ML20141C942
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| ML20141C942 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/18/1986 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20141C925 | List: |
| References | |
| 50-285-86-01, 50-285-86-1, GL-81-38, GL-81-389, GL-85-14, IEB-79-19, IEIN-83-10, IEIN-84-14, IEIN-84-50, IEIN-85-092, IEIN-85-92, NUDOCS 8604070351 | |
| Download: ML20141C942 (17) | |
See also: IR 05000285/1986001
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APPENDIX
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-285/86-01 License: DPR-40
Docket: 50-285
Licensee: Omaha Public Power District (0 PPD)
1623 Harney Street
Omaha, Nebraska 68102
Facility Name: Fort Calhoun Station (FCS)
Inspection At: FCS Site, Washington County, Nebraska
Inspection Conducted: January 6-10, 1986
Inspector: b ' dlbb 7)'llL4tfd/ W8h6
Date
H.~Chaney,Radl5 tion /pecialist,
3 Facilities Radiological Protection
Section
Approved: / b E 7 N /Jffh/ /[[htb
Oate'
B. Murray, Chi ~et, Fadilities Radiological
~
Protection Section
Inspection Summary
Inspection Conducted January 6-10, 1986 (Recort 50-285/86-01)
Areas Inspected: Routine, unannounced inspection of the licensee's radiation
protection program, low-level radioactive solid waste (LLRW) program, and
transportation of radioactive materials (RAM). The inspection involved
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46 inspector-hours onsite and 7 inspector-hours offsite by one NRC inspector.
Results: Within the areas inspected, four apparent violations (see paragraphs
8, 9 and 10) and no deviations were identified.
8604070351 G60327
PDR ADOCK 05000285
G PDR
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DETAILS
j 1. Persons Contacted ! OPPD i *R. L. An'drews, Division Manager-Nuclear Production
*W. G. Gates, Manager, Fort Calhoun Station
*R. L. Jaworski, Section Manager-Technical Services
*F.' F. Franco, 'Section Manager-Radiological Health and Emergency
Preparedness
*C. J. Brunnert, Supervisor Operations Quality Assurance (QA)
~
*K. Stultz, Technical Services
, *G. L. Roach, Supervisor-Chemical and Radiation Protection (CRP) '
*F. K. Smith, Plant Chemist
*A. Bilau, Radioactive Waste Coordinator
*J. M. Mattice, Plant Health Physicist
B.' Wentworth, Quality Control (QC) Inspector
J. M. Hale, CRP Technician Coordinator '
D. A. Jacobson, CRP Training Instructor
J. Carlson, Administrative Clerk
R. A. Cords, CRP Technician .
J. J. Fisicaro, Supervisor-Nuclear Regulatory and Industry
Affairs
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C. R. Crawford, ALARA Coordinator
,
J. E. Bentzinger, General Office QA
j T. J. McIvor, Supervisor Technical Services
t
Others
- D. Whitlock, Contract CRP Technician
l -
P. Harrell, NRC Resident Inspector ~
[ The NRC inspector also interviewed other licensee and contractor employees
including CRP, administrative, maintenance, and QA/QC personnel.
i " Denotes those individuals present during the exit interview on '
January 10, 1986.
2. Licensee Action on Previously Identified Inspection Findings
! . (Closed) Violation (285/8010-01): Failure to Survey - This item was
previously discussed in NRC Inspection Report 50-285/80-10 and involved
the failure to perform a monthly radiation survey in-room 15A of the
reactor auxiliary building (RAB). Selected licensee survey records for
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room 15A were reviewed and it was determined that the licensee had been
surveying room 15A at an adequate frequency during 1985. This item is
considered closed.
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(Closed) Open Item (285/8226-15): NUREG-0737, Item II.F.1-1, High Range
Noble Gas Effluent Monitor - This item had remained open pending licensee
action to complete installation and testing of the instrumentation.
Radiation Monitor (RM) 063 had been installed and appears to satisfy the
requirements of NUREG-0737. This item is considered closed.
(Closed) Open Item (285/8226-18): NUREG-0737, Item III.D.3.4,
Modifications for Control Room Habitabi1ity - This item had remained open
pending the licensee's completion of modifications to satisfy NUREG-0737
requirements. The licensee had completed installation of: (1) additional
radiation shielding in the west side wall adjacent to the control room,
(2) iodine monitor RM-65, and (3) toxic chemical monitors. All monitors
are considered operational. This item is considered closed.
(Closed) Violations (285/8303-01) & (285/8502-05): Radiation Hot Spot
;
Posting - The NRC inspector reviewed licensee corrective actions to
resolve the failures to properly post radiation hot spots. The licensee
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had: (1) provided for review of procedures by HP technicians, (2) revised
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health physics procedures to eliminate conflicting requirements, and
(3) more clearly state hot spot posting requirements. Inspections of the
i licensee's facility did not identify any problems with hot spot posting. ,
This item is considered closed.
,
I (Closed) Violation (285/8331-01): Review of Radiation Work Permits - The
NRC inspector reviewed 10 radiation work permits (RWP) and found all had
- been properly reviewed per procedure RPP-20 which now requires a monthly
- review for certain RWPs. This item is considered closed.
(Closed) Violation (285/8502-01): Radiation Protection Instructions to
Workers - The licensee had issued special instructions on selected
training topics concerning radiological protection for badged personnel.
- The licensee's training outlines and procedures were revised also to
ensure all personnel entering the protected area (i.e., restricted area)
received the training required by 10 CFR Part 19.12. This item is
! considered closed. I (Closed) Violation (285/8502-02): NRC Form 4 - The licensee had taken
corrective action to have all NRC Form 4s tilled out in their entirety.
A review of radiation exposure records did not identify any NRC Forms not
properly filled out. This item is considered closed.
. . (Closed) Violation (285/8502-03): NRC Form 5 - The licensee had taken
corrective action to use a form that was equivalent to the NRC Form 5 to
track quarterly exposures of workers. This item is considered closed.
3. Inspector Observations
j
The following are observations the NRC inspector discussed with the licensee
- during the exit interview on January 10, 1985. These observations are
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neither violations nor unresolved items. These items were recommended for
licensee consideration for program improvement, but they have no specific
regulatory requirement. The licensee did not provide any specific comment
for these items,
a. Supervisor Review of Work Areas - The NRC inspector noted during
interviews witI workers that a general theme was expressed concerning
the lack of C' supervisor tours of job site and ongoing work and
conditions within the controlled areas, i.e., RAB and containment
during outages. See paragraph 4.
b. Release Limits for Potentially Radioactive Material - The NRC inspector
noted that the licensee's orocedures could allow for the release of
materials to unrestricted areas with radioactive contamination levels
above those referenced in recent NRC Information Notices. See
paragraph 10.
c. Coordination and Documentation of Training - There appears to be a
lack of general knowledge in the CRP group in regards to who is
responsible for the development of training, conduct of training, and
of ensuring that training records.are properly documented. See
paragraph 5.
4. Radwaste/ Transportation Program Organization and Management Controls
The NRC inspectors examined the licensee's organization and staffing to
determine compliance with the Updated Safety Analysis Report (USAR) -
Sections 11 and 12; NRC Inspection and Enforcement (IE) Bulletin 79-19;
10 CFR Parts 20, 50, and 71; Facility Operating License Technical
Specifications (TS) 2.9.2, 5.2.2, 5.8, 5.9.4, and 5.10.1; and the
recommendations of NRC Regulatory Guides (RG) 1.33, and 1.8, and NRC IE
. Information Notices 83-10 and 84-50.
The NRC inspector reviewed the staffing of the CRP group Radioactive Waste
Coordinator (RW/C) position, compared staf fing to TS requirements and the
work load involving solid RW management and transportation activities.
The NRC inspector determined that the RW section was responsible for
oversight of contractor solidification services, compaction of dry active
waste (DAW), preparation of RAM and waste for shipment, and general RP
duties associated with RW operations.
,
The NRC inspector reviewed the licensee's operating procedures for RW
activities. The NRC inspector noted that the licensee had prepared a
waste stream characterization and analysis program for compliance with
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10 CFR Part 61 requirements. The NRC inspector reviewed the procedures
used by a contracted LLRW solidification service vendor and the licensee's
controls over changes to those documents. The licensee's burial site
contracts, DOT /NRC regulations, and package user manuals were found to be
up to date.
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The NRC inspector reviewed QA audits and surveillances of RP, RW, and
transportation ac ivities, and determined that they were carried out in
accordance with Q manual requirements. The deficiencies noted in license
QA audits were re olved in an effective and timely manner. The licensee's
QC program for tr nsportation activities was reviewed and found to be
comprehensive and well documented.
During interviews with various RP and other FCS employees, it was determined
that there appears to be a concern on the part of some employees that CRP
group supervisory personnel were not aware of activities and employee
conduct within radiologically controlled areas, and that CRP supervision
did not appear to be conducting tours of radiological work areas within
the RAB and reactor containment. A review of 1985 CRP supervision exposure
records and access key card reader entries for accesses leading into the
RAB confirmed-that only a few entries had been made via the routine RAB
access door, and when added to the very little exposure being acquired by
key supervisory personnel is indicative of infrequent tours of radiological
work areas. This concern was brought to the attention of the licensee
during the exit meeting and a subsequent telephone conversation between
the NRC inspector and plant manager on February 3,1986.
No violations or deviations were identified.
5. Radwaste/ Transportation Organization Staff Qualifications and Training
The NRC inspector examined personnel qualifications to determine compliance
with NRC IE Bulletin 79-19, USAR Section 12, 10 CFR Parts 19.12 and
71.105(d), and TS 5.3, 5.4, and 5.10.2; and the recommendations of RGs 1.8,
8.2, 8.8, 8.27, and NUREG-0761.
The NRC inspector reviewed position descriptions, training records,
training outlines, special training announcements, training attendance
,
rosters, and discussed the qualifications and training activities of
personnel performing LLRW processing and transportation activities with
licensee representatives and contracted personnel.
The NRC inspector determined that CRP personnel associated with LLRW
activities had received periodic training by offsite vendors; however, the
records of such training were found to be fragmented and difficult to
retrieve. Tentatively scheduled offsite LLRW management and DOT /NRC
transportation training for RW workers was also reviewed. During discus-
sions with licensee personnel in the training and CRP groups, it was
determined that scheduling of specialized RW training and conduct of
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training was not being provided sufficient attention. The NRC inspector
identified to licensee representatives at the exit meeting that RW training
of CRP personnel needs additional attention to ensure that annual training
commitments (licensee response to NRC IE Bulletin 79-19) are not compromised.
No violations or deviations were identified.
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6. Low-level Radioactive Waste Management Program
The NRC inspector reviewed the licensee's program for the control,
classification, characterization, and shipment of LLRW to determine
compliance with the commitments contained in Section 11.1.4 of the USAR;
and the requirements contained in 10 CFR Parts 20.301, 20.311, 61.55, and
61.56; and TS 5.9.4; and the recommendations of NRC branch technical
position (BTP) papers on LLRW classification and waste form.
The NRC inspector reviewed the licensee LLRW process control program,
implementing procedures, LLRW processing areas, documents on processed
LLRW, and QA/QC aspects of processing LLRW. The licensee had elected not
to use or make operational the permanently installed LLRW solidification
system (see Section 11.1.4.1 of the USAR) in the plant, but is having wet
wastes solidified / processed by a contracted service. The contracted
service uses an NRC approved process. The licensee's procedures for
sampling of waste streams within the plant and results of radionuclides
analyses were reviewed. The NRC inspector determined that the licensee
had tentatively scheduled a QA audit of the offsite laboratory that
performs certain analyses to be conducted during March 1986. The
licensee's scaling factors are a combination of generic Combustion
Engineering factors as modified by OPPD for site-specific conditions.
The NRC inspector noted that licensee scaling factors are routinely adjusted
based on in-house radiochemistry analyses involving correlation factors
for cesium and cobalt radioisotopes. The offsite laboratory analyses are
used to verify hard to analyze radionuclides (transuranics and strontiums).
LLRW shipment records contain all the information required by 10 CFR
Part 20.311.
The NRC inspector noted that the licensee had only been solidifying liquid
waste concentrates for disposa?. Current chemistry and operational condi-
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tions have sharply reduced the depletion -, demineralizer resins. Also,
the licensee is currently segregating DAW and has realized a fifty percent
reduction in DAW requiring disposal as LLRW. That DAW being identified as
not radioactively contaminated is being controlled and not released until
further radiological surveys can be performed using more sensitive analysis
equipment as referenced in NRC IE Information Notice 85-92.
The NRC inspectors reviewed the licensee's somiannual Radioactive Effluent
Release Report, documented changes to the solid radwaste system, and PCF
procedure changes submitted to the NRC per TS 5.9.4 for 1985.
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The NRC inspector reviewed the licensee's records of LLRW shipped from FCS
since 1981. The following table shows the total volume for the period 1981
through 1985:
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Volume
Year {CubicMeters)
1981 253
1982 342
l - l 1983 465
1984 450
l- 1985 343 l No violations or deviations were identified. ! l
7. Onsite Low-Level Radioactive Waste Storage
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The licensee's onsite low-level radioactive waste storage facilir.ies were
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reviewed for compliance with the guidance provided in NRC Generic Letters
81-38 and 85-14; the licensee's commitments contained in Section 11.1.4.4
of the USAR: and the information contained in NRC IE Circular No. 80-18.
The NRC inspector determined that the licensee had prepared interim
engineering plans for using an onsite warehouse for storage of select LLRW.
However, these plans are being held in abeyance until a national LLRW
program is determined.
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No violations or deviations were identified.
Radioactive Material Transportation Program
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The NRC inspector reviewed the licensee's radioactive material transportation
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program for compliance with the requirements of TS 2.9.2 and 5.10.1.g,
l 10 CFR Part 71, DOT regulations 49 CFR Parts 171 through 178, and NRC I&E ,
Bulletin 79-19, and the recommendations of I&E Notices 83-10, 84-14, and
! 84-50, NRC Regulatory Guides (RGs) 7.1 through 7.10.
The NRC inspector reviewed selected records of RAM /LLRW shipments made by
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the licensee. The licensee made approximately 61 shipments during 1985.
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The shipments primarily consisted of either LLRW shipped as low specific
l activity (LSA) via sole use carrier or equipment and/or items shipped as I
limited quantities. The NRC inspector determined that no LLRW shipped as
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LSA exceeded A, quantities. The NRC inspector specifically reviewed the
following areas of the RAM shipping / transportation prog,am:
a. Audits and Appraisals - Onsite QA Audits, onsite surveillances, and
audits conducted by the OPPD General Office Safety Audit and Review
Committee (SARC) were reviewed (see the Attachment to this report on
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documents reviewed) and found to be comprehensive and conducted in
-accordance with FCS QA manual. Audits involved both the control over
procurement and receipt inspection of packagings, and the conduct of
the RAM receipt and transportation program. The last audit of RAM
transportation activities was September 1984. The next audit is
tentatively scheduled to be performed in 1987. Onsite QA
surveillances of RAM shipping is routinely performed.
b. Procedures - Licensee procedures for the preparation, inspection, ~
loading, closing, curie content determination, labeling, and
preparation of shipping papers foi radioactive material were reviewed
and found to be maintained current and adequate. See the Attachment
to this report for procedures reviewed,
c. Procurement and Reuse of Packagings - Licensee procurement prcedures,
receipt inspection, and QA program for compliance with 10 CFR Part 71,
Subpart H were reviewed. The licensee routinely uses QA and QC
checklists for the receipt inspection and loading of packages.
d. RAM Shipments - Fifteen shipments of RAM /LLRW were reviewed for
compliance with the requirement of 00T and NRC for such shipments.
e. Transportation Incidents - The NRC inspector determined on January 7,
1986, while reviewing transporation incident reports that the licensee
was notified by an offsite laboratory on or about October 14, 1985,
that radicactive contamination above the DOT limits was found on a
valve (MS-280) shipped on October 9, 1985. The licensee subsequently
determined that the valve contained approximately 0.46 uct of loose
radioactivity within the valve and about 8 uci of activated radio-
activity. The shipment of the valve as non-radioactive material is
an apparent violation of, 49 CFR Part 171.2(a) and 173.423 and 10 CFR
Part 71.5(a) requirements (285/8601-01).
f. Registration of Use of NRC Certified Packagings - The licensee was
found to be a registered user of NRC certified packages used to ship
RAM from FCS. Registration was being maintained on other packages
not routinely used.
g. Quality Assurance Program - The licensee maintains a program for
ensuring that the QA program for RAM shipment packages referenced in
10 CFR Part 71, Subpart H, was being complied with.
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h. Preparation of Packages for Shipment - The licensee's records for
shipment of RAM show that packages were inspected for quality of
construction and integrity, free standing liquids, package markings /
labeling, and that comprehensive radiation and contamination surveys
were performed. The NRC inspector observed the preparation and
packaging of a solidified liner of waste concentrates for shipment to
a LLRW burial site. Independent radiation measurements of the package
was made by the NRC inspector.
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i. Delivery of Completed Packages to Carriers - The NRC inspector
reviewed licensee records of RAM shipments, including LSA shipments
and determined that loading, bracing, use of tamperseals, placarding,
advanced notification, and providing instructions on maintenance of
sole use conditions was adequate.
j. Periodic Maintenance of Packagings - The licensee does not routinely
perform maintenance on packages, but does keep adequate records of
maintenance performed by the package vendors. The NRC inspector
specifically verified that annual replacement of lid seals on certain
reusable packages was performed by the package vendor,
k. Records and Reports - The NRC inspector reviewed general records,
QA/QC records, and RAM shipment reco.rds for 1984 and 1985 and
verified proper records of QA/QC activities, shipment manifests,
radiation and contamination surveys, certification of compliances,
semi-annual reports of transportation and LLRW activities, and
evaluation of 00T specification packaging compliances.
No deviations were identified.
9. External Radiation Exposure Control
The licensee's RP program was reviewed for compliance with the commitments
contained in the USAR - Section ll, the requirements of TS 5.11, and
10 CFR Parts 19.12, 19.13, 20.101, 20.102, 20.104, 20.105, 20.202, 20.203,
20.205, 20.206, 20.405, 20.407, 20.408, and 20.409.
The NRC. inspector reviewed licensee personnel radiation exposure records
for implementation of the corrective action taken by the licensee in
regards to Notice of Violation 285/8502-04, which involved the licensee's
failure to notify terminated individuals of their radiation exposure
- received while at FCS as required by 10 CFR Part 20.409. The NRC inspector
reviewed, with the licensee during the entrance meeting of this inspection,
a radiation exposure termination report sent from FCS to the NRC inspector
on August 31, 1985, (OPPD Serial No. FC-C-050-85) approximately 5 months
fc110 wing the inspectors last visit to FCS (March 8, 1985). On January 7,
1986, the NRC inspector determined that the exposure termination report
sent to the NRC inspector was not processed within the time period set
forth in 10 CFR Part 20.409, which is identical to the violation referenced
in NRC Inspection Report 50-285/85-02. Further investigation by the
licensee determined that, additionally, termination reports for approximately
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30 temporary employees had not also been processed within the required
tire period. The failure to provide timely reports of radiation exposure
is an apparent repeat violation of 10 CFR Part 20.409 (285/8601-02).
The licensee's TS 5.11.2 requires that radiation areas above 1000 mrem /hr
be controlled by posting and use of locked doors to prevent unauthorized
entry into such areas. The NRC inspector determined on January 8, 1986,
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that a posted very high radiation area within Room 27 of the RAB was not
being controlled by locked doors even though lockable doors were present.
The licensee considered the area to be exempt from locking (per TS 5.11.2.a)
, due to the additional ef fort that would be necessary to provide locking
devices on the entry doors (one was a sliding door and the other was a
standard door with a keyed locking mechanism) and the relative : size of the
room. The NRC inspector noted to the licensee that the size of Room 27 -i
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(approximately 150 square feet of accessible space) did not conpare to the
example provided in the TS exemption (containment building), and that two
out of three flashing lights required by the exemption were not working
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and the access at the east end was not properly roped off. The general
radiation levels in Room 27 were less than 1000 mrem /hr; however, waste
material stored in several plastic bags within the room produced radiation
levels of approximately 1200 mrem /hr measured at 18 inches. The failure
to properly control very high radiation areas is considered an apparent ,
violation of TS 5.11.2 (285/8601-03).
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No deviations were identified. L
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l 10. Control of RAM and Contamination, Surveys, and Monitoring
The licensee's programs for the control of RAM and contamination, radiological
surveys and monitoring were reviewed for compliance with the commitments
contained in the USAR - Section 11, and the requirements in 15 5.11,
10 CFR Part 19.12, and 20.4, 20.5, 20.201, 20.203, 20.205, 20.207, 20.301,
20.401, and 20.402, and the recommendations in IE Information Notice 85-92.
! 10 CFR Part 20.201 requires that a licensee shall make or caese to be made
such surveys as may be necessary for the licensee to comply with the regu-
lations in this part, which also require that surveys be conducted
incident to the use, release, and disposal materials. The NR inspector
determined on January 7, 1986, that on or about October 9, 1935,
,
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l l valve MS-280 was removed from the main steam system within Room 81 of the l plant (a normally non-radiologically controlled room) and shipped to an '
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i offsite laboratory for testing per a plant maintenance order that did not
require any radiological controls. This valve is part of steam
generator 8 (SGB) of the main steam system that was exposed to primary
coolant radioactivity during a primary to secondary leak in 1984. The !
failure to perform proper surveys of potentially contaminated items prior !
to leaving the plant is an apparent violation of 10 CFR Part 20.201
- (285/8601-04).
.
! The NRC inspector noted that an internal incident report (No. 2183) was i generated on October 15, 1985, concerning the shipping of the contaminated l
valve to the offsite laboratory, but at the time of this inspection
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written procedures addressing radiological controls for work on the !
SG-B main steam components had not been developed. The NEC inspector
pointed out tomlicensee representatives that with no established permanent
corrective action, a similar situation could occur involving other
systems. ,
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The NRC inspector di'scussed with licensee representatives within the CRP
group and those at the exit meeting the observation that FCS procedures
allow the release of materials with detectable levels of radioactive
materials on them which is not in accordance with the philosophy of the
NRC as expressed in NRC IE Information Notice 85-92. The NRC inspector
also noted that loose surface radioactive contamination limits for
materials was a factor of almost ten above the minimum sensitivity of
their laboratory counters / scalers.
No deviations were identified.
11. Exit Meeting
The inspector reviewed the scope and findings of the inspection with
licensee representatives noted in paragraph 1 of this report at the
conclusion of the inspection on January 10, 1986. In response to the
inspector's comments the licensee agreed to implement immediate action to
lock the doors to Room 27 or eliminate the source of the very high
radiation.
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ATTACHMENT
TO NRC INSPECTION REPORT
50-205/06-01
APPENDIX B
D_OCUMEf1TS__R_EV 1 EWED
IIILE SEVISION DAIE
Omaha Public Power (OPPD) District Quality
Assurance Manual 4 11-O'-83
Fort Calhoun Station (FCS) Quality Assurance Plan
Section'10.4. Deficiency Control and
Corrective Action 0 09-01-84
Section 11.1. Radioactive Material Control 0 09-01-84
Section 11.2, Health Physics 0 09-01-84
Section 11.3. ALARA. Radiation Exposure
Program 0 09-01-84
Section 11.5, Packaging and Transportation
of Radioactive Waste 0 09-01-84
FCS Quality Assurance Department Procedure Manual (OADP)
DADP-5. Internal Audit and DA Survei11ance
Scheduling 3 12-03-85
OADP-6, Conduct of Audits 2 11-30-84
OADP-7, Conduct of GA Surveillances 3 07-10-85
OADP-8, Conduct of OA Inspections 1 11-30-84
DADP-10 Review of Procurement Documents 2 11-30-84
OADP-12, Material Acceptance and neceipt
Inspection 2 11-30-84
,DADP-14, Deficiency Tracking and Trending 3 12-03-85
FCS DA Department and OPPD Safety Audit. Review Committer (SARC) Audits
Audit No._ Cit 1e Erggu e n c ylyJ1a r s ) - Rey p_on s i b i 1 i t v
13, Procurement Control 3-DA
14 Control and Dualification
of Vendors 2-SARC
31, Storage. Shipping, ano
Handling of Controlled
"
Ouality Equipment (COE) 3-DA
56, Radioactive Material
Packing and Shipping 3-DA
57. Radioactive Matertal Control
and Waste Management 3-DA (Requires use of
Technical Specialist)
63. Radiation Protection Program
and Implomanting Proctriures 2-SARC
, .
11TL.E REVI.SIOr] De31 E
DA Surveillances:
tFrequency: M= monthly, O=quarteriv.
S= semiannual 1y, A= annual 1y,
R"r.=f uel i ng / .18 months)
M-14 Plant Activities - House Keepinq
0-1, COE Material Receipt / Storage /Insue
0- 7, Health Physics Surveys /Reporti
0-12. Radioactive Materi al / Sources
.0-23, Radiation Protection
1.
5-3, 11aintenance Qual i ty Control
S-13, Waste Solid Release
A-42, Radicactive Material Shipment
GA Department Internal Audit Schedule (1983 - 1986)
SARC Internal Audit Schedule (1984 - 1985)
NGC Ouality Assurance Program Approval tor
Padioactive Material Packages No. 0256 2 07-23-04
OA/SARC Audits and Survei11ances:
83-DA-185, COE Storage, Shipping and
Handling, Audit P1an 31 10-31-G4
34-OA-167, Radioactive Material, Shipping.
Control & Waste Management, Audit Plans
56 6 57 09-05-84
- Surveillance S-13, 5/95-1 through 11/05-14
RAM Shipments
OA Receipt Inspection Records
Purchase Orders Material
63213% Rad Waste Container 02-17-04
63222% Rad Waste Container 02-22-94
63237% Rad Waste Container 03--09-84
. 536805% Rad Waste Contatner 09-04-04
538630% Rad Waste Container 05-14-05
FCS Training Manual
Gection 2.0 General Employee Trainina 10 ,
v?~19-05
Section 6.o. Chemistry and Radiation
Pr utection Group Trainino 10 09-19 95
bection 6.2. Chemistry and Radiation
Protection Group Retrainina 10 v'/ - 19 -05
k
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TITLE FEVISION DATE
FCS Operating Procedure Manual
Volume A. Standing Orders
General (G):
G-22, Storaoe of Crttical Clement and
Rad 2cactive Material PacLaqino.
Fire Protection Material, and
Calibration Equipment 14 12-17-GS
G-24, Receipt C"ntrol of CDE Material 17 12-20-94
G-25. Stores Control 14 06-25-85
G-26. Maintenance Quality Control Program to 10-16-05
G-26A. Quality Control Procram. Append 1 L.
Radioactive Shipment Checklist 10 09-13-05
G-27 Training 5 0G-16-85
G-o3, Volume Reduction of Radioactive
Waste O 07-39-05
Tecnnical (T):
T-1. Fadiation Procedure Manual ! 03-31-01
T-4, kaste Solids Release 6 04-23-G5
T-10, Personnel E::posure Records 27 07-02-G5
T-18. Cleaning Agents for Use in the
Au>:i l i ar y Bui l di ng 2 06-25-G5
Records (R):
R-4 Operating Incident Reports 9 04-16-04
Volume VII, Radiation Protection Manual
Section 2.0, Personnel Protection and
Control 32 09-24-05
Section 2. 7, Radiation Work Permits
.
Section 2.0. Area Control 14 05-00-D5
Section 3.1.B. High Fadiation Area
Section 3.2, Contamination Limitu
Section 3.4, Access Control
Section 5.0 Equipment Control 5 11-15-03
Section 5.3.2. Release to Unrestricted
Area
.
Section 6.0, Radioactive Material Control 17 10-11-85
(RAM)
Section 6.1, Receivino RAM
5ecticn 6.2. Storage of RAM
Section 6.2 Trancportation of RAM
Section 6.4, Loading Waste Containern r.n
" Sole Une" Tral 1er for Ghipment
Section 6.5, Radioactive Material
Shipping Papers (FC-210)
3
. .
TITLE h.CYItjiON DATE
Sect 2on S.O. Radiation Protectino Procedur es tRPPi
RPP-14 In-Plant Collection and Disposal
of Radioactive Waste 2 06-10-05
FPP-15, Veri f i cati on of Liquid Free
Solidified Waste, Spent Resin Waste
and Dry Compactable er Noncomnact-
able Waste 4 11-13-05
HFP-20 Radiation Work Permtts 4 08-29-05
Section 9.0, Operating Procedures for Health Phycics Personnel (HP)
HP-3, Solid Waste Shipment Procedure 13 07-30-85
H P -- 3 A , Operation of the Darrier 5 5 H i --
Integrity Container Overpack O 09-07-04
I tF -3D. Procedure (CNSI) 1 07-30-G5
HP-3C. Maintenance /NUS Support for Rad-
Waste Solidificatien 0 10-30-b3
H -8, Labeling and Bagging of RAM 3 05-28-75
HP-17, Outside Storage and Movement of
Radicactive Waste 1 05-07-85
Hf ' 16 Gelection of Contract s 'eal th
F h ', s i c s Technittans 1 07-12-03
h?-19 Radioactive Waste Inventory
Procedure ! Oo-10-OG
HP-21. Determination of Package Curie
Content 1 11-15-83
(P-21A, Determination of Waste Fcrm
C1ausfication 3 10-24-85
HF -23, Restricted Area Vi si tor Tir t e f i n g O 12-01-83
HP-25. Radiation Hot Spot Verification /
Update O O2-20-84
HF -2 /, Determination of Dry Active Waste ,
'
kverage Radsonucl1de/Compoettton
and Energy 1 10-31-SS
Goi: t 2 an 10.0. Radialocical Incident Reports 1 12-01-04
Goc t i on 11.0, Procene Control Program 0 10-03-05
volume '/ I I I , Chemistry Manual Procedure (CMP)
.%c t t on 2.0, Sample Collection
LMP-2.3, 40 CFR Pert 190 Sampling 1 10-02-05
-
CMP-3.5. Determinatton of Isotopic
Specietc Acttvity 4 O',-19-05
Maintenance Procedures (MP)
HfulUPAC-1. Loadino of Htqh Intoqrttv
Containers J 07-30-US
MP - HUSC AGl'- 1, Opening. l.cadino ond Clostnq
'
of Pact: age NUS 14-!70 f 1 - 1 i' - H b
4
. ., .
TITLE fiEV l G 10f! DATC
FC5 Memorandum. FC-618-04, Subj: 10 CFR 61 Analvses for Waste
C1assification 03-20-04
Innenendent Laboratory First Quarter 1985 Waste Stream
Analvsis Hesulta 08-01-8S
Solidification Service Procedures
$ 5 --001, Precess Control Prooram for the
NUSPAC Solidiftcation System I 00-16-85
55-019 System Set up / Removal Procedure for
the System 8000 A
SG-020, Operatino Instructions f ac the
Gystem 8800 A 10-25-05
NU.3 Letter of Instruct 1on: 7526-003, FCS
En1idiftcation Service Sampiing Methad 10-39-OS
.
FCS Calibration Procedures:
CP-065-EC, Control Room Iodine Monitor 2 04-01-05
FC3 Surveillance Frocedt.re:
ST -RM -2. F. 5, Process Monitor Electronic
and Secondarv Calibrations 37 11-12-05
Accer,s Logs for Aunil1ary building Controlled
Doore 100715 and 100722 for the period
July 1985 through Deceinber 1985
FCS Drawino 435 302-001, Steam Generator Dlowdown Processing Gvstem
~
RhM Shipping Package Vendor Manuals:
CurrentIv
TliiE Co t C . Revj e i o.n. _lgeqi s tf y ed_t)ser_
CNSI 14-195H. USA /?O74/A G YES
CNSI 21-300, USA /9096/A 2 NO
CMSI 8-120 USA /6601/D i ) 20 NO
HN-100 USA /9151/A 0 YES
HN-68)O, USA /90GO/A l YES
NUPAC-!OO, USA /9000/A 12 YES
NUPAC 14D-2.O. USA /907c,/4 13 YE5
NUS-9000, USA /9000/A 12 YES
NUS 14-l'/, USA /9151/A O YES
NUG 10-135. USA /9073/A IS NO
.
. . , .
FC9 Semtannual Solid Radioactive Watte Disposal Report
.lu l y 1904 through Deceaber 1984
January 1985 through June 1985
Ju' y 1985 through December 1985 (preliminary data)
FCS Form 205, Radiation Exposure Termination Reports
FLStrorm 220, NRC Form 5 Equivalent
.
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