IR 05000302/1979015
| ML19241C170 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/25/1979 |
| From: | Jenkins G, Zavadoski R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19241C161 | List: |
| References | |
| 50-302-79-15, NUDOCS 7907270406 | |
| Download: ML19241C170 (6) | |
Text
'
[ga anag#'o UNITED STATES l'
- . 7/' 1 NUCLEAR REGULATORY COMMISSION
'
$e'
'"g E
REGION 11
.
o,
[ '8 101 MARIETT A ST., N.W., SUITE 3100 g v ' j
ATLANTA, GEORGIA 30303
.....
Report No. 50-302/79-15 Licensce: Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Facility Name:
Crystal River Unit No. 3 Docket No. 50-302 License No. DPR-72 Inspection at C.s River Site near Crystal River, Florida Inspeyr:
Et h
8M N
.
-
. Za a o~
i Date Signed
/r R.
Y'
5 A
Approved by:
.f.
t y L+w
/
G.R.Jeps,ActingSectionChief,FF&MSBranch Date Signed SUMMARY Inspection on May 7-11, 1979.
Areas Inspected This routine unannounced inspection involved 32 inspector-hours onsite in the areas of facility tours, radiation work permits, external radiation exposure control, exposure review, posting and control, training and qualifications, respiratory protection program, surveys, airborne radioactivity areas, bioassays and solid waste shipments.
Results Of the eleven areas inspected, no apparent items of noncompliance or deviations were identified in nine areas; two apparent items of noncompliance were found in two areas (Infraction - failure to prepare procedures for identifying containers of radioactive material (79-15-01), paragraph 4; Infraction - shipment of solid wastes (79-15-02), paragraph 14).
7 9 0727 0 W o
m{bI
- g. I LN ] J
.
DETAILS 1.
Persons Contacted Licensee Employees
- G.
P. Beatty, Jr., Nuclear Plant Manager
- J. Cooper, Jr., Nuclear Compliance Engineer
- J. R. Wright, Chemical and Radiation Protection Engineer
- J. L. Harrison, Assistant Chemical and Radiation Protection Engineer
- G. H. Ruszala, Supervisor, Radioactive Waste Management
- G. D. Pcrkins, Health Physics Supervisor
- R.
E. Fuller, Plant Engineer
- G. M. Williams, Nuclear Compliance Plant Engineer
- G. Holtz, Chem Rad Other persons contacted included six licensee mechanics and ten contractor mechanics.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on May 11, 1979 with those persons indicated in Paragraph 1 above. Items discussed included the items of noncompliance regarding procedures for labeling of stored material onsite and shipping of solid waste in appropriate containers. These items were acknowledged by the Plant Manager.
Two unresolved items were also discussed.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are discussed below.
a.
(0 pen) Unresolved Item (79-15-03) Exit From the Radiation Control Area.
During periods when the garage door from the waste drumming area in the Auxiliary Building is open, the potential exists for an individual to exit the RCA without the benefit of frisking.
Ingress is prevented by security guards, but egress is contingent upon thc astuteness of the chem rad technician directing other operations outside the door.
h n,
h
,-
QIJ
.
.
-2-
.
b.
(Open) Unresolved Item (79-15-04) Chemical Releases In the Auxiliary Building.
Technical Specifications require laboratory testing of charcoal absorbents in the Auxilary Building Ventilation System following a chemical release or painting, but do not quantify the amount or type.
The use of small amounts of any chemical in the radiochemistry laboratory in the Auxilary Building could place the ventilation system in the inoperable status.
5.
Facility Tours a.
The inspector toured portions of the Radiation Controlled Area (RCA)
on each day of the inspection and toured containment on May 8 and 11.
The inspector commented favorably on housekeeping inside containment and in the Auriliary Building. The inspector performed random radiation level surveys during these tours.
b.
While touring the Auxiliary Building on various days during the inspec-tion, the inspector noted several areas where bagged materials of radioactive materi l were being stored.
Accompanied by a licensee representative, the inspector observed one storage area where tools and equipment from the previous outage were beit 3 r.tored.
Licensee representatives estimated that the material had been stored in its present location for a period of at least six months. The inspector noted that scme items were not bagged at all, some were bagged in open bags, some were double bagged and a few bags were marked with black indellable markings identifying the contents and the radiation hazard inside the container. Radiation levels near unmarked, unlabeled open bags exceeded 10 mrem /hr as confirmed by licensee measurements. The inspector further observed that there were no procedures for bagging and labeling materials for storage within tI e RCA. The inspector informed licensee rperesentatives that their Technical Specification 6.11 requires that " Procedures for perconnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and that 10 CFR 20.203(f) requires that
' ach container of licensed
-
material shall bear a durable, clearly vis.Sle label identifying the radioactive contents" and further the requirad label "shall bear the radiation caution symbol and the words 'CAU1ICA, RADIOACTIVE MATERIAL'
or ' DANGER, RADI0 ACTIVE MATERIAL'.
It shall also provide sufficient information to permit individuals handling or using the containers, or working in the vicinity thereof, to take precautions to avoid or minimize exposures".
"As app rop ria te, the information will include radiation levels, kinds of material, estimate of activity, date for which activity is estimated, mass enrichment, etc."
The inspector informed licensee representatives that failure to have a procedure which takes into account the labeling requirements of 10 CFR Part 20 was an item of noncompliance (79-15-01).
3oG 2b3 9/J
,
-3-
.
6.
Radiation Work Permits (RWPs)
The inspector selected RWPs posted at the entrance to the Radiation Control Area (RCA). The inspector selected records from the file " Terminated RWPs" for the period January 1 through May 5, 1979. The inspector observed a Health Physics Shif t Supervisor discussing with maintenance personnel the radiation safety requirements for specific work and issuing RWPs.
The irlpector toured the Auxiliary Building and Unit 3 containment and observed implementation of RWP requirements for selected operations. No items
.ne of nor. compliance or deviations were observed by the inspector.
7.
External Radiation Exposure Control a.
The inspector observed the wearing of TLD badges and pocket chambers by workers during tours of the RCA.
The inspector discussed the control and monitoring of radiation exposur-with operators, RPM and licensee representatives and had no further gaestions.
b.
The inspector asked licensee representatives how radiation exposures were maintained be'ow the limits established in 10 CFR 20.101. Licensee representatives r tated that the exposure of each individual working in the Radiation Controlled Area (RCA) is t.pdated with pocket dosimeters information. The information is posted on the bulletin board near the change out area in the RCA. The information is presented by groups, e.g., health physics, instrumentation and control, maintenance, opera-tions nuclear, electrical, visitors and sub-contractors. The inspector noted the posting of the current radiation exposure report in the RCA, noted workers consulting the list, noted foremen consulting the list, and had no further questions.
8.
Exposure Review The inspector examined computer printouts of individual whole body and skin exposures for calendar year 1978.
The licensee is required by 10 CFR 20.101(b)(3) to have on file a Form NRC-4 icr each person who has exceeded the exposure limits of 10 CFR 20.101(a). The inspector examined records of those individuals whose yearly exposures indicated a potential for quarterly exposures in excess of the limits specified in 10 CFR 20.101(a) and verified that NRC-4 forms were included.
9.
Posting and Control a.
Posting The inspector observed the posting on bulletin boards throughout the plant of the notices and reports required by 10 CFR 19.11.
b.
Warning Signs The inspector toured the Radiation Control Area (RCA) and observed the posting of warning signs and the locking of access points to certain
o (b l
r b
.
-4-
.
The inspector took radiation level readings at selected locations areas.
and requested that air samples be taken at selected locations to assure that areas were posted and locked as required by 10 CFR 20.203 (c)(1) and Technical Specification 6.13, respectively.
Radiation Level Surveys c.
Th2 inspector discussed the radiation level survey program with licensee representatives. The inspector accompauied technicians and observed them making radiation level surveys. The inspector made confirmatory surveys of radiation levels. The inspector examined selected record:
of radiation level surveys inside Unit 3 containment and RCA for the period January 1 through May 5, 1979.
The inspector had no further questions.
10.
Training and Qualifications Technical Specification 6.3.1 states that "each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for compa rable positions." Section 4.5.2, ANSI N18.1-1971, states that technicians in responsible positions shall have a minimum of two years of working experience in their speciality, and that personnel should have a minimum of one year of related technical training in addition to their experience. A licensee representative stated that all shifts were assigned an H.P. supervisor with more than two years experience.
The inspector examined various persor.el files of members of the health physics staff as well as a number of
,ntract health physics technicians hired for the refueling outage. No i tems of noncompliance or deviations were observed.
11. Respiratory Protection Program By review of records, observations, and discussions with licensee representa-tives, an inspector evaluated the program for air sampling, bioassay, engineering controls, iiPC-hour controls, respirator medical evaluation, training, fitting, operational testing, maintenance, issuance controls, and determined that the respiratory protection program appeared to be in com-pliance with 10 CFR 20.103.
12. Surveys a.
The licensee is required by 10 CFR 20.201(b) to perform such surveys as may be necessary to comply with regulations. The inspector accom-panied by a licensee representative performed an independent contamina-tion survey of the decay beat pits. Twenty-one swipes were taken and counted. The inspector had no further questions.
b.
The licensee is required CFR 20.401(b) to maintain records showing the results of tb.
arveys.
The inspector examined the surveys for the first quart of calendar year 1979 and had no further questions.
n/7 O I_-
/ijJ JJ
.
.
-5-
-
13. Airborne Radioactivity Areas The inspecto; ceviewed tne records of airborne radioactivity levels.
CFR 20.203(f) requires that each airborne radioactivity area be conspicuously posted with a sign bearing the radiation caution symbol and the words
" CAUTION, AIRBORNE RADI0 ACTIVITY AREA'. The inspector observed that all identified airborne radiation areas were properly marked and had no further questions.
14. Bioassays Discussions with licensee representatives and examination of urinalysis and whole bcdy counting results for selected individuals for the first quarter of 1979 revealed that the licensee had established a bioassay program as required by 10 CFR 20.103.
Records for this period verified that body burdens of the most probable radionuclides for these individuals were well below maximum permissible body burdens.
The inspector had no further questions regarding the licensee's bioassay program.
15. Solid Waste Shipments The inspector reviewed the licensee's records for shipments of solid wastes from the site for the period September 1978 to May 1979.
The records revealed that on March 21, 1979, the licensee made a shipment, numbered 79-21 #1 and #2, of spent reactor coolant letdown pre-filters containing 276 Curies and 92 Curies respectively in shipping cask bearing a certificate of compliance number 9081. The inspector informed the licensee representa-tives that 10 CFR 71.12.b.ii requires that the licensee " complies with the terms of the... certificate," and further, condition 5.b of the certificate of compliance dated June 5, 1978, and in effect on the date of shipment, number 9081, limits the contents of the cask used to either " solid metals" or "ueutron sources in specia.1 form." and that the shipment of filters with radioactive sludge on them could not be shipped in the cask used. This is an itea of noncompliance (79-15-02).
a r
o<
'
iJ