ML17297B143

From kanterella
Jump to navigation Jump to search
Comments on NUREG-0777,DES for Facilities.Radiological Monitoring Program Should Be Modified to Include Problems of Monitoring Radiohalogens in Presence of Radionoble Gases
ML17297B143
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 12/07/1981
From: Villforth J
FOOD & DRUG ADMINISTRATION
To: Kerrigan J
NRC
References
RTR-NUREG-0777, RTR-NUREG-777 NUDOCS 8201070076
Download: ML17297B143 (6)


Text

ACCESSION NBR:820 FACIL;STN"5Q"528 STN 50-529 STN"50 530 AUTH INANE VILLFORTHPJ,C, RECIP. NAME KERRIGANP J ~

1070076 DOC ~ DATE: 81/12/07 NOTARIZED; NO Palo Verde Nuclear StationP Unilt ii Ar izona Publ i

'Palo Verde Nuclear Stations Uni;t 2P Arizona Publi Palo Verde Nuclear StationP Uniit 3P Arizona Publi AUTHOR AFFILIATION HENPDept>>ofP

'Food 8

Drug Administration RECIPIENT A F F IL'I ATION NRC -

No Detailed Affiliation Given DOCKET OSOOQ528 05000529 05000530

SUBJECT:

Comments on NUREG-0777PDES for facilities. Radiological monitoring program should be modified to include problems of monitoring radiohalogens in presence of =radionable gases'ISTRIBUTION CODE:

COOED:COPIES RECEIVED:LTR j ENCL Jg SIZE:

TITLE: Env i r on.

Comments.

NOTES:Standardized Plant

~ 1 cy.C Grimes Standardi-zed,Plant,i cy:C Grimes Standardized

'Plant

~ 1 cy.'C Grimes 050Q0528 OBOOOBEO 05000530 RECIPIENT ID CODE/NAME ACTIOt'IC BR e3 BC Qe KERRIGANrJ>>

01 INTERNAL: ELD NRR/DE/AEAB 20 NRR/DE/HGEB

?1 NRR/DSI/AEB 19 NRR/DS I/RAB 17 COPIES LTTR ENCL 1

1 1

1 1

RECIPIENT ID CODE/NAME ANL IE 13 NRR/DE/EEB 16 NRR/DE/SAB 18 NR FTSB 15 E'G FILE 00 COPIES LTTR ENCL EXTERNAL: ACRS NATL LAB NSIC 21 Q5 1

5 1

LPDR 03 NRC PDR 02 NTIS P~T/( I Sl s

TOTAL NUMBER OF COPIES REQUIRED:

L'TTR P'd ENCL Ptl'

1

it--r/ ~

pg Commission 82pip7pp7 5ppp528 8ii2P7

DR ADOC

>DR D

ji Ms. Janis Kerrigan Division of Licensing, U.S. Nuclear Regulatory Washington, D.C.

20555 DEPARTMENT OF H

.H S HUMANSERVICES C

pJ Public Health Service Food and Drug Administration Rockville MD 20857

Dear Ms. Kerrigan:

lhe Bureau of Radiological Health staff have reviewed the Draft Environmental Statement (DES) for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, NURIM-0777, dated October 1981.

In reviewing the DES, we note that (1) the application for a construction permit is dated July 1974, (2) the NRC staff evaluation was issued as a Final Environ-mental Statement Construction Phase in September

1975, (3)

DHHS comments were provided on the Draft DES Construction Phase (Appendix A-110, page A-27) June 10, 1975, prior to issuance of the construction permit in May 1976, and (4) as of July 1981, the construction of Unit 1 was about 90 percent canplete, Unit 2 was about 65 percent complete, and Unit 3 was about 24 percent cmplete.

The Bureau of Radiological Health staff have reevaluated the public health and safety impacts associated with the proposed operation of the plant and have the following comments to offer:

l. It appears that the dose&esign objectives of 10 CFR 50, Appendix I, the operating standards of EPA's 40 CFR 190, and the applicant's radioactive waste management system for the PVNGS units provide adeauate assurance that the poten-tial individual and population radiation doses meet current radiation protection standards.

It is recognized that there are no liguid effluents, conseguently the doses presented in the DES are from the radionuclides expected to be released annually to unrestricted areas in only the gaseous effluents from normal reactor operations.

2. The environmental pathways discussed in Section 5.9.1.

and shown schematically in Figure 5.1 cover all emission air pathways that could impact on the population in the environs of the facility.

The dose computational methodology and rmdels (Appendix C and D) used in the estimation of radiation doses to individuals near the plant and populations within 80 km of the plant have provided the means to calculate a reasonable estimate of the doses resulting from normal operations and accident situations at the facility.

Results of these calculations are shown in Appendix C, Tables C-4, C-5 and C-6, and confirm that the calculated doses meet the design objectives.

f' I

l

Ms. Janis Kerrigan, NRC Page 2

3. The discussion in Section 5.9.2 on postulated accidents is considered to be an adequate assessment of the radiation dose pathways and dose and health impact (Table 5.12) of atmospheric releases.

Under normal operation, there is no release of radioactivity to ground water.

However, there is a potential for the accidental release of radioactive material into the hydrosphere through contact with ground water.

This pathway could lead to population exposure from inhalation or.ingestion of contaminated food or water.

Even though this event is unlikely, the emergency plan should include provisions for expanding the ground water monitoring program to be prepared for such an accidental release.

In particular, the sample collection points should be in the expected pathway and sanple analyses should be specific for the radionuclides that are likely to be released.

Section 5.9.2.4(3) states that the emergency preparedness plan including protective action measures for the Palo Verde facility and environs is in an

advanced, but not yet fully developed stage.

We will forego further comments on emergency plans, realizing that the process of granting an operating license to the facility will include an adequate review of emergency preparedness (FEMA-NRC Memorandum of Understanding, Regional RAC's, criteria in NUREG-0654).

We have representation on the RAC's whose evaluation of the emergency planning relevant to Palo Verde will speak for this agency.

4.

Lhe radiological monitoring program, as presented in Section 5.9.1.4 and summarized in Table 5.8, appears to provide an adequate sampling frequency in the expected critical exposure pathways.

The analyses for specific radio-nuclides are considered sufficiently inclusive to (1) measure the extent of emissions from the plant, and (2) verify that such emissions meet applicable radiation protection standards.

In view of some of the monitoring problems during the Three Mile Island-2

accident, we suggest the plan be modified to include a section that addresses the problems of monitoring radichalogens (especially radioiodines) in the presence of radionoble gases.

'Ibis could be accomplished by reference 'to FEMA-REP-2, a document on instrumentation systems prepared with considerable input from NRC.

5. Section 5.10 and Appendix G of this DES contains a description of the envi-ronmental impact of the Uranium Fuel Cycle.

Lhe environmental effects pre-sented are a reasonable assessment of the population dose commitment and the health effects associated with releases of radon-222 from the uranium fuel cycle.

Thank you for the opportunity to review and comment on this draft document.

Sincer ly yours, r

J hn C. Villforth D rector reau of Radiological Health

4 sf I.

lJ J,l, f

I