ML20151U530

Forwards Response to Re Criterion 10 of NUREG-0737,Item II.B.3 Found in Util 840110 Response.All Analytical Procedures Used to Analyze post-accident Sample Based on ASTM Procedures

ML20151U530
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	02/04/1986
From:	Taylor J DAIRYLAND POWER COOPERATIVE
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM LAC-11396, NUDOCS 8602110042
Download: ML20151U530 (3)

Text

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'OOPERA TlVE

• P O. BOX 817 2615 EAST AV SOUTH . LA CROSSE. WISCONSIN $4601 (608) 788 4 000 February 4, 1986 In reply, please refer to LAC-11396 DOCKET NO. 50-409 Mr. John A. Zwolinski, Director BWR Project Directorate il Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

DAIRYll.ND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO.'DPR-45 RESPONSE TO CRITERION 10 0F II.B.3 0F 0737

REFERENCES:

-(1) NRC Letter, Crutchfiled to Linder, dated June 30, 1982.

(2) DPC Letter, Linder to Denton, LAC-6979, dated June 12, 1980.

(3) DPC Letter, Linder to Crutchfield, LAC-8468, dated August 6, 1982.

(4) .NRC Letter, Crutchfield, to Linder, dated November-3, 1983.

(5) DPC Letter, Linder to Crutchfield, LAC-9526, dated January 10, 1984.

(6) NRC Letter, Crutchfield to Linder, dated February 29, 1984.

(7) DPC Letter, Linder to Crutchfield, LAC-9818, dated April 12,'1984.

Gentlemen:

This submittal is in response to your letter of February 29, 1984 (Reference 6).regarding itens of concern for NUREG-0737, Item II.B.3, found in Dairyland Power's resposne dated January 10, 1984 (Reference 5). '

, . EB (LIAW)

PSB (L. ' HtJLMAN) 8602110042 860204 EICSB-(SRINIVASAN)

PDR A00CK 05000409 PDR / HS8 (ACTING)

P f FOB (VASSALLO)

AD - C. LAINAS (Ltr only) l

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- c. Mr. J hn A. Zwolin';ki, Dirsetor Fabru ry 4, 1986 BWR Project Directorate #1- LAC-11396 If you have any questions regarding this submittal, please contact me..

Very truly yours, DAIRYLAND POWER COOPERATIVE

~ James W. Taylo

' General Manager JWT:LLN:sks Enclosure cc: J.:G. Keppler, Regional.III NRC Resident Ins pector John Stang, LACBWR Project Manager

-WP4.39

, s' Enclosure NRC Criterion 10:

Accuracy, range and sensitivity shall be adequate to provide pertinent data to the operator in order to describe radiological and chantical status of the reactor coolant systent.

DPC Response LACBWR's primary coolant P.A.S.S. does not contain any of the equipment that would be used to perform the required analysis. The PASS is strictly a system by which a primary coolant sample can be obtained. This sample is then transported to the Radiochem Lab where all the required analyses will be performed. Because there is no inline analysis equipeant used in the primary coolant PASS, none of the analytical equipment will be exposed to the potential severe radiological environment which may occur during an accident condition. Therefore, the induced gamma radiation field of the standard test matrix does not apply to LACBWR analytical equipment.

The primary coolant sample taken to the Radiochem Laboratory will be handled and diluted prior to any required analysis as per EPP-6. This sample dilution will again decrease the effects of the accident environment on any analytical equipment. Because of the methodology for analysis of a primary coolant post accident sample, the test matrix in criterian 10 does not apply-to LACBWR.

All analytical procedures used to'analysze a post accident sample are based on ASTM procedures.

Chloride analysis is based ~on ASTM procedure D512. This analytical method has the following interferences:

500 ppm sulfide 1 '1000 ppm iodide 1000 ppm anmonia Boron analysis is based on ASTM procedure D3082. This analytical method has the'following interferences.

I 25 ppm silica 25 ppm phosphate pH will be determined using an orion pH meter based on ASTM procedure D1293.

There are no interferences to this method.

Gross activity and gamma spectrum will be performed on equipment located in the Radiochem Laboratory. A primary coolant sample will be diluted as per

. EPP-6 to reduce counted dead time to less than 10%. This eliminates any concern of the radiation levels this equipment is exposed to.

The accuracy, range and sensitivity of the PASS instruments and analytical procedures are consistent with the recommendations of Reg. Guide 1.97 Rev. 3 and the clarifications of NUREG-0737 Item II.B.3, post-accident sampling

capability (NRC letter Crutchfield to Linder dated 06-30-82) with the i

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exceptions noted in DPC letter Taylor to Zwolinski, dated 07-17-85.- The analytical methods and instrumentation were selected. for their ability to operate in the post-accident sampling environment they would -be exposed to' at LACBWR.

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Semi-annual training is held'for the health physics personnel who would be

' involved in the collection and handling of an' accident coolant' sample.- This.

training uses_ nock. samples only. . it is done to instruct the personnel on the proper handling methods necessary to handle _ a potentially high radioactive

-sample. Training is not conducted on the analysis procedures.: This is not performed because the personnel who would analyze a post accf. dent sample-routinely perform all' the required analytical procedures necessary to perform .

--the required post accident sample analysis in the normal sampling program.

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