ML20064N457

Responds to Open Items Identified in NRC 820723 Safety Evaluation Re Containment Leakage Testing Program.Resolution of Areas of Containment Personnel Access Door Seal & Isolation Valve Testing to Be Provided by 821101

ML20064N457
Person / Time
Site:	Fort Calhoun
Issue date:	09/03/1982
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	Clark R Office of Nuclear Reactor Regulation
References
LIC-82-318, TAC-8910, NUDOCS 8209080365
Download: ML20064N457 (2)

Text

9 Omaha Public Power District 1623 HARNEY a OMAHA. NEBRA5MA 68102 e TELEPHONE S36 4000 AREA CODE 402 September 3, 1982 LIC-82-318 Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear fir. Clark:

10 CFR 50, Appendix J Containment Leakage Testing Program The Commission's letter to the Omaha Public Power District, dated July 23, 1982, transmitted the Commission's safety evaluation report (SER) regarding the containment leakage testing program at the Fort Calhoun Station. The SER identified three open items that are to be resolved prior to issuance of the District's license amendment. The District's response to these open items is provided below.

The first open item concerns the leak testing of the containment personnel access door seals and, specifically, the methodology for extrapolating the leakage results determined at the 5 psig test pressure to a leakage rate equivalent to a test at 60 psig. Appendix A to the l Commission's letter dated July 23, 1982 details an extrapolation method-ology, different from that proposed by the District, that is acceptable to the Commission for this purpose. The District has reviewed the Appendix A methodology and has determined that in order to make an l accurate assessment of the acceptability of the criteria for the Fort Calhoun Station, further detailed analysis is required. Additionally, t the District has requested copies of three of the references identified

! in Appendix A from our Project Manager to supplement the-District's review and analysis of this methodology. Pending further review of Appendix A and receipt of the requested information, the District expects to provide the Commission with a response to this item by November 1, 1982.

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Mr. Robert A. Clark LIC-82-318 Page Two The other two open items concern Type C testing of the isolation valves associated with containment mechanical penetrations M-3 and M-44.

The isolation valves associated with penetration M-3, the charging pump discharge line, will not be tested in accordance with Appendix J, Type C testing, as justified in the District's letter to the Commission dated May 15, 1980 and the current Technical Specifications. These valves and associated piping are part of a closed system which is connected to the reactor coolant system and the valves do not automatically close upon receipt of an accident signal. However, the principal justification for not leak testing the M-3 isolation valves is the fact that the pressure seen by these valves in the direction of flow toward the contaiGnent building will always be much greater than the maximum design basis accident-(i.e., LOCA) pressure in containment of approximately 60 psig.

Since all charging pumps are automatically started upon receipt of a Safety Injection Actuation Signal (SIAS) and produce a normal discharge pressure of approximately 2100 psig in the subject line, the leakage of contaminated containment air through this path is precluded.

Concerning the testing of the isolation valves associated with penetration M-44, the " Pressurizer Dead Weight Tester," the District is presently evaluating the possibility of capping this 1/8" instrument line inside the containment. The District no longer utilizes this instrument line, thus capping the line would preclude the necessity of leak testing the penetration isolation valves. The results of this evaluation and the schedule for completing the work, if applicable, will be provided to the Commission with the District's response to the first open item discussed above.

Sincerely, QL}Q)

W. C. Jones Divisi'on Manager Production Operations WCJ/TLP:jmm cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

l Washington, D.C. 20036 l

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