ML20206D248
| 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: |
| References | |
| 50-267-87-07, 50-267-87-7, NUDOCS 8704130281 | |
| Download: ML20206D248 (6) | |
See also: IR 05000267/1987007
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/87-07
License:
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
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Inspector:
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R. E. Bser, Radiatiory Specialist, Facilities
'Date
Radiological Protectidn Section
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Approved:
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'8~ Murrhy, Chief, Facil) ties Radiological
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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
- 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
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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
02.05 - Replacement Personnel
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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
not achieve its requirements, and had a low priority, and the commitment
to achieve and maintain TS compliance was questionable.
A copy of the same allegation was presented to the licensee by the alleger
when he terminated employment at FSV on December 31, 1986.
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The licensee performed an in-depth evaluation, documented as QA monitoring
procedure report QAMP-MAC-01-87-01, dated February 6, 1987, of the
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
recommendations to improve the program and concluded that, except for
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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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