United States Nuclear Regulatory Commission - Protecting People and the Environment

U.S. Nuclear Regulatory Commission

Clarification of the 11 Criteria of NUREG-0737 on Postaccident Sampling System

HPPOS-011 PDR-9111210103

Title: Clarification of the 11 Criteria of NUREG-0737 on

Postaccident Sampling System (PASS) Capability

See the letter from S. A. Varga to J. A. Jones (Vice

President, Carolina Power and Light Company) dated

September 24, 1982. Enclosed with this letter were the 11

criteria contained in NUREG-0737, Item II.B.3, on PASS

capability and clarification developed by the NRR staff.

These 11 criteria are briefly discussed below; however, the

document must be reviewed in its entirety. The licensee


1. Provide information on sampling and analytical

laboratory locations and their relative elevations,

distances, as well as sample handling, transport,

recirculation, analytical time limits, and provisions for

sampling during loss of off-site power sufficient to meet a

3-hour sampling and analysis time limit.

2. Provide discussions of counting equipment

capabilities including provisions for sample handling and

background radiation reduction to personnel (ALARA);

procedures relating radionuclide concentrations to reactor

core damage including the monitoring for short and long

lived volatile and nonvolatile radionuclides, as well as

provisions for estimating core damage based on radionuclide

concentrations, core temperatures and sample location;

discuss the capability of obtaining a grab sample,

transport and analyzing for hydrogen; discuss capabilities

to sample and analyze for accident sample species; and

discuss the suitability, reliability and maintenance

information of selected on-line instruments.

3. Provide system schematics and discussions that

clearly demonstrate PASS, including recirculation, is

possible without using isolated auxiliary systems.

4. Discuss methodologies for measuring total dissolved

gas or hydrogen and oxygen and how this information is

related to reactor coolant system concentrations. In

addition, if chlorides exceed 0.15 ppm, verification that

dissolved oxygen is <0.1 ppm is required.

5. BWR's located near or using sea or brackish water

in heat exchangers with single barrier protection are

required to analyze chloride within 24 hours. All other

plants have 96 hours. Initial chloride analysis must use

dilutions of <1:1000, be reported in units of ppm, and have

<0.1 ppm dissolved oxygen.

6. Provide information on predicted personnel

exposures based on person-motion sampling, transport and

analysis of samples.

7. PWR's must perform boron analysis on primary

coolant. BWR's must have the capability to perform boron

analysis, but need not do them providing boron was not


8. Have the capability to obtain diluted and undiluted

backup samples when required. If off-site laboratories

will do the backup analysis, an explanation of the

capability to obtain and ship one sample per week until

accident conditions do not exist is needed.

9. Discuss the predicted activity in the samples to be

taken and the methods of handling / dilution used to reduce

activity sufficiently for the required analysis. The

predicted background radiation levels in the counting room,

including the contribution from other samples, must be

stated. 10. Discuss the accuracy, range, and

sensitivity of the methods of analysis. These must be

adequate to provide the operator sufficient and pertinent

data describing the radiological and chemical status of the

reactor coolant system. The recommended accuracy,

sensitivity, and ranges for numerous compounds are

described in this criterion.

11. Describe provisions for purging sample lines,

reducing sample line plateout, decreasing sample loss and

distortion, preventing sample line blockage, sample

disposal, and limiting reactor coolant loss from ruptured

sample lines. The ventilated exhaust from the sampling

station must be filtered with charcoal absorbers and HEPA

filters, however, the ventilation system need not be


Regulatory references: NUREG-0737, Technical Specifications

Subject codes: 5.0, 7.6, 8.3, 10.1, 12.16

Applicability: Reactors

Page Last Reviewed/Updated Thursday, March 29, 2012