ML20040E532

Third Interim Deficiency Rept Re Reactor Core Isolation Cooling Steam Line Break,Initially Reported 810630.Util Still Investigating GE Proposed Solution to Add 1-inch Bypass to Limit Downstream Flow in Event of Rupture

ML20040E532
Person / Time
Site:	05000000, Hartsville, Phipps Bend
Issue date:	01/27/1982
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8202050048
Download: ML20040E532 (1)

Text

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TENNESSEE VALLEY AUTHORjTY WNHC REGi3N CH ATTANOOGA TENNESSEE 374013gg 7g ,

400 Chestnut Street Tower II January 27,1992[F p l A 8. $6 HTRD-50-518/81-15, -519/81-11,

-520/81-13, -521/81-11 PBRD-50-553/81-16, -554/81-09 77 Jff'I

• 9 Mr. James P. O'Reilly, Regional Administrator 9- M .S C D U.S. Nuclear Regulatory Commission rh Region II - Suite 3100 --d rn4 E2h 'I--

101 Marietta Street [))'T Atlanta, Georgia 30303 A

• ,Q

Dear Mr. O'Reilly:

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HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS - REPORTABLE DEFICIENCY -

RCIC STEAM LINE BREAK - HTRD-50-518/81-15, -519/81-11, -520/81-13,

-521/81-11, PBRD-50-553/81-16, -554/81-09 The subject deficiencies were initially reported to NRC-0IE, Region II, Inspector F. S. Cantrell on June 30, 1981 as NCR's HTA NEB 81-03, HTB NEB 81-04, and PBN NEB 81-02. The first and second interim reports were submitted on July 31 and September 30, 1981. In compliance with paragraph 50.55(e) of 10 CFR Part 50, this letter constitutes the third interim report on the subject deficiencies.

TVA is still investigating GE's proposed solution to this deficiency which consists of the addition of a normally closed valve with a one-inch bypass located just outside the steam tunnel in the RCIC pipe chase. The one-inch bypass will limit downstream flow in the event of a rupture.

TVA has requested that GE provide clarification of certain items in their proposal. Since the proposal does not address a break during RCIC operation, TVA is requesting GE to verify that no credit is taken for RCIC operation during normal plant operations. We believe more information is needed from GE concerning the hot standby mode and simultaneous RCIC operation. We anticipate transmitting an additional report on or before May 18, 1982. We consider 10 CFR Part 21 applicable to this nonconformance. If you have any questions, please call Jim Domer at FTS 858-2725.

Very truly yours, TENNESSEE VALLEY AUTHORITY A '

. V1.

L. M. Mills, Mana er Nuclear Regulation and Safety

, cc: Mr. R. C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 8202050048 820127 PDR ADOCK 05000518 Ob'FTCf AT. CbM2' S PDR An Equal Opportunity Employer

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