellefonte Final Safety Analysic 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 (P1W)

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 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. .

I Interim Progress TVA recently received B&W's final analytical report for^ the loss of feedwater event and has begun a technical review.of the subject report.

t The report should show if the FSAR analysis is conservative. A preliminary

! review of the report indicates that the FSAR analysis is conservative and that therefore, no problem exists.

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