ML20206D248

Insp Rept 50-267/87-07 on 870302-06.Violation Noted:Failure to Sample & Analyze Effluent

ML20206D248
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/23/1987
From:	Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20206D220	List: ML20206D215 ML20206D230 ML20206D248
References
50-267-87-07, 50-267-87-7, NUDOCS 8704130281
Download: ML20206D248 (6)

See also: IR 05000267/1987007

Text

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APPENDIX B

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-267/87-07 License: DPR-34

Docket: 50-267

Licensee: Public Service Company of Colorado (PSC)

P. O. Box 840

Denver, Colorado 80201-0840

Facility Name: Fort St. Vrain Nuclear Generation Station (FSV)

Inspection At: FSV Site, Weld County, Platteville, Colorado

Inspection Conducted: March 2-6, 1987

Inspector: n f/ u ]?){/h/V// V' 'Y/$?

R. E. Bser, Radiatiory Specialist, Facilities 'Date

Radiological Protectidn Section

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Approved: [ . //k 6 28///////

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Murrhy, Chief, Facil) ties Radiological Date '

Protection Section

Inspection Summary

Inspection Conducted March 2-6, 1987 (Report 50-267/87-07)

Areas Inspected: Routine, unannounced inspection of functional areas of the

radiation protection program including: organization and management controls;

training and qualifications; external occupational exposure control and

personnel dosimetry; internal exposure control and assessment; control of

radioactive materials and contamination, surveys; and monitoring; facilities

and equipment; maintaining occupational exposures ALARA; reportable events; and

an allegation.

Results: Within the areas inspected, one violation was identified (failure to

sample and analyze effluent sample, paragraph 4). No deviations were

identified.

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DETAILS

1. Persons Contacted

PSC

• R. O. Williams, Jr. , Vice President, Nuclear Operations

D. R. Alps, Security Supervisor

F. J. Borst, Manager, Support Services

• M. J. Ferris, Manager, Operations Quality Assurance (QA)

C. H. Fuller, Station Manager

! *J. M. Gramling, Nuclear Licensing

S. Hofsetter, Licensing Engineer

• A. L. Holland, QA Engineer

D. A. Krout, Documents Clerk, Radiation Dosimetry

G. W. Lindsay, QA Engineer

D. D. Miller, Radiochemistry Supervisor

R. L. Millison, Engineering Technician

P. F. Moore, Supervisor, QA Technical Support

D. G. Seymour, QA Engineer

C. Stolley, General Employee Training Instructor

• P. F. Tomlinson, Manager, QA

G. D. Valentine, Health Physics Instructor

• W. E. Woodard, Health Physicist

Other Personnel

• R. E. Farrell, NRC Senior Resident Inspector

• P. W. Michaud, NRC Resident Inspector

The NRC inspector also interviewed several other licensee employees

including operations, health physics, and administrative personnel.

• Denotes those present during the exit interview on March 6, 1987.

2. Inspector Observations

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The NRC inspector discussed the following observations with the licensee

during the exit interview. These observations are neither violations nor

unresolved items. They were identified for licensee consideration for

program improvement, but they have no specific regulatory requirement.

The licensee indicated that these items would be considered.

ALARA Training - During general employee training, radiation workers

are not instructed to retreat to an area of low radiation intensity

when work is not being performed by the individual.

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Respiratory Air Characteristics - The licensee performs periodic

sampling (surveillance test - annually) of the air quality from the

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breathing air system; however, the sampling program did not include

periods when the air-line breathing air system was in operation and

self-contained breathing air bottles were being recharged.

3. Program Areas Inspected

The following program areas were inspected. Unless otherwise noted, the

inspection was completed and revealed no violations, deviations,

unresolved items, or open items. Notations after a specific inspection

item are used to identify the following: I = item not inspected or only

partially inspected; V = violation; D = deviation; U = unresolved item;

and 0 = open item.

Inspection Procedure Inspection Requirements

83722 Radiation Protection, Plant Chemistry, and

Radwaste: Organization and Management

Controls

02.01 - Organization

02.02 - Staffing

02.03 - Radiation Protection Manager

02.04 - Identification and Correction of

Weaknesses

02.05 - Audits and Appraisals

83723 Training and Qualifications: General

Employee Training, Radiation Safety, Plant

Chemistry, Radwaste, and Transportation

02.01 - Training Adequacy

02.02 - Employee Knowledge Retention

02.03 - Transportation /Radwaste Training (I)

02.04 - Staff Qualification Requirements

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02.05 - Replacement Personnel

02.06 - Accreditation Status

02.07 - Audits and Appraisals

02.08 - Identify Training Not Covered By

Accreditation (I)

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83724 External Occupational Exposure Control and

Personal Dosimetry

02.01,- Audits and Appraisals

02.02 - Changes

02.03 - Planning and Preparation for Outages

02.04 - Personal Dosimetry

02.05 - Administrative Controis-

02.06 - Records, Reports, and Notifications

83725 Internal Exposure Control and Assessment

02.01 - Audits and Appraisals

02.02 - Changes

02.03 - Planning and Preparation for Outages

02.04 - Assessing Individual Intakes of

Radioactive Materials ~

02.05 - Engineering and Administrative

Controls

02.06 - Respiratory Protection Equipment

02.07 - Records, Reports, and Notifications

83726 Control of Radioactive Materials and

Contamination, Surveys, and Monitoring

02.01 - Audits and Appraisals

02.02 - Changes

02.03 - Surveys and Monitoring

02.04 - Radioactive Materials and

Contamination Controls

83727 Facilities and Equipment

02.01 - Facility Changes

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83728 Maintaining Occupational Exposures ALARA

02.01 - Audits and Appraisals

02.02 - ALARA Program Changes

02.03 - Worker Awareness and Involvement

02.04 - ALARA Goals and Objectives

02.05 - ALARA Results

4. Reportable Event

The licensee reported to the NRC Operations Officer on February 15, 1987,

that an unanalyzed release of radioactive liquid waste had occurred and

approximately 2500 gallons from the waste monitor tank was discharged to

the South Platte River on February 7,1987.

Technical Specification (TS) 8.1.2.b.1 requires that before the release of

radioactive liquid effluent, two representative samples of liquid effluent

from the radioactive liquid waste system shall be analyzed for gross alpha

activity, gross beta activity, principal gamma emitters, I-131, tritium,

dissolved and entrained gases, and other radioisotopes of concern.

The waste monitor tank was released between 8:49 p.m. on February 7, and

1:10 a.m. on February 8,1987. A routine sample obtained from the

discharge stream at 11:35 p.m. on February 7, 1987, indicated that

regulatory limits were not exceeded.

The NRC inspector stated that performing a release of radioactive liquid

effluent without obtaining and analysing two representative samples of the

effluent prior to the release was considered an apparent violation of

TS 8.1.2.b.1., (267/8701-01). The violation was a licensee-identified

problem. However, it is reasonable to expect that the licensee should

have implemented proper controls to prevent the violation.

5. Allegation (4-86-A-129)

The NRC had received an allegation titled " Assessment of the Radiation

Monitoring Program at Fort St. Vrain Nuclear Generating Station," which in

general stated the radiation monitoring program was not comprehensive, did l

not achieve its requirements, and had a low priority, and the commitment  !

to achieve and maintain TS compliance was questionable.

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A copy of the same allegation was presented to the licensee by the alleger

when he terminated employment at FSV on December 31, 1986. i

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The licensee performed an in-depth evaluation, documented as QA monitoring I

procedure report QAMP-MAC-01-87-01, dated February 6, 1987, of the l

allegation. All suggestions and criticisms were evaluated by an

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independent third party between January 25 and February 5,1987. The

licensee initiated corrective action report 87-001 to correct program

deficiencies.

This evaluation did not identify any violations, but listed several

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recommendations to improve the program and concluded that, except for

allegations concerning incompetent personnel, complete disregard of

technical specifications, and lack of an I&C training program, many of the

alleger's suggestions and criticisms were valid.

The NRC inspector considers that each technical matter identified in the

allegation was adequately dispositioned by~the licensee. This allegation

is considered to be closed.

6. Exit Interview

The NRC inspector met with the NRC resident inspectors and licensee

representatives denoted in paragraph 1 on March 6, 1987, and summarized

the scope and findings of the inspection as presented in this report.

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