NUREG-0730, Forwards Meteorology & Effluent Treatment Branch Input to Suppl 3 of Ser,Reviewing NUREG-0737,Item II.F.1,Items 1 & 2. Item 2 Re Sampling Provisions for Reactor Bldg Remains Open Issue

Forwards Meteorology & Effluent Treatment Branch Input to Suppl 3 of Ser,Reviewing NUREG-0737,Item II.F.1,Items 1 & 2. Item 2 Re Sampling Provisions for Reactor Bldg Remains Open Issue

ML20213E564
Person / Time
Site:	Columbia
Issue date:	08/19/1983
From:	Muller D Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
References
CON-WNP-0640, CON-WNP-640, RTR-NUREG-0730, RTR-NUREG-0892, RTR-NUREG-730, RTR-NUREG-737, RTR-NUREG-892, TASK-2.F.1, TASK-TM NUDOCS 8308250620
Download: ML20213E564 (4)

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METB R/F METB Plant File Docket ?!o.: 50-397 AUG 191983 MEMORANDUM FOR: Thomas A. Novak, Assistant Director for Licensing, DL FROM: Daniel R. Huller, Assistant Director for Radiation Protection, DSI SUBWCT: METB INPUT TO NUREG-0892. SUPPLEMENT NO. 3, WNP-2 SER REGARDING NUREG-0737, II.F.1, ITEMS 1 AND 2 Enclosed is the Meteorology and Effluent Treatment Branch input to Supple-ment No. 3 of the WNP-2 SER. The information provides our review of TMI action plan items (NUREG-0737, II.F.1, Itens 1 and 2) as submitted in Amend-ment 29 of the WNP-2 FSAR. Due to the issues specified in the attached SER Supplement Writeup, fiUREG-0737, II.F.1, Item 2 remains an open issue.

Questions concerning the review and evaluation should be addressed to Dr. Charles L. Miller (27639), the cognizant reviewer for the WNP-2 facility.

Original signed by ,

Daniel R, Mutter .

Daniel R. Muller, Assistant Director for Radiation Protection Division of Systems Integration

Enclosure:

As Stated cc: Ritattson WGarunill ASchwencer CWillis CMiller RAuluck e308250620 830819

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11. Radwaste Systems 11.5 Process and Effluent Radiological Monitoring and Samoling Systems In the SER, the staff indicated that the applicant had committed to provide the equipment for sampling and monitoring process and effluent streams during postulated accidents in accordance with the guideline in NUREG-0737, but had yet to submit detailed information of his proposed designs or equipment. A complete staff evaluation was to be supplied in a supplement to the SER.

In Amendment 29 of the WNP-2 FSAR the applicant provided the detailed informa-tion that was required for the staff to conduct an evaluation.

Table 11.3, Prccess and Effluent Radiation Monitoring System, is an updated version of the corresponding Table 11.3 that appears in the SER, and sup-plies the information that is required by NUREG-0737, II.F.1, Item 1 The staff has reviewed the applicant's submittal with respect to NUREG-0737, II.F.1, Items 1 and 2. We find that the WPPS commitment and descriptions meet the requirements of NUREG-0737, II.F.1, Item 1, subject to regional inspectors verifying the design during a post implementation review to be conducted after installation.

Open Item: NUREG-0737, II.F.1, Item 2 Although the sampling provisions are satisfactory for the reactor building vent, the applicant needs to add a discussion in the FSAR of the nethods, procedures, and any special equipment for analyzing samples. Since -samples are projected to be highly radioactive, some snecial methods, precautions, etc., should be established. If special equipment is required, it should be described. If this aspect can be handled procedurally, the applicant should DISIGnTZD OEIGITAIP Certified EF .

., u say so, and provide procedures for Regional review prior to power operation.

Also, procedures should be in place for turbine building vent, and radwaste building vent hot samples. Until this information is provided, this remains an open item.

., u Table 11.3 Process and effluent radiation monitoring system Stream monitored No. Monitor classification Monitor sensitivity liquid RHR standby service water 2 Gamma-scintillation 1 x 10 s pCi/ml Reactor building closed 2 Gamma-scintillation 1 x 10 8 pCi/ml cooling water Radwaste effluent 1 Gamma-scintillation 1 x 10 8 pCi/ml Circulating water effluent 1 Gamma-scintillation 1 x 10 8 pCi/nl Service water 1 Gamma-scintillation 1 x 10 8 pCi/m1 Turbine building sump 3 Gamma-scintillation 1 x 10 8 pCi/ml discharge Condensate storage area 1 Gamma-scintillation 1 x 10 s pCi/ml floor drain Gaseous Reactor building exhaust ' 4 Geiger-Mueller (not provided) plenum Offgas post-treatment 2 Geiger-Mueller (not provided)

Reactor building elevated vent ,

(Normal range) 1 Beta-scintil .. tion 1 x 10 s pCi/ml l (Acciden.t range)

• y-Ionization chamber 1 x los pCi/ml* j Turbine building vent  :

l (Normal range) 1 Beta-scintillation 1 x 10 6 pCi/ml l (Accident range) 1 Beta-scintillation 1 x 103 pCi/ml*  :

Radwaste building vent  !

(Normal range) 1 Beta-scintillation 1 x 10 8 pCi/ml Beta-scintillation 1 x 103 pCi/ml*

(Accident range) 1 O upper range

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