IR 05000285/1989041
| ML19327C169 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/09/1989 |
| From: | Murray B, Ricketson L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19327C167 | List: |
| References | |
| 50-285-89-41, NUDOCS 8911210056 | |
| Download: ML19327C169 (14) | |
Text
p
.
..
..
..
.
.
.
,
'
.
l APPENDIX B i
[
U.S. NUCLEAR REGULATORY COMMISSION
-
REGION IV
NRC Inspection Report:
50-285/89-41 Operating License: DPR-40
Docket: 50-285 (
Licensee: Omaha Public Power District (OPPD)
i 444 South 16th Street Mall Omaha, Nebraska 68102-2247
.-
Facility Name:
Fort Calhoun Station (FCS)
L Inspection At:
Fort Calhoun Station. Fort Calhoun, Nebraska Inspection Conducted:
October 10-13, 1989 Inspector:
.
a
/b@
N-9- M LM. Picketspn, P.EG ' Radiation Specialist Date Fac11t' ties h 'diolo cal Protection Section
-
Approved:
ll4 @
l 8@
e D.Murray,ChieT,' Faci 1[tiesRadiological Dite' /
Protection Section Inspection Summary
Inspection Conducted October 10-13, 1989 (Report 50-285/89-41)
Areas Inspected: Routine, unannounced inspection of selected areas of the r
Ticensee's radiation protection (RP) program as set forth in the core inspection program (83750) as well as licensee action on previously identified findings.
'
Results: One violation involving the failure to use exit portal monitors was identified.
The licensee has made overall improvement in the RP area.
Increased management attention was evident by the implementation of a comprehensive audit of the RP program.
New office facilities and equipment, such as a thermoluminecent system, has been provided.
Considerable effort has been expended in the development and training on new RP procedures.
Staffing has been maintained at an adequate level and improvements were noted in radiation training L
activities.
Discussions were held with the licensee concerning methods to i-improve the tracking of certain RP information.
l'
lL 8911210056 891114
!
PDR ADOCK 05000285 O
!
L
7.+ -
.
,
..
..
.
.g.
f DETAILS l
1.
Persons Contacted OPPD
,
- K. J. Morris, Division Manager, Nuclear Operations
- R.
. Andrews, Division Manager Quality & Environmental Affairs
- G. Peterson, Manager, Fort Calhoun Station n
- J. P. Bobba, Supervisor, RP L
- D. L Lovett, Supervisor, RP Operations
- R. J. Sexton, Supervisor, Radiological Health and Engineering
K. E. Steele, Coordinator, Radiological Health M. S. Welch, Coordinator, Radiological Health t
C. R. Crawford, Coordinator, Respiratory Protection L. K. Haskell, Coordinator, Radiological Engineering
- C. J. Brunnert, Supervisor, Operations Quality Assurance (QA)
- C, F. Simmons, Station Licensing Engineer
- -
NRC P. H. Harrell, Senior Resident Inspector
'
- T. Reis, Resident Inspector The inspector also conducted interviews with technicians in the field.
- Denotes those present at the exit nieeting on October 13, 1989.
2.
Followup on Previous Inspection Findings (Closed) Open Item (285/8804-01):
Demineralizer Skid, Hoses, and
<
Connections - This item was previously discussed in NRC Inspection Report 50-285/88-04 in which the inspector noted that the licensee had not r
established a preventive maintenance / hydrostatic testing program for the temporary demineralizer skid. The licensee submitted documentation of results of the vendor's maintenance and testing program for the
'
inspector's review. A hydrostatic test was initially performed on the unit August 13, 1986, with subsequent tests performed August 18, 1987, and August 23, 1988. The vendor states that the system was tested to a pressure of 225 psi and such a test is performed each time a pressure point is broken. The licensee's actions appear adequate to resolve the NRC's concern regarding this item.
(Closed) Open Item (285/8805-09): Audits and Evaluations - This item was previously discussed in NRC Inspection Report 50-285/88-05 and involved the lack of a comprehensive audit program and the inability to identify weaknesses in the RP program.
In response to this item, the licensee employed a contractor with health physics experience to aid QA with the audit of the RP program conducted in April 1989 and subsequent
.
-
I'
s i,
.
.,
-
.
,
!
-3-
!
surveillances (see paragraph 5).
Several new surveillances were added to the "QA Surveillance List." Subjects of the surveillances included:
,
l RP surveillance surveys, contamination control, radiation work
'
permits (RWP)/ALARA, radioactive source receipt and control, respiratory equipment, health physics counting instrument operation, radioactive effluent release surveys, equipment calibration, and thermoluinescent dosimetry program.
To bolster ths QA department's expertise in health
.
physics and thereby effecting a longer range solution, a trained technician was transferred from RP to QA, effective July 1,1989, and, when trained, will be assigned to ::onduct audits and surveillances dealing with RP.
This individual was among those whose qualifications as RP technicians were verified during NRC Inspection 50-285/88-34. The licensee's actions appear to be adequate to address the NRC's concerns I
regarding this issue.
(Closed) Open Item (285/8805-13):
Respiratory Protection Program - This item was previously discussed in NRC Inspection Report 50-285/88-05 and involved the lack of a respiratory protection program meeting the
recommendations of Regulatory Guide 8.15 and NUREG 0041.
The licensee has estcblished a program for respiratory protection that meets the aforementioned guidance.
See paragraph 8, " Internal Exposure Controls,"
for details. The licensee's actions appear adequate to address the NRC's concerns regarding this item.
(Closed) Violation (28w8842-01):
Failure to Follow Procedures - This item was previously discussed in NRC Inspection Report 50-285/88-42 and involved the failure of licensee personnel to follow procedures related to intry into very high radiation areas.
Specifically, decontamination personnel entered into a very high radiation area around the reactor coolant drain tank without continuous health physics coverage as required by procedure. The individuals involved were suspended from work for 5 days.
DLpartment management discussed the matter with their personnel, emphasizing the importance of following procedures. A temporary fence was erected and remained around the area during the outage.
The licensee is evaluating the possibility of erecting a permanent barrier in the same place at the start of the next outape.
RP Procedure 204, " Radiological Area Controls," issued September 26, 1989, requires that a special RWP be issued for all entries into very high radiation areas.
It further requires that entrances to very high radiation areas shall be under constant control when personnel occupy such areas. The licensee's corrective actions appear adequate to prevent future violations.
(Closed) Violation (285/8904-01); (LER 285/89-05):
Failure to Follow Procedures - This item was previously discussed in NRC Inspection Report 50-285/89-04 and involved:
(a) the failure to follow the 2-man rule in a very high radiation area and (b) the presence of individuals in a high radiation area without an integrating dosimeter and without the
'
knowledge of the RP staff.
The licensee revised the applicable procedures, which are now RP-204, " Radiological Area Controls" and RP-500,
" Radiation protection Surveillance Program Administrative Procedure" to delete the 2-man rule for entry into very high radiation
--
,
..
.g l
'
-4-areas.
However, the procedures require that any individual or group of individuals entering into such areas be accompanied by a RP technician equipped with a dose rate mater. The net result is that anyone other than RP personnel requires constant accompaniment.
Following identification of item (b), licensee management de:ided to stop outage work and required all employees to attend briefings in which the incident was discussed and the need to follow procedures was emphasized. Personnel were required to attend a refresher training course before reentry into the radiological controlled area. The inspector reviewed the attendance records for the
-
meetings. Routine maintenance RWPs were rewritten to exclude high radiation areas and very high radiation areas, entry into which then
required special RWps. The two individuals involved in item (b) were required to complete training normally given to contractor junior l
RP technicians. The training consisted of both classroom and practical
,
training.
The licensee's corrective actions appear adequate to prevent
'
future violations.
,
(Closed) Violation (285/8904-02):
Inaccurate Whole Body Count Data - This item was previously discussed in NRC Inspection Report 50-285/89-04 and i
involved the reporting to terminated individuals of negative whole body
count results when, in fact, no whole body count had been performed. The licensee routinely indicated on Form FC-285 that "No detectable activity"
was discovered as a result of monitoring for internal contamination. As corrective action, the licensee is no longer relying on contractors to control dosimetry documentation. A radiological health coordinator, with
,
a staff of three personnel, has been assigned the responsibility for j
maintaining dosimetry records and transmitting notices to terminated
personnel.
New forms for reporting information to terminated personnel are included in RP-603, " Exposure Monitoring, Terminations, and Records,"
issued September 1, 1989.
The new forms indicate whether the individual followed the proper procedures when terminating (on FC-RP-603-1) and
' include a space for the date when the exit whole body count was conducted
,
,
(on FC-RP-603-4) as another check. An audit of the dosimetry records, by
,
contractors, continues.
The purpose of the audit is to identify all
records of workers with incomplete radiation histories and to ensure that all terminated employees receive a proper report of radiation exposure received while employed at the site.
The licensee's corrective actions appear adequate to prevent future violations.
L 3.
Licensee Event Report Followup
(Closed) LER (285/89-05):
Failure to Follow Procedure - See paragraph 2, Violation 285/8904-01.
4.
Inspector's Observations The following are observations the inspector discussed with the licensee during the exit meeting.
Inspector observations are not violations, deviations, unresolved f tems, or open items.
These observations were identified for licensee consideration, for program improvement, but have i
no specific regulatory requirements.
-
!
~_y
(-
' '.Q
, 2.
.
.
-5-J i
p
Manual Recording and Tracking of Information - The licensee did not (
have a computerized information and tracking system for use in access control, respirator issue, or dosimetry, as is common in the
F industry, Such a system could allow the RP department to verify the qualifications of individuals and update exposure records more quickly.
It could perhaps eliminate errors in record keeping brought
,
about by having.to repeatedly trenscribe exposure information by hand.
'
'
Respirators Overdue for Inspection - The inspector noted approximately five. full-face respirators on the storage rack at the
,
issue station tagged with dates which indicated that the routine inspection interval of 30 days had been exceeded. The inspector-
identified nothing to indicate that respirators overdue for inspection had been issued.
5.
Audits and Appraisal
-
'
The inspector reviewed the licensee's QA program with respect to areas related to RP to determine compliance with Appendix A of the Updated Safety Analysis Report (USAR).
As part of its Safety Enhancement Program, the licensee contracted for appraisals of its RP program.
The results of these appraisals, along with the findings of the NRC and the Institute of Nuclear Power Operation became the basis for the licensee's Radiation Enhancement Program.
The 1989 QA audit of RP focused on how well the suggested improvements in this area, or the Protection Improvement Plan, had been in plemented. The audit appeared to be comprehensive, identifying weaknesses associated with the lack of verification, validation, and field testing of procedures before implementation and the lack of appropriate training associated with some procedures.
The inspector reviewed the following QA surveillances:
Report No.
Subject Report Date C12-88-8 Thermoluminescent Dosimetry Program December 31, 1988 Cl-89-4 Radioactive Source Receipt and Control February 23, 1989 i
C2-89-1 Radiation Protection Surveillance March 3, 1989
.
I Surveys C2-89-2 Contamination Control March 3, 1989 H1-89-1 Radiation Protection Surveillance June 7, 1989 a
J L<
- _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _. _ _ _. _
_ _ _ _ _ _ _ _ _ _
,.
,
,
.
~*
-6-i
Surveys H2-89-2 Contamination Control June 7, 1989 H4-89-4 Radioactive Source Receipt and Control June 30, 1989
'
. H2-89-2 Contamination Control August 23, 1989 The surveillances appeared to be thorough and all identified deficient or unsatisfactory items. The 1989 audit and the surveillances were conducted with the assistance of a contractor with health physics experience.
A technician was transferred from RP to QA, effective July 1,1989, but had not, at the time of the inspection, begun to perform surveillances independently.
<
No violations or deviations were identified.
-
6.
Changes Numerous changes have been effected to the licensee's organization and operating procedures. The latest revision of the organizational structure.
(July 1989) as given in Section 12 of the USAR shows the RP department-divided into three groups:
Radiation Protection Operations, Radiological Health and Engineering, and Radioactive Waste Operations. The groups are further divided into programs as shown below:
Radiological Operations
Radiological Operations
RWP, Surveillance and ALARA Radiological Health and Engineering
"
Radiological Health
Respiratory Protection
"
.
Radiological Engineering
Radiological Instrumentation and Equipment Radioactive Waste Operations
Radwaste Operations Contamination Control The RP department is fully staffed.
The RP department is operating with essentially all new procedures, implemented in September 1989. An index to the RP procedures is attached to this report. The procedures reviewed by the inspector are noted.
_ _ _ _ _ _ _ _ _ - _ _ _ _ _
t
,
.
...-
..
,
.
.
.
-7-
7, External Exposure Control-
'The inspector reviewed the licensee's external exposure control program to determine compliance with FSAR commitments; 10 CFR Parts 19.13, 20.1, 20.101, 10.102, 20.104, 20.105, 20.202, 20.401, and 20.408 requirements; and the recommendations of RGs 8.2, 8.4, 8.7, 8.8, 8.14, 8.28, and ANSI
.(
. N13.11-1983, N13.27-1981, N319-1976.
The licensee has installed a new dosimetry system which uses 4-element thermoluminscent dosimetry and will allow the licensee to apply for accreditation from the National Voluntary Laboratory Accreditation Program
,,
t (NVLAP) in' all categories, Until NVLAP accredation is obtained..the licensee has received reaccreditation, in compliance with 10 CFR 20.202(c),
on its old system in Categories 2, 4, 5, 7, and 8.
The licensee will have approximately 6000 TLDs with the new system, doubling the number available of the old type.
The inspector noted that exposures did not exceed
.
10 CFR 20.101 limits.
The procedures reviewed by the inspector are shown on the attachment to this report.
No violations or de';iations were identified.
8.
Internal Exposure Control The inspector reviewed the licensee's program for control of internal radiation exposure to determine compliance with commitments in the FSAR; the requirements of 10 CFR Parts 20.103, 20.201, 20.203, 20.401; and the recommendation of RGs 8.2, 8.7, 8.8, 8.9, 8.15, 8.20, 8.26, and 8.27; and ANSI N343-1978 and NUREG-0041.
The inspector reviewed Standing Order T-11 which contains the licensee's respiratory protection policy statement and was found to be in accordance
!
with the guidance in Regulatory Guide 8.15.
The licensee has a system for cleaning respirators and can perform fit testing by use of a fit booth or tabletop fit testing unit.
A pulmonary tester was purchased, but has not been used, because the licensee elected
to contract with a local clinic to provide full physicals.
- The licensee is currently not reusing filters nor using supplied air respirators.
(The Procedures RP-503, "Use of Compressed Air for Supplied
- ..
Air Respirators and RP-506, " Respirator Filter Testing" had not been implemented at the time of the inspection.)
Respirators are issued by RP technicians at access control 'eho verify that individuals are qualified (by checking the user cards issued to qualified individuals) and are on a valid RWP. The inspector interviewed technicians on duty at the issue facility and verified that they were knowledgeable of the respiratory issue procedur L 0.
)..
..
L
'
,.
t
.
8-s L
The licensee fills self-contained breathing apparatuses from air bottles r
purchased from a vendor.
The inspector verified that the licensee obtains
'
certification from the vendor that the air meets ANSI Z86.1-1973 Grade D quality standards.
The inspector reviewed the licensee's whole body counting program results to' evaluate the effectiveness of the respiratory protection program.
In addition to the. initial and termination whole body counts, whole body counts are performed at random on individuals selected from the list of respirator users. There have been no cases of internal contamination identified this year.
Th'e procedures reviewed by the inspector are shown on the attachment to this report.
,
No violations or deviations were identified.
9.
Control of Radioactive Materials and Contamination, Surveys, and Monitoring The licensee's programs for the control and survey / monitoring of radioactive materials were reviewed to determine. agreements with commitments in the FSAR and compliance with requirements of 10 CFR Parts 19.12, 20.201, 20.203, 20.205, 20.207,-20.301, and 29.401.
The inspector reviewed randon, survey records of various areas in the radiologically controlled area (RCA) and verified that they had been conducted ac(ording to the established schedule.
The inspector performed independent radiation measurements and verified that areas were posted correctly and doors to very high radiation areas were locked.
,
l The inspector noted that there were 16 routine RWPs.
None allowed
>
entrance into high radiation areas, very high radiation areas, airborne
!
radiation areas, or highly contaminated areas.
Special RWPs are required for entry into these areas.
!
l The inspector observed individuals as they removed protective clothing at j
,
the exits of contaminated areas and noted they followed proper undressing
!
procedure.
l Technicians were interviewed concerning their training and understanding of the new procedures.
All seemed to be knowledgeable of the procedures
-
discussed.
Several also stated that there were still many detail l
refinements which needed to be made in many pre::edures. The RP supervisor acknowledged this and stated that it was expected and was being performed.
The resident inspector informed the inspector that on September 26, 1989,
)
a group of approximately 40 visitors were allowed to bypass a radiological frisking station set up at the protected area egress.
The RP supervisor l
confirmed the occurrence, stating that all portal monitors were out of service, perhaps aue to a lightning strike, and that the frisker i
,
~
i I
>
'*
..
i
,
-9-U
,
p station was set up as an alternate. The supervisor further stated that he E
had been contacted by security when the group was ready to leave the site
,
and that an evaluation of the situation was performed by RP.
Because he
,
knew the areas in which the visitors had been, the RP supervisor made the L
decision that the exit frisk was not necessary.
However, Standing Order i
No. G-76, requires that all personnel exiting the restricted area via the security building will use the portal monitors. Becatse the visitors were not required to use the alternate method of checking for contamination upon exiting the restricted area, this was identified by the inspector as
.
!
an apparent violation of TS 5.8.1, for failure to follow procedures set
'
forth in the standing order.
(285/8941-01)
,
The procedures reviewed by the inspector are shown on the attachment to this report.
No deviations were identified.
"
l 10.
Exit' Meeting The inspectors met with the resident inspector and the licensee's representatives deroted in paragraph 16t the conclusion of the inspection
,
on October-13, 1989, and summarized the scope and findings of the
!
inspection as presented in this report. The licensee did not identify as proprietery any of the materials provided to, or reviewed, by the. inspector during the inspection.
!
,
--
FORT CALHOUN~ STATION
PAoE 1 Or
~,
,
.s
..,
,
.,
.,i RADIATION PROTECTION
.;-
RADIATION PROTECTION INDEI f
-
i
' PROCEDURE TITLE / DESCRIPTION REVISION /DATI
.
L
- RP-201 Radiation Work Permits R0 09-01-89
- RP-202 Radiological Surveys R1 09-26-89
,
RP-203 Air Sample Collection and Analysis R0 09-01-89 r
'
- RP-204 Radiological Area controls R1 09-26-89
- RP-205 MPC-Hour Tracking RO 09-01-89
,
- RP-206 Radioactive Material Handling R2 10-10-89
- RP-207 Personnel Monitoring and Decontamination RO 09-01-89
,
RP-208 Radiography'
RO 09-01-89-
- RP-209 Hot Particle Program RO 09-01-89
'
RP-210 Primary Side Steam Generation Entries RO 09-01-89
'
-j RP-211 Steam Generator Sludge Lancing R1 09-26-89
,
RP-212 Diving Operations Within Radiologically Controlled Areas R1- 09-26-89
- *RP-301 ALARA Job Reviews R0 09-01-89 RP-303 ALARA Cost-Benefit Analysis RO 09-01-89
,
RP-304 Radiological Goals Program,
R0 09-01-89 t
RP-305 ALARA Suggestion Program R0 09-01-89
'
l RP-306 Hot Spot Identification and Tracking R0 09-01-89 RP-307 Use and Control of Temporary Shielding R1 09-26-89 4,
.-
RP-308 Radiological Assessments R1 09-26-89
L RP-401 Issue, Control and Accountability of ll Radiation Protection Instrumentation RO 09-01-89 RP-402 Calibration and Test Requirements for Radiation Protection Equipment RO 09-01-89 RP-403 Portable Survey Tnstrument Response Testing RO 09-01-89 L
- Procedures reviewed by the inspector
,
- - -,
c,- -.......,,...., - -, - - -., -,
,
,,, -, -,
-. - - -,,
-,, _ -,, - -...., - -. - - -, - - -,,.,, - - - -
,
_
__
_ _ _ _ _ _.
_
i
- , FORT,CALH"UN STATION
.
&
PAGE 2 OF 5
'
'
-
RADIATION PROTECTION
,
RhDIATION PROTECTION INDEZ
,,
PROCEDURE TITLE / DESCRIPTION REVISION /DATE RP-404 Quality Assurance of Counting Systems and
'
Portable Counters RO 09-01-89
'
RP-405 Radioactive Source Inventory Control RO 09-01-89
"
RP-410 Operation of the Eberline Model RO-2/RO-2A
.
"
Survey Meter RO 09-01-89'
- RP-411 Operation of the Eberline RO-7 Ion Chamber R0 09-01-89 RP-412 Operation of the Bicron RSO-5/50/500 Series Ion Chamber Survey Meters RO 09-01-89
RP-415 Operation of the Eberline Model E-120/E-520/
E-530 G-M Survey Meter RO 09-01-89
RP-416 Operation of the Eberline 6112B Teletector RO 09-01-89 l
RP-417 Operation of L1cron GM Survey Meters Models Tech 50, Surveyor 50 and Surveyor 2000 RO 09-01-89 RP-419*
Operation of the Eberline ASP-1 with NRD L
Rem Ball RO 09-01-89-RP-420 Operation of Ludlum and Eberline Count Ratemeters Using External Pancake GM Probes R0 09-01-89 RP-421 Operation of the Ludlum Model 12 count Ratemeter Model 43-20 160 cm2 Probe RO 09-01-89 l
l; RP-422 Operation of the Xatex Alarming Dosimeter R0 09-01-89 l
RP-423 operation of the Eberline PAC-4G-(3) Alpha
,
Counter R0 09-01-89 RP-424 operation of the Xetex Teledose Model 503A Telemetry System RO 09-01-89 I
~
RP-425 Operation of the Dositec Model DR-24 Portable i
Remote Monitor RO 09-01-89
-
RP-426 Operation of the Dositec Model PR-2L Portable Remote Monitor R0 09-01-89 RP-427 Operation of the DCA Area Monitor Model 3090-3 RO 09-01-89 RP-428 Testing and Verification of Self-Reading Dosimeters RO 09-01-89
l-
- -
. -
..-
-
..
....
-
.
.
_
.
__
._
>
'
%~
FORT CALHOUN STATION PAGE 3 OF !
RADIATION PROTECTION
.
RADIATION PROTECTION INDEI
'
.
l PROCEDURE TITLE / DESCRIPTION REVISION /DATE'
1; p
'RP-430 Operation of Low Flow Air Samples F and J
'
Models, LV-1 and LV-14M R0 09-01-89
,,
j RP-431 Operation of the Radeco Model H-809 Air
Sampler R0 09-01-89
.
i
'RP-432 Operation of the Gillan Model HFS 513A UC r
'
Lapel Sampler R0 09-01-89
!
i RP-440 Operation of the Eberline Models AMS-2 and AMS-3 Beta Air Monitors R0 09-01-89
- RP-441 Test and Operation of the PING-1A Constant Air Monitor R0 09-01-89'
RP-445 Operation of the Victoreen Model 570 Condenser R-Meter Gamma Source Exposure Rate.
Verification R0 09-01-89 RP-450 Operation and Response Check of the Eberline Model BC-4 Beta Counter R0 09-01-09 RP-451 Response Testing and Operation of the Eberline SAC-4, Scintillation Alpha Counter R0 09-01-89
,
,
RP -453 Operation of the Tennelec LB 5100 Series
'
II/III Alpha and Beta Counting System R1 09-29-89
'
RP-454 Operation of the Canberra Gamma Spectroscopy
<
System RO 09-01-89
,
- RP-456 Testing and Operation of the NNC Gamma 10
'
,
Portal Monitor R0 09-01-89
.;
- RP-457 Test and Operation of the Eberline Personnel I
Contamination Monitor (Model PCM-1)
R1 09-05-89
- RP-501 Description and Eelection of Respiratory Protection. Equipment R0 09-01-89
- RP-502 Use of Respiratory Protection Equipment R0 09-01-89
- RP-504 Respirator Fit Testing - Dynatech R0 09-01-89
- RP-505 Issue and Control of Respiratory Protection Equipment R0 09-01-89
- * RP-5 0
Inspection and Maintenance of Respiratory Protection Equipment R0 09-01-89 Procedures reviewed by the inspector
......
.
.
.
...
-
..
.
.
..
~
~
~
,qg.
.
- z F8RT CALHOUN' STATION PAGE 4~OF 9 I
.,.
,
.
,
R&DIATION PROTECTION
'l
,
RADIATION PROTECTION INDEI
?
r
'
PROCEDURE TITLE / DESCRIPTION
-
REVISION /DATE ORP-508 Respirator Face Geal Testing RO 09-01-89
,
ORP-509'
Quantitative Condensation Nucleus Counter R1 09-07-89.
RP-510 Operation of Respirator Cleaning Equipment RO 09-01-89
$
,
ORP-511 Recharging of SCBA Cylinders R0 09-01-89 dRP-601 External Dosimetry Program R0 09-01-89 RP-602 Perronnel Dosimetry Issuance RO 09-01-89 QRP-603 Exposure Monitoring Terminations and Reports RO.09-01-89
'
RP-604 Authorizing Administrative Exposure Limits Increases RO 09-01-89
-RP-605 Exposure Evaluation Reports RO 09-01-89-RP-606 Special Dosimetry Issuance, Control and Use RO 09-01-89.
[
RP-607 Dosimetry Changeout and Dose Updating RO 09-01-89
,
cRP-608'
Skin Dose Calculations RO 09-01-89
RP-609'
Monitoring of Visitors in Radiologically Controlled Areas RO 09-01-89 RP-610 Alternative Radiation Worker Qualification RO 09-01-89 RP-631 Calibration of the.Panasonic Up 716A TLD Reader System'
RO 09-12-89
)
RP-632 Operation of the Model WE-2001 PC Irradiator RO 09-01-89-
'
RP-634 Routine-Quality Control of the Panasonic TLD
Reader System.
R0 09-12-89 RP-635 Dosimeter Receipt and Inspection RO 09-01-89
.RP-636 Calibration of Panasonic TLDs RO 09-12-89 ORP-638 Processing Panasonic TLDs R0 09-12-89
'
RP-640 Cleaning the Panasonic Model UD-716A TLD
'
Reader RO 09-12-89 RP-641 Annealing TLD Badges RO 09-01-89
,_oRP-650 Internal Dosimetry Program RO 09-01-89 CProcedures reviewed by the inspector
.
,.. _ _. - _ _._
_ _..
__
..
.
.
.
.
-
11 >
17 :.. FORT,CALHOUN STATION PAGE 5 OF 5
'
[
- l, '
RADIATION PROTECTION s
RADIATION PROTECTION INDRI i
F p
PROCEDURE TITLE / DESCRIPTION REVISION /3 ATE
'i
,
,
RP-651 Routine Operation of the FastScan Whole i
Body Counter R0 09-01-89 RP-652 Calibration of the FastScan Whole Body l
'
Counter R0 09-01-89
,,
..
oRP-655 In-Vitro Bioassay Sampling R0 09-01-89 0 RP-656 Bioassay Calculations RO' 09-01-89
'RP-657 Bioassay Quality Control Measures R0 09-01-89
'
,
RP-660 Verification of J.L. Shepherd Model 142-10 i
Panoramic Irradiator R0 09-12-89 RP-661 Calibration of the Harshaw Model 2271 TLD l
Reader Picoammeter System.
R0 09-12-89.
.
RP-662.
Annealing and Issuing TLD Cards R0 09-12-89 RP-663 Source Procedures.for Irradiating TLDs R0 09-12-89
RP-664 Quality Control / Test Badges R0 09-12-89
-
T
RP-665 Determining TLD Gamma Sensitivities and Selecting.
R0 09-12-89
l-
.RP-666 Dose Calculations for TLD Specials R0 09-12-89 RP-667 Reading TLD Cards R0 09-12-89 I
'
RP-668'
Monthly TLD Report R0 09-12-89 o
RP-901 Radiation Protection Program Effectiveness
.
Reports R0 09-01-89
.
RP-902 Trending of Routine Survey Dr.ca R0 09-01-89 RP-903 Radiological Occurrences Reporting and
-
Trending R0 09-01-89
+
~oRP-904 Radiological Work Practices Program R0 09-01-89 oRP-905 Control Area Work Restrictions R0 09-01-89
,
OProcedures reviewed by the inspector
>
$
i
.
.-
.
.
.
.
...
.
...
..
.
.