ML20207N600

Summary of 840905 Meeting at NRC Region III Ofc Re Inservice Insp of HPI Sys

ML20207N600
Person / Time
Site:	Davis Besse
Issue date:	09/10/1984
From:	Cobb H H.A.F.A. INTERNATIONAL, INC.
To:	Daft C H.A.F.A. INTERNATIONAL, INC.
References
TAC-55824, NUDOCS 8701140311
Download: ML20207N600 (3)

Text

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H.A.F.A. INTERN ATION AL, INC.

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7545 Central Industrial Drive Riviera Beach, riorida 33404 (305) 848-5252 MEMO September 84 HIJ4 TO:

C. T. Daft - QA Director y

FROM:

H. Cobb - H.A.F.A. International, Inc.

SUBJECT:

Meeting at NRC Region III to discuss 151 of HPI Sys tem at DB-1 A meeting was held at Glen Ellyn, NRC Region III, Wednesdaj, September 5, to obtain further infonnation, and discuss the options and response actions to the NRC's SER concerning the nB-1 ISI (pump and valve) progr am which essentially defines valves HP 56-57-58-59-48-49-5D-51 of the HF I System (see Pt.ID Drawing 033) as Category A-C.

TED had listed these valves as category C only (i.e., no testing defined).

Present were:

%,r#5IoD6MT P. Fng NRC R. Peters Manager Licensing. TED H. Askwith HAFA H. Cobb HAFA In discussing the WASH 1400 Event V issue referred to by tte SER, it was apparent that the NRC merabers present were not wholly familiar with this subject. Obviously then it was not a totally pervasive item within the NRC and the subject was most probably raised by HRC Headquarters ord not the region.

The TED design rationale and reasons for the back-to tack check valves were explained as being to facilitate a code class change.

It was also explained that the system met the regulatory general desi n criteria for

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G containment, which had always been the prior concerns addressec by the 151 program.

There was an attempt by the NRC to introduce another iten irito the issue which was the integrity of the check valves in the makeup line.

It was explained that this was a constantly operative (modulating) system, as such it is not within the accepted ground rules of " safety related" valves; i.e.,

valves which are required to move to mitigate the consequentcs of an accident.

It is believed that the NRC staff accepted this prenise but DB-1 staff should be aware that the issue is likely to be raised again separately.

In this case, acceptance to test would not create problems as it could be simply undertaken, but there was not intention to settle such issues during discussions on a separate subject.

In keeping with the suggestions by the NRC in the SER of ccasidering alternative testing such as RT, UT, etc., the options for leak testing the valves at issue were briefly defined. The methods referred being wholly non-intrusive systems, such as acoustic emission and temperature mcnitoring my PDR ORO 05o oo 36H2 eft 9 I 1 8701140311 040910 e urt

Memo - Page Z-September 10, 1984 To:

C. Daft From: H. Cobb-e.g.; Mode 2 plant conditions. No mention was made of penetraling the coolant boundary!

These discussions appeared to meet the NRC t taff's concerns, and they were amenable at the regional level to a proposed time scale for implementing the task extending to the refueling outage, approximately 18 months hence.

Finally as a result of discussions on the design philosoph es of the subject system, and to address some of the NRC's concerns it wa s agreed to recognize that we should do intersystem* leak tests on the following valves:

HP 2A-B-C-D, HP 22-23 (see Drawing 033) leak tested and leak rat e quantified and valves MU 196 ard 197 (see Drawing 031). These valves are easily i

with the HAFA MMLT system.

• Intersystem in this instance is that which is separated by an internal barrier such as a. valve seat.

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