IP 71124.07, Radiological Environmental Monitoring Program

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https://www.nrc.gov/docs/ML1728/ML17286A291.pdf

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Issue Date: 12/21/17 1 71124.07

NRC INSPECTION MANUAL ARCB

INSPECTION PROCEDURE 71124 ATTACHMENT 07

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Effective Date: January 1, 2018

INSPECTABLE AREA: Radiological Environmental Monitoring Program

CORNERSTONE: Public Radiation Safety

INSPECTION BASES: 10 CFR 20.1302 requires licensees take appropriate surveys of the

unrestricted and controlled areas and effluents released into these

areas to demonstrate compliance with the dose limits for individual

members of the public. 10 CFR 50.36a requires licensees to

establish Technical Specifications to keep releases of radioactive

materials ALARA and provides numerical guidance via 10 CFR Part 50 Appendix I for establishing limiting conditions for operation to

ensure effluents from light water cooled reactors are ALARA. 10 CFR 50 Appendix I directs licensees to establish surveillance and

monitoring programs that provide data on measurable levels of

radiation and radioactive material in the environment to evaluate the

relationship between the quantities of radioactive materials released

in effluents and resultant radiation doses to individuals from

principal pathways of exposure. The scope of the REMP is

specified in 10 CFR Part 50, Appendix I, Section IV, paragraph B.

Additionally, licensees are to identify changes in the use of

unrestricted areas (e.g., for agricultural purposes) to permit

modifications in the monitoring program for evaluating doses to

individuals from principal pathways of exposure. Implementation of

these requirements is described in plant-specific Technical

Specifications and, typically, further described in licensee-controlled

Offsite Dose Calculation Manuals (ODCM).

This inspection area verifies aspects of the Public Radiation Safety

Cornerstone for which there are no performance indicators to

measure performance.

LEVEL OF EFFORT: Inspect Biennially

Issue Date: 12/21/17 2 71124.07

PROGRAM APPLICABILITY: IMC 2515 App A

71124.07-01 INSPECTION OBJECTIVES

01.01 To verify that the Radiological Environmental Monitoring Program (REMP) quantifies

the impact of radioactive effluent releases to the environment and sufficiently validates

the integrity of the radioactive gaseous and liquid effluent release program.

01.02 To verify that the REMP is implemented consistently with the licensee’s TS and/or

ODCM and to validate that the radioactive effluent release program meets the design

objectives in Appendix I to 10 CFR Part 50.

01.03 To ensure that the REMP (1) monitors noneffluent exposure pathways (e.g., onsite

spills or leaks, exposures from direct and scattered (skyshine) radiation from plant

facilities and components), (2) is based on sound principles and assumptions, and

(3) validates that doses to members of the public are within the dose limits of

10 CFR Part 20, “Standards for Protection against Radiation,” and 40 CFR Part 190,

“Environmental Radiation Protection Standards for Nuclear Power Operations,” as

applicable.

01.04 To verify that the licensee is continuing to implement the voluntary NEI/Industry Ground

Water Protection Initiative (GPI).

01.05 To conduct a Routine Review of problem identification and resolution activities per

Inspection Procedure (IP) 71152, “Problem Identification and Resolution.”

71124.07-02 INSPECTION REQUIREMENTS

02.01 Site Inspection (1 Sample)

Walk down 3-5 of the air sampling stations and 3-5 of the thermoluminescent dosimeter

(TLD) monitoring stations to determine whether they are located as described in the

ODCM and to determine the equipment material condition.

For the air samplers selected above, review the calibration and maintenance records to

verify that they demonstrate adequate operability of these components.

Review the calibration & maintenance (or volume verification) records of up to five

composite water samplers, as available.

Verify that the licensee has initiated sampling of other appropriate media upon loss of a

required sampling station.

Observe the collection and preparation of 2-4 environmental samples from different

environmental media and verify that environmental sampling is representative of the

release pathways as specified in the ODCM and that sampling techniques are in

accordance with procedures.

Issue Date: 12/21/17 3 71124.07

Based on direct observation and review of records, verify that the meteorological

instruments are operable, calibrated, and maintained in accordance with guidance

contained in the FSAR, and licensee procedures. Verify that the meteorological data

readout and recording instruments in the control room and, if applicable, at the tower

are operable

As available, evaluate the licensee’s actions in response to 3-5 events that involved a

missed sample, inoperable sampler, lost TLD, or anomalous measurement.

Review the licensee’s assessment of any positive sample results (i.e., licensed

radioactive material was detected above the lower limits of detection or LLDs).

Select 3-5 structures, systems, or components (SSCs) that involve or could reasonably

involve licensed material for which there is a credible mechanism for licensed material

to reach ground water, and verify that the licensee has implemented a sampling and

monitoring program sufficient to detect leakage of these SSCs to ground water.

Verify that records developed since the last inspection that are important to

decommissioning are retained as required.

Review any significant changes made by the licensee to the ODCM and review

technical justifications for any changed sampling locations. Verify that the licensee

performed the reviews required to ensure that the changes did not affect its ability to

monitor the impacts of radioactive effluent releases on the environment.

Verify that the appropriate detection sensitivities are used for counting samples to

satisfy TS/ODCM required LLDs.

Review quality control charts for maintaining radiation measurement instrument status

and actions taken for degrading detector performance.

If the licensee uses a vendor laboratory to analyze REMP samples, verify that the

vendor’s quality control program, including inter-laboratory comparison programs, is

adequate.

Review the results of the licensees’ inter-laboratory comparison program to verify the

adequacy of environmental sample analyses performed by the licensee. If applicable,

review the licensee’s determination of any bias to the data and the overall effect on the

REMP.

02.02 GPI Implementation (1 Sample)

Verify that the licensee is continuing to implement the voluntary NEI/Industry Ground Water

Protection Initiative (GPI). Since the last inspection:

Review monitoring results of the GPI to determine if the licensee has implemented its

program as intended, and to identify any anomalous results. For anomalous results or

missed samples, determine if the licensee has identified and addressed deficiencies

through its corrective action program.

Issue Date: 12/21/17 4 71124.07

If applicable, document observations of incomplete or discontinued elements of the

licensee’s implementation of the GPI in the inspection report in Section 4OA5. [C1]

If the licensee is not implementing the minimization of contamination and survey

aspects of the GPI, review licensee methods of meeting the Decommissioning Planning

Rule requirements.

Review identified leakage or spill events and entries made into 10 CFR 50.75 (g)

records. Review evaluations of leaks or spills, and review any remediation actions

taken for effectiveness. Review onsite contamination events involving contamination of

ground water (Lessons Learned Task Force (LLTF recommendation #17). Assess

whether the source of the leak or spill was identified and mitigated.

Note: Limited, defined documentation of the review of abnormal or unplanned

radioactive discharges (e.g., leaks and spills) should be provided in the inspection

reports (see also IMC 0612) (LLTF recommendation #19)

For unmonitored spills, leaks, or unexpected liquid or gaseous discharges, ensure that

an evaluation was performed to determine the type and amount of radioactive material

that was discharged.

1. Assess whether sufficient radiological surveys were performed to evaluate the

extent of the contamination and the radiological source term. Verify that a

survey/evaluation has been performed to include consideration of hard-to-detect

radionuclides.

Determine whether the licensee completed offsite notifications; as provided in its GPI

implementing procedures

Review the evaluation of discharges from onsite surface water bodies that contain or

potentially contain radioactivity, and the potential for ground water leakage from these

onsite surface water bodies. Determine if the licensee is properly accounting for

discharges from these surface water bodies as part of its effluent release reports.

Verify that on-site ground water sample results and a description of any significant onsite leaks/spills into ground water for each calendar year are documented in the Annual

Radiological Environmental Operating Report (AREOR) for REMP or the Annual

Radiological Effluent Release Report (ARERR).

For significant, new effluent discharge points (such as significant or continuing leakage

to ground water that continues to impact the environment if not remediated), determine

if the ODCM was updated to include the new release point and includes the bases for

all new assumptions and parameters used in dose calculations.

02.03 Problem Identification and Resolution

For each sample, conduct a routine review of problem identification and resolution

activities using Inspection Procedure (IP) 71152, “Problem Identification and

Resolution.

Issue Date: 12/21/17 5 71124.07

71124.07-03 INSPECTION GUIDANCE

Inspection Planning

Review the annual radiological environmental operating reports and the results of any

licensee assessments since the last inspection enable to verifying that the REMP was

implemented in accordance with the TS and ODCM. Review the report for changes to

the ODCM with respect to environmental monitoring, commitments in terms of sampling

locations, monitoring and measurement frequencies, land use census, inter-laboratory

comparison program, and analysis of data. Guidance on the proper location of

environmental monitoring stations is in NUREG-1301, “Offsite Dose Calculation

Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,”

issued April 1991. Also, refer to the NRC Branch Technical Position, Revision 1, “An

Acceptable Radiological Environmental Monitoring Program (ADAMS Accession No.

ML010710060),” for additional information.

Review the ODCM to identify locations of environmental monitoring stations.

Review the final safety analysis report (FSAR) for information regarding the

environmental monitoring program and meteorological monitoring instrumentation.

Review quality assurance audit results of the program to assist in choosing inspection

“smart samples.” If the licensee uses a vendor laboratory to analyze the REMP

samples, review any audits and technical evaluations performed on the vendor’s

program.

Review the annual effluent release report and the 10 CFR Part 61, “Licensing

Requirements for Land Disposal of Radioactive Waste,” report, to determine if the

licensee is sampling, as appropriate, for the predominant and dose-causing

radionuclides likely to be released in effluents.

Review reported groundwater monitoring results, and changes to the licensee’s written

program for identifying and controlling contaminated spills/leaks to ground water.

Review changes to the plan and program since last inspection to identify changes that

have decreased effectiveness and scope.

03.01 Site Inspection

Consistent with smart sampling, the air sampling stations should be selected based on

the locations in the downwind sectors with the highest concentration per unit release

rate (X/Q), and highest deposition per unit release rate (D/Q), and thermoluminescence

dosimeters (TLDs) should be selected based on the most risk-significant locations (e.g.,

those that have the highest potential for public dose impact). Shifts in wind sectors with

the highest X/Q and D/Q may be detected by comparing several years of the licensee’s

meteorological data.

No inspection guidance.

No inspection guidance.

Issue Date: 12/21/17 6 71124.07

Consider the following media ground and surface water, milk, vegetation, sediment, and

soil. Guidance on sample collection and preservation is provided in NUREG-1576,

“Multi-Agency Radiological Laboratory Analytical Protocols Manual” (MARLAP), issued

July 2004. Also, refer to the NRC Branch Technical Position, Revision 1, “An

Acceptable Radiological Environmental Monitoring Program,” for guidance on sampling

other appropriate media upon loss of a required sample location.

No inspection guidance.

Compare readout data (i.e., wind speed, wind direction, and delta temperature) in the

control room and at the meteorological tower to identify any differences that would

indicate that inaccurate data are being used for dose determination.

Note that most 10 CFR Part 50 licensees will not be committed to Regulatory

Guide 1.23, “Meteorological Monitoring Programs for Nuclear Power Plants,” but may

be committed to Safety Guide 23, “Onsite Meteorological Programs,” (1972).

Review missed and or anomalous environmental samples to identify if they should be

reported in the annual environmental monitoring report. Review the licensee’s

assessment of any positive sample results (i.e., licensed radioactive material detected

above the lower limits of detection (LLDs). Review the associated radioactive effluent

release data that was the source of the released material. Ensure that the licensee has

addressed any positive indications in the environmental monitoring samples and has

adjusted the effluent monitoring program and dose modeling, as appropriate to ensure

the accuracy of the models. (See Section 6.8 in NUREG-1301, “Offsite Dose

Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized

Water Reactors,” and in NUREG-1302, “Offsite Dose Calculation Guidance: Standard

Radiological Effluent Controls for Boiling Water Reactors,” issued April 1991.)

No inspection guidance.

Some examples of SSCs are outdoor refueling water storage tanks, spent fuel pools,

spent fuel pool leak detection systems, outdoor tanks, outdoor storage of contaminated

equipment, buried piping, retention ponds, basins, or reservoirs, and steam lines.

Some examples of leak detection methods for the SSCs are ground water monitoring,

operator rounds, engineering walk downs or inspections, leak detection systems, or

periodic integrity testing.

Licensees should document significant contamination resulting from leaks and spills, as

required by 10 CFR 50.75, “Reporting and recordkeeping for decommissioning

planning,” paragraph (g).

Changes may be made in response to changes to the land census, long-term

meteorological conditions (3-year average), or modifications to the sampler stations

since the last inspection.

No inspection guidance.

If the licensee uses a vendor laboratory to analyze the REMP samples, review the

results of the vendor’s quality control program, including the inter-laboratory comparison

program, to verify the adequacy of the vendor’s program.

Issue Date: 12/21/17 7 71124.07

No inspection guidance.

RG 1.33, 1.21 and 4.15 provide guidance for licensees participating in an intralaboratory and inter-laboratory comparison program to verify the quality of analyses.

03.02 GPI Implementation

Monitoring results are provided in the licensee’s Annual Radiological Effluent Release

Report or the Annual Radiological Environmental Operating Report.

For Part 50 licensees, adequate implementation of the NEI-GPI provides one

acceptable method of implementing the Decommissioning Planning Rule requirements

in 10 CFR 20.1406 and 10 CFR 20.1501 in accordance with RG 4.22,

“Decommissioning Planning during Operations.” If the licensee chooses other methods

of implementing these requirements, review those methods of implementation.

For 10 CFR Part 52 licensees, in addition to complying with 10 CFR 20.1406, licensees

are committed to implementing the GPI as part of their licensing basis, including use of

the NEI 08-08A, “Generic FSAR Template Guidance for Life-Cycle Minimization of

Contamination” as implemented in design features and operational programs.

Decommissioning planning rule requirements are found in 10 CFR 20.1406

(minimization of contamination) (see Regulatory Guide 4.22, “Decommissioning

Planning during Operations”) and 10 CFR 20.1501, “General” for requirements on

subsurface surveys.

Assess whether sufficient radiological surveys were performed to evaluate the extent of

the contamination and the radiological source term. Verify that a survey/evaluation has

been performed to include consideration of hard-to-detect radionuclides. Note that the

use of scaling factors can be used in bounding calculations. 10 CFR 50.75(g) files (or

corrective action program files referencing 50.75(g) files) should contain a description of

the leak or spill (isotopes and quantities), location and size of the impacted area, cross

reference to survey results, and results of any remediation performed if undetected

leakage has occurred or is suspected and insufficient monitoring/remediation actions

have been taken by the licensee, discuss this issue with your supervisor. If assistance

in assessing the adequacy of the licensee’s onsite/offsite monitoring activities is needed

and/or site hydrologic characteristics are not clearly defined, the program office should

be consulted.

No inspection guidance.

No inspection guidance.

Surface water bodies include: ponds, retention basins and lakes.

No inspection guidance.

Guidance on new release points is provided in Regulatory Guide 1.21 and Lessons

Learned Task Force (LLTF) recommendation #17.

Issue Date: 12/21/17 8 71124.07

Note: In accordance with Regulatory Guide 1.109, a significant new exposure pathway

exists if a conservative evaluation yields an additional dose increment equal to or more

than 10 percent of the total from all exposure pathways considered in Regulatory Guide 1.109.

03.03 Problem Identification and Resolution

Per IP 71152, it is expected that routine reviews of PI&R activities should equate to

approximately 10 to 15 percent of the resources estimated for the associated baseline

cornerstone procedures, this is a general estimate only based on the overall effort

expected to be expended in each strategic performance area. It is anticipated that the

actual hours required to be expended may vary significantly from attachment to

attachment, depending on the nature and complexity of the issues that arise at the

particular facility. Overall, an effort should be made to remain within the 10 to 15 percent

estimate on a strategic performance area basis. Inspection time spent assessing PI&R

as part of the baseline procedure attachments should be charged to the corresponding

baseline procedure.

71124.07-04 RESOURCE ESTIMATE

For planning purposes, it is estimated to take 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />, on average (with a range of 25 to

33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />) to perform the requirements of this attachment.

71124.07-05 COMPLETION STATUS

Inspection of the minimum sample size will constitute completion of this procedure in the

RPS. The minimum sample size for this attachment is two, defined as the completion of the

activities contained in sections 02.01 and 02.02.

If any of the sample inspection requirements cannot be completed, the procedure should be

closed in accordance with IMC 0306, “Planning, Tracking and Reporting of the Reactor

Oversight Process (ROP).” For example, if certain steps could not be completed due to

sample unavailability, the procedure attachment should be declared “Complete – full sample

not available” with a comment addressing the specific steps or activities that could not be

completed.

71124.07-06 REFERENCES

10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” Criterion 64,

“Monitoring radioactivity releases,”

10 CFR 50.34a, “Design Objectives for Equipment to Control Releases of Radioactive Material in

Effluents—Nuclear Power Reactors,”

10 CFR 50.75, “Reporting and recordkeeping for decommissioning planning,”

IMC 0612, “Power Reactor Inspection Reports,”

Issue Date: 12/21/17 9 71124.07

Inspection Procedure 71152, “Problem Identification and Resolution,”

NEI 07-07, “Industry Ground Water Protection Initiative (GPI),”

NEI 08-08A, “Generic FSAR Template Guidance for Life-Cycle Minimization of Contamination,”

NRC, “Lessons Learned Task Force (LLTF) Report,” ADAMS ML062650312

NUREG-1301, “Offsite Dose Calculation Guidance: Standard Radiological Effluent Controls for

Pressurized Water Reactors,”

NUREG-1302, “Offsite Dose Calculation Guidance: Standard Radiological Effluent Controls for

Boiling Water Reactors,”

NUREG-1576, “Multi-Agency Radiological Laboratory Analytical Protocols Manual,”

Regulatory Guide (RG) 4.22, “Decommissioning Planning During Operations,”

RG 1.23, “Meteorological Monitoring Programs for Nuclear Power Plants,”

RG 4.22, “Decommissioning Planning During Operations,” and

Safety Guide 23, “Onsite Meteorological Programs.”

END

Issue Date: 12/21/17 Att1-1 71124.07

Attachment 1: Revision History for IP 71124, Attachment 07

Commitment

Tracking

Number

Accession Number

Issue Date

Change Notice

Description of Change Description of

Training Required and

Completion Date

Comment and

Feedback Resolution

Accession Number

(Pre-Decisional, NonPublic Information)

N/A 12/02/09

CN 09-030

Conducted four year search for

commitments and found none.

This new procedure is being issued as a

result of the 2009 ROP IP Realignment. It

supersedes inspection requirements in

IP 71121 and 71122.

Yes

09/09/2009

ML092810423

C1

Reference:

SRM-SECY11-019

(August 15,

2011)

Senior

Management

Review of

Overall

Regulatory

Approach to

Groundwater

Protection

ML12321A387

06/06/13

CN 13-013

This revision directs the inspection staff to

document observations of incomplete or

discontinued implementation of the

NEI/industry ground water protection

Initiative (GPI). The revision also instructs

inspection staff that if the licensee is not

implementing the GPI, to review the

adequacy of the licensee’s implementation

of the Decommissioning Planning Rule

under 10 CFR 20.1406(c) and 10 CFR 20.1501, including Part 52 licensee

requirements to implement the GPI and

NEI-08-08A.

N/A ML13085A201

ML13129A076

Issue Date: 12/21/17 Att1-2 71124.07

Commitment

Tracking

Number

Accession Number

Issue Date

Change Notice

Description of Change Description of

Training Required and

Completion Date

Comment and

Feedback Resolution

Accession Number

(Pre-Decisional, NonPublic Information)

N/A ML15345A067

04/01/16

CN 16-010

Revisions to the IP 71124.07 procedure

attachment were made in response to the

2013 ROP Enhancement Project.

This revised procedure includes

groundwater monitoring inspection

requirements transferred in from IP 71124.06.

The revision changed the way samples are

counted.

N/A IP revised only to

include new sample

sizes. There is no valid

comment resolution at

this time.

N/A ML17286A291

12/21/17

CN 17-031

Major editorial revision of IP 71124.07.

Section 02 was audited and modified to

move guidance to Section 03 and concisely

state actions necessary to complete each

requirement

Modified Inspection Bases to reference

applicable regulations. Adjusted guidance

in response to ROPFF 71124.06-1743.

PI&R was transitioned from an independent

sample to a requirement that would be

completed as part of each sample.

Guidance section updated to reflect

resource estimates for routine review of

PI&R activities per IP 71152 Section 04.01.

Verbal discussion of

changes during 2017

HP Counterpart

meeting, 09/06/2017

ML17300A476

Closed FBF 71124.06-

1743

ML17300B383