ML20126F615

Containment Leak Rate Testing Investigations, Monthly Progress Rept for Feb 1983.Incomplete Progress Rept for Mar 1983 Encl

ML20126F615
Person / Time
Site:	Browns Ferry, 05000000
Issue date:	02/28/1983
From:	Naus D OAK RIDGE NATIONAL LABORATORY
To:	Arndt G NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML20126E434	List: ML20126E431 ML20126E750 ML20126E798 ML20126E831 ML20126E994 ML20126F139 ML20126F221 ML20126F254 ML20126F479 ML20126F615 ML20126F644 ML20126F659 ML20126F946 ML20126F970 ML20126F977 ML20126G018 ML20126G093 ML20127A186 ML20127A289 ML20127A368 ML20127A386 ML20127A395 ML20127B180 ML20127B286
References
CON-FIN-B-0489, CON-FIN-B-489, FOIA-85-143 NUDOCS 8506170558
Download: ML20126F615 (3)

Text

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OAK RIDGE NATIONAL LABORATORY OPERATED SY UNION CARBIDE CORPORATION NUCLEAR DIVl510N POST OFFICE BOX Y f "_C, ( '

2 OAK RIDGE, TENNE 55EE 37830 g,M J . }, j l.m ' L February 28, 1983 3 , ,,

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• - , . e f ,' l Mr. Gunter Arndt '

Mechanical-Structural Engineering Branch Division of Engineering Technology h1 238 Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Gunter:

This letter summarizes our progress on the Containment Leak Rate Testing Investigations (Fin. No. B0489) Program for the month of February 1983.

Technical Highlights Browns Ferry was visited February 14-17, 1983 to observe the integrated leak rate test on Unit 2 containment. The following is an account from our per-spective of what occurred and can not be considered as typical since this is only the first of a series of tests which we plan to observe under this program. Local leak testing of the drywell head and drywell airlock were completed prior to the beginning of the Type A test. After successfully pressurizing the containment and allowing for containment stabilization, excessive leakage was noted. As this leakage showed no signs of abating, a search for possible leak sources was begun. During this time there was a reactor vessel low water indication in the control room. As a result, water was pumped into the vessel to the point that some of it overflowed and fell to the floor of the containment. Althought it turned out that the vessel water level had not been low, this produced a change in the humidity, pressure and temperature for the leak test. After correcting for the above, the test was then resumed, but an excessive leak rate was still observed. The leak was traced to a loose valve flange which was then tightened and the test resumed. The measured leak rate was then found to be acceptable.

An overview of available exemption requests has been completed. One area of continued requests involves the schedule and pressure for airlock testing. Another area concerns the local testing of main steam isolation valves in BWRs with respect to location (i.e. , between valves), pressure, and the pressure directions. The testing of BWR traversing in-core probe lines also was the subject of several' exemptions. Additonal

@lh - $6 =-l 0 8506170558 850325 eA gy PDR FOIA REYTBLAB5-143 PDR

4 Mr. Gunter Arndt 2 February 28, 1983 requests involved venting and draining lines, hydrostatic testing instead of pneunatic, leak rate extrapolation from low pressure to high, short duration testing, and Type B and C test schedules. Also, requests were made concerning the use of local leak test results to adjust Type A test re sult s .

An overview of the available licensee event reports has also been completed.

These events included: excessive penetration and valve leakage during Type B and C testing; time limits being exceeded for Type A, B, and C tests; and f ailure of a Type A test due to excessive leakage caused by holes inadvert-ently drilled through the containment sphere.

Expenditures Expenditures under this program during this fiscal year are shown below Oct. Nov. Dec. Jan. Feb.

Expenditure ($K) 7.2 8.9 7.8 8.9 8.3 Cumulative ($K)** 14.2 23.1 30.9 39.8 48.1

• Estimated -

• • Program Total Sincerely, fu D. J. Naus DJN:ege cc: J. R. Dougan l

l

OAK RIDGE ortnarro NATIONAL av LABORATORY I UNION CAR 81DE CORPORATION NUCLEAR DIVIS\0N 1 O

Po37 OFFICE 80X Y OAK RIDGE, TENNESSEE 37800 I April 4, 1983 Mr. Gunter Arndt Mechanical-Structural Engineering Branch Division of Engineering Technology NL 238 Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Vashington, DC 20555

Dear Gunter:

! This letter summarizes our progress on the Containment Leak Rate Testing Investigations (Fin. No. B0489) Program for the month of March 1983 .

Technical Highlights Meeting on Reactor Operating Experience Scottsdale, Arizona.

to be held Augusta p 1-3, 1983, in and provides a brief background discussion of:The paper is entitled "The Issue of CIL the present duration requirements, several proposed concepts for deterthe reasons for mining the duration of CILRTs, and several of the concerns raised by the move to redefine the duration.

! has been received from Z. Reytblatt.A report entitled "A Critique of Containme .

l ment of the subcontract agreement between OPNL and Reytblatt.This The report report represen identifies potential sources of error in leak rate testing and illus t rates j the significance of these errors through examples.

a discussion of the existing industry standard (ANSI /ANS-56.8-1981.The The report also contain portion of the contract remaining for improving ANSI /ANS-56.8-1981 to be fulfilled concerns recommen)dations ing weighting factors for the sensors.and the procedures for placing and determin -

This information is expected to be Leakage Testing Requirements. contained in a forthcoming report by Reytblatt entitled

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