ML17277B354

Confirms 840328 Telcon Re post-accident Sampling Sys. Modified Sys Installed,Tested,Functional & in Compliance W/Tmi Action Item II.B.3 & License Condition 13

ML17277B354
Person / Time
Site:	Columbia
Issue date:	03/28/1984
From:	Mazur D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
TASK-2.B.3, TASK-TM GO2-84-177, NUDOCS 8404030529
Download: ML17277B354 (12)

Text

REGULATORY INFORMATION DISTRIBUTION SYSlEN (RIDS)

'C ACCESSION NBR:8404030529 OOC.DATE: 84/03/28 NOTARIZED: NO DOCKET ¹ FACIL:50-397 HPPSS Nuclear Projecti Unit 2E Nashington Public Powe 05000397 AFFILIATION AUTH INANE NAZUREO ~ 8 RECIP

'ashington AUTHOR Public Power NAME, RECIPIENT AFFILIATION Supply System SCHNENCER<A. Licensing Branch 2

SUBJECT:

Confirms 840328 telcon re post accident sampling sys, Modified sys installeditested,functional 8 in compliance w/TNI Action Item II;BE 3 8 License Condition 13 TITLE: Licensing CODE: 8001S COPIES RECEIVED:LTR Submittal: PSAR/FSAR Amdts 8 ENCL Related j 'ISTRISUTION Correspondence SIZE:

NOTES:

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Washington Public Power Supply System 3000George Washington Way P.O. Box968 Richland, Washington99352-0968 (509)372-5000 Docket No. 50-397 840328 84040305@9 050003~7 PDR ADQCK PDR P"

March 28, 1984 G02-84-177 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

SUPPLY SYSTEM NUCLEAR PLANT NO. 2 POST ACCIDENT SAMPLING SYSTEM MODIFICATIONS The purpose of this letter is to confirm our telephone conversation of this morning concerning the WNP-2 Post Accident Sampling System (PASS).

As we have discussed, the Plant 2 PASS (Fig. 1) was recently modified based on recommendations from the General Electric Company and the BWR Owner's Group to enhance the system capability. The modifications were made to simplify the design, improve system operability and to improve dose projections (ALARA).

The modified system (Fig. 2) is presently installed, tested and functional. Our personnel have been trained in its operation and we feel that we are in compliance with the requirements of TMI action item II.B.3 and WNP-2 License Condition 13 (NPF-21).

As you are aware, the modifications eliminated the capability to obtain a grab sample of the reactor coolant for performing a dissolved gas analysis. While we do not feel that this capability is required to meet the above noted conditions, we have agreed that the grab sample capability will further enhance the system and will meet the recommendations of Regulatory Guide 1.97.

The capability to obtain the grab sample will be accomplished by adding a sample tap to the existing system as discussed with you today and as shown in Figure 3 (attached). This modification has been discussed with the NSSS vendor (General Electric Co.) and with our Architect-Engineer (Burns and Roe). The sample tap will be installed, procedures prepared, and personnel trained by May 1, 1984.

Because we presently have a cold, clean core and the testing to be performed between now and flay 1 will result in only a minimal amount of radioactivity in the core, this modification should not be a condition for exceeding five percent (6%) of rated core thermal power.

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Mr. A. Schwencer Page Two If there are any further questions, please contact Mr. P. L. Powell, WNP-2 Licensing Manager.

Very truly yours, D.W.t r Managing Director GCS/kd Attachments: (3) As stated cc: R Auluck - NRC WS Chin - BPA (901A)

N Lewis - EFSEC AD Toth - NRC Site (901A)

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