IR 05000267/1986021
| ML20210D261 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/05/1986 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20210D239 | List: |
| References | |
| 50-267-86-21, NUDOCS 8609190094 | |
| Download: ML20210D261 (14) | |
Text
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APPENDIX B
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
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NRC' Inspecf.f on' Report:
50-267/86-21 License: DPR-34
Docket:
50-267
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j Licensee:
Public Service Company of Colorado (PSC)
P.O. Box 840
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j Denver, Colorado 80201-0840 i
j Facility Name:
Fort St. Vrain Nuclear Generating Station (FSV)
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j Inspection At:
FSV Site, Weld County, Platteville, Colorado l
Inspection Conducted:
August 4-8, 1986 f
Inspector:
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9f H. Chaney, tadiation Specialis, Facilities Udte'
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j Radiological Protection Section Approved:
di f Mll)7(///
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B. M~urray, Chief, Facilities Radiological Date'
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Protection Section
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Inspection Summary
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Inspection Conducted August 4-8, 1986 (Report 50-267/86-21)
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j Areas Inspected:
Routine,' unannounced inspection of radwaste management,
radiological effluent releases, and radioactive material transportation l
programs.
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Results: Within the areas inspected, one violation (see paragraph 10)'and no
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deviations were identified.
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8609190094 860?16 i
PDR ADOCK 05000267 O
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DETAILS
1.
Persons Contacted PSC
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- L. W. Sing 1eton, Manager, Quality Assurance (QA)
C. H. Fuller, FSV 5.ation Manager
- F. J. Borst, FSV Support Services Manager
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M.'J. Fa'ris, Manager, Operations QA V. J. McCaffic, Supervisor, Radiochemistry
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- S. Hofstetter, Licensing Operations i
- T.'D. McIntire,-Supervisor, Site Nuclear Engineer Department
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- P.' F. Moor 1, QA Technical Support Supervisor
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D. L. Frye, Senior Licensing Specialist
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S. Sherrow, Health Physicist
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W. Woodard, health Physicist
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.0thers
'R. E. Farrell,'NRC Senior Resident Inspector
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- P. Michaud, NRC Resident Inspector
- Denotes thos'e individuals present during the exit interview on August 8, 1986.
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The NRC inspector also interviewed other licensee employees including i
health physics (HP), operations, QA, and document control.
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2.
Licensee Action on Previously Identified Inspection Findings (Closed) Violation (267/8511-001):
Certified Package Procurement - This
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violation was discussed in NRC Inspection Report 50-267/85-11 and involved the licensee's failure to properly implement QA reviews of procurement i
documents for radioactive materials packages procured in accordance with j
the requirements of Appendix H to 10 CFR Part 71.
The licensee's corrective actions concerning this violation are considered adequate. This item is considered Closed.
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(Closed) Violation (267/8511-002):. Receipt Inspection of Radioactive Material Transportation Packages - This violation was discussed in NRC
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Inspection Report 50-267/85-11 and involved the licensee's failure to perform a receipt inspection of components used in NRC certified I
radioactive materials shipping packaging.
The licensee's corrective actions are considered adequate.
This item is considered Closed.
(Closed) Violation (267/8602-02):
Transfer of Licensed Materials to an Unauthorized Location - This violation was discussed in NRC Inspection i
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-3-Report 50-267/86-02 and involved the licensee's transfer of radioactive materials to an unauthorized location.
Licensee corrective actions are considered adequate.
This item is considered Closed.
3.
Organization and Management Controls
,Thb NRC inspector examined the organization and staffing of the licensee's
' organization concerning radioactive waste management and radioactive material transportation activities to determine agreement with commitments in Sections 12.1 and 12.3 of the Updated Final Safety Analysis Report (UFSAR); the requirements of 10 CFR Parts 20 and 50, and Technical Specifications >(TS) 7.1 and 7.4; and the recommendations of NRC Regulatory
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Guides-(RG) 1.33, 1.,8, and 8.8.
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The NRC, inspector reviewe'd staffing charts, position descriptions, and i
' administrative. documents assigning responsibilities regarding radioactive
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waste management, radio 1'ogical effluent control, and the transportation of
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radioactive materials'.
Interviews were held with personnel resporsible
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for the,above noted activities.
The NRC inspector noted that the licensee had revised FSV Administrative Procedure P-3,." Radioactive / Contaminated Waste / Area Control," which now provides authority for radiation protection technicians to stop unsafe
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radiological work.
This resolves the NRC concern addressed in NRC Inspection Report 50-267/36-02.
The NRC inspector noted that current station procedures provide too much flexibility regarding personnel authorized to sign documents certifying shipment of radioactive materials.
Licensee representatives stated at the exit interview on August 8, 1986, that the station's position on persons authorized to sign shipment documents would be reviewed for possible clarification.
No violations or deviations were identified.
4.
Qualifications and Training The NRC inspector examined the qualifications and training of personnel responsible for radioactive waste management, radiological effluent-releases, and transportation of radioactive materials to determine agreement with commitments in Section 12.2 of the UFSAR; the requirements of NRC Inspection and Enforcement (IE)Bulletin 79-19, 10 CFR Part 19.12, TS 7.1.1.h; and the recommendations of RGs 1.8, 8.27, and NUREG-0761.
The NRC inspector reviewed personnel training records, training outlines, training procedures,'and interviewed selected personnel.
No violations or deviations were identified.
5.
Audits The NRC inspector reviewed the licensee's QA audit program for radioactive waste management, radiological effluent releases, and transportation of
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i radioactive materials to determine compliance with 10 CFR Parts 20, 61,
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and 71; Department of Transportation (DOT) 49 CFR Parts 171-178; TS 7.1.3,
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7.4, 7.5.3 and 8.0; and commitments in Section 11.'1 of the UFSAR.
The NRC inspector reviewed QA manuals, audit procedures, audit checklists,-
audits conducted by the Nuclear Facility Safety Committee (NFSC) during
1985 and 1986, audit. findings, corrective action tracking and responses to findings, and auditors' qualifications.
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No violations or deviations were identified.
6.
Radioactive Effluent Releases
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The NRC. inspector reviewed the licensee's liquid and gaseous radwaste s
process.ing systems, operational procedures, and records associated with
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liquid 'and gaseous releases to determine agreement with commitments in
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l Section 11.1 of the UFSAR; the requirements in'10 CFR Parts 20 and 50,
TS 7.3.b.5 and 8.0; and the Offsite Dose Calculation Manual (00CM).
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' Liquid j
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iThe'NRC inspector reviewed a representative number of liquid release i
permits for the period of January 1985 through July 1986.
The NRC
-inspector determined'that processing, sampling and. analysis, and i
' discharge approval were conducted in accordance with TS and plant l
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Quantities of radioactive nuclides released in the liquid
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effluents were within the limits of specified in Appendix I to 10 CFR s
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Part.50, and TS'8.0 (Radiological Effluent Technical-Specifications -
RETS). The NRC inspector determined that no design changes to the
liquid ra'dioactive waste system had been made since the previous NRC inspection conducted March 1985.
The licensee is proceeding with the installation of an on-line beta radiation monitor for monitoring and
j controlling discharge of liquid effluents.
The licensee will provide
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j the NRC Project Manager documentation concerning the installation,
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i testing, and calibration of the beta monitor.
Projected offsite doses
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were verified to have been made at the required frequency and in the
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j proper manner.
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Gaseous
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The NRC inspector reviewed representative gaseous release permits
which included continuous and batch releases from the waste gas i
processing ~ system for the period January 1985 through July 1986.
It was determined that gaseous waste releases were performed according to TS and plant procedures, and that the quantities of nobl_e gases and particulates were within the limits specified in the TS.
Projected i
offsite doses were verified to have been made at the required frequency i
and in the proper manner.
The NRC inspector determined that no design j
changes had been made to the gaseous waste management system since'the j
previous NRC inspection conducted in March 1985.
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'The NRC inspector reviewed gaseous waste records for determining the
' maximum amount of Krypton 88 in the waste gas system surge tank.
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The NRC inspector reviewed the licensee's results involving reduction
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of historical meteorological data and the calculation of a new annual average dilution factor for use in calculating gaseous effluent
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No violations.or deviations were identified.
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7.
Records' and Reports of Radioactive Effluents The NRC inspector reviewed the licensee's records and reports concerning effluent releases to determine compliance with the requirements of TS 7.5.1.a, 7.'5.1.e, 7.5.3, 8.1.1, and 8.1.2, and 10 CFR Part 20.401(c)(2).
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The NRC inspector reviewed semiannual reports for 1985 and raw data for the first half of 1986.
Reports contained the information required by NRC Regulatory Guide (RG) 1.21.
No licensee event reports (LERs) had been
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written since the previous NRC inspection of this area in March 1985.
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No violations or deviations were identified.
8.
Radioactive Effluent Release Procedures The NRC inspector reviewed the licensee's effluent release procedures to determine agreement with commitments in Section 11.2.3.3 of the UFSAR; compliance with TS 8.1.1, 8.1.2, 8.1.3, 8.1.4, and 8.1.5; and TS surveillance requirements.
The licensee's procedures concerning the release of liquid, gaseous, and
solid radioactive wastes were reviewed for format and content.
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No violations or deviations were identified.
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9.
Air Cleaning Systems The NRC inspector reviewed the licensee's procedures, surveillance tests, selected records and test results for air cleaning systems containing high-efficiency particulate air (HEPA) filters and activated charcoal
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adsorbers to determine agreement with the commitments in Section 6.2.5 of the UFSAR; the requirements of TS 5.5.3.a. b, c, e; and the recommendations of industry standard ANSI N510-1975.
The licensee's procedures provided for the required periodic-inspections and testing of HEPA and adsorber systems.
Checklists and testing results provided by outside contractors for the 1985 and 1986 inspections / testing were reviewed. The NRC inspector noted that one adsorber bed failed leak test requirements and the charcoal adsorber material was replaced in October 1985.
All other results were within TS limit.
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No violations or deviations were identifie,
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10. Radioactive Process and Effluent Monitoring Instrument Calibration The NRC inspector reviewed the licensee's effluent monitoring
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instrumentation for agreement with commitments in Section 11 of the UFSAR;
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the requirements of TS 8.1.1 and 8.2.1; and the recommendations of NRC RG 4.15.
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The NRC inspector inspected the licensee's placement and status of
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operation of liquid and gaseous effluent monitors and selected process and l
l alert monitors for liquid and gaseous waste streams.
Procedures for-
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calibration, alarm / trip setpoint adjustments, functional checking of i
"actuations, and calibration records for 1985 were reviewed.
Discussions
I were held with radiochemistry, operations, and health physics personnel regarding the. licensees use of radioactive gas standards to calibrate
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gaseous monitors, verification of alarm / trip setpoints, and the use of j
' radioactive liquids standards to calibrate liquid effluent monitors.
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TS 8.'1'.'j ' requires, in part, that "The alarm / trip setpoints of radioactive
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gaseous effluent activity monitors shall be determined and adjusted in accordance with the Offsite Dose Calculation Manual (00CM)." Furthermore,
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FSV Support Services Manager's Administrative Procedure (SUSMAP) - 2,
"Offsite Dose Calculation Manual," states, in part, that "These procedures i
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will be utilized by the operating staff of,FSV to assure ---aliance with i
the Technical Specifications." During the review of a ip setpoints
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for the plant stack noble gas effluent monitors RT 73'
RT 7324-1,
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the master setpoint log (in the control room) and se,
, monitors at 3.50 C64 and 1.30 E+3 counts per minute (CPM), rcspectively.
These setpoints were last established on October 25, 1985, during the last
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i routine scheduled calibration of the instruments.
Using FSV i
j Procedure SUSMAP-2, Revision 12, dated April 18, 1986, the NRC inspector
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determined on August 7,1986, that the aforementioned monitors' setpoint l
should have been set at 3.10 E+4 and 9.80 E+3 CPM, respectively.
This is~
i an apparent violation of TS 8.1.j (267/8621-01).
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After the licensee was notified of the apparent error in setpoint settings
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on August 7, 1986, the licensee took immediate action to verify the NRC e
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inspector's calculations, and upon reaching agreement with the NRC inspector, initiated the following corrective actions:
. Verified the setpoints of all effluent and process monitors and j
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established the required setpoints per the 00CM.
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Issued a setpoint change request to correct setpoints on tha rconitors listed below:
Monitor Function (1)
Current
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Re 6314-1 Waste Gas Iod.
(C)
7.00 E+6 7.10 E+6 (
6314-2 Waste Gas NG (C)
1.70 E+6 1.50 E45 7325-1 Effluent lod.
(C)
1.60 E*3 4.70 E+3
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4801 Plant Stack Part. (P)
1.00 E+4 9.20 E+3
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4802 Plant Stack lod.
(P)
1.90 E+4 1.00 C+4 4803 Plant Stack NG (P)
2.34 F+4 2.30 E+4 (
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73437-1 Plant Stack Iod.
(C)
2.00 E+4 1.70 F+4 73437-2 Plant Stack Part. (C)
9.50 E+3 1.10 E+4 (1) (C) = Release control monitoring function, (P) = Process monitoring function, IOD. = Iodine radioactivity, NG = hable Oas radioactivity, Part. = Particulate radioactivity No setpoints were found that would have resulted in the
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discharge of radioactive effluents above the limits estabMshed by the TS or 10 CFR Part 20.
Issued a revision to radicchemistry prccedure (RCP-30), 'I,otupic (
Calibration of Particulate, Iodine anQ Noble Cas Activity Mcnitort.,
Revision 7, dated August 8,1985, which establishes instrument sensitivities, alarm / trip setpoints, and instructions, for ver ifying that setpoints are in agreertent with SUSMAP-2.
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The licensee's corrective actions were reviewed by the NRC inspector on August 8,1986, and determined to be adequate to corr 0ct the apparent
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violation and prevent a recurrence.
11. Qw-Level Radicar.tive Waste (LLRV) Managementlrogram The NRC inspector inspected the licensee's program for the control, classification, characterization, and shipment of low-level radioactive waste to determine agreement with commitments in Section 1L13.1 of the UFSAR; the requirements in 10 CFR Parts 20.301, 311, 51.55, and 61.56, and TS 7.5,e and 8.1.4; the recommendations NRC I&E Notices 85-05, 85-92, 86-20, and NRC branch technical positions cuncerring LLRW classificaticr and waste form.
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-8-The NRC inspector reviewed selected records and orocedures cor.cerning the i
licen3ee's solid waste processing progran, including:
training, vendor
support. (the licensae has not as of this inspection teen required to
solidify any vet wastes), waste -classification and characterization procedures, shipment manifests, material segregatio1, surveying of potentially contardneted neaterial, samplirg and analysis of waste streams, compaction'af dry active waste, and tre Process Control Program (OCP).
- The licensee was noted to have a current copy of the dispcsal site license.
i The following table lists the disposal and storage cf radioactive' waste
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for the. periods January - December 1995 and (January - June 1966):
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Shipunts LLRW to be Long Term Jypes of LL,RW To Burjd Snippe.1 Storage *
CAW (m )..
43.1 d.0 0.0 (0,0)
(2.0)
(0 0)
Wetted k'astes (m )
66.1 0. 0 5.0 (0.0)
(0.0)
(6.0)
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Ca;npoaants (m )
73.6 0.0 0.0
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(O. 0)
(310)
(O. 0)
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- Denotes waste being held pending 10 CFR Part 20.302 determination.
Nn violations or deviations were identified.
12. Cnsite Low-tevel kadicactive Watte St.orace lhe licehsee's onsite low-level radioactive waste stornge facilities were
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rev(ewed for agreenent with the guidance provided in NHC Generic
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Letter 61-38.
Tha NRC inspecto.' reviewed representative records, ir.spected storage facilities, arid discussed with licea,see personnel the long term storagc
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of certain waste forms.
The licensee currently has rpproximately 24 drums (55 gallon) of absorbed racicactively contaminated oil and 5 drums of
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dewatered ret, ins in long term storage.
The "sicensee is awaiting finalizing of the state of Nevada disposal site burial criteria for si.ch wastes.
The licensee's storage facilities were,)reviously discussed in N'tC Inipection Reoorts 50-267/83-28, 85-02, and 85-11.
The onsite storw'e facilities
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No violatio.1s or deviations were identified.
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Radioactive Ma*.erial Transportation Progry
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The NRC insfector reviewed the licensee's radioactive material trarsportation pregram for agreement with comnitments in Section 11.1.1.1
of the UFSA9; compliance with the requirements of 10 CFR Part 71, 49 CFR Parts 171 through 178, NRC IE Eu11etin. 79-19; and agreement with the recoramendations of NRC Regulatory Guides (RGs) 7.1 through 7.10, and the guidance cnntained in IE Information Notice 65-46.
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Audits and Aporaisals Tne licensee's recent aedits (J:inuary and May 1986) of transportation and. solid radicactive waste activities was reviewed and found to be satisfactory in scope and content.
The audit checklist and qualificatiens of the auditors was determined to be satisfactory, b.
Procedures Tha licensee's procedures for processing radioactive material and spent fuel shipments was reviewed and found to incorporate the essential portions of NRC and 00T requirements, c.
Radioactive Ma_terial (RAM) and Spent Fuel Shipments The licensea's recorus of RAM and soent fuel shipments for Jaruary 1985 through Jt.ly 1986 were reviewed.
The licensee made 22 spent fuel snipments to tFe Department of Energy in Idaho in 1986,
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and approximately 29 shipments of NMi/ waste between 1985 and 1986.
$ hipping ard accountability documents, prior notifications, package inspectinns, certificate of authorization for packaging use, and dttermination of curie content of packages were in order.
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Mu errent and Reuse of hRC Certified Packaula1s
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The licensee's procedJros for the procurtment of certified packagings and the receipt inspections of packagings were reviewed.
The licensee procures packagings in accordance with QA procedures, and performs receipt inspections and maintenance activities in accordance
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with vendor approved procedure / checklists.
The licensee maintains vendor maintenance manuals on all packagings normally used.
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J,ramportationinci_ dents e.
The licansee stated that they were not aware of any transportation incirients involving licensed.r.aterial:s that have occurred since the last inspection of this arna in April 1985.
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QualityAsa.urancePrnuram
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The licensee maintains an NRC approved QA program that implements the requiicments of Appendiy H to 10 CFR Part 71.
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Records and Report l
The licensee's records for RAM and spent fuel shipments were reviewed, as were material receipt inspection surveys and packaging re elpt inspections.
Licensee submitted Semi-Annual Effluent Reports contain the shipment volume Information required by FSV TS 7.5.e.
The i
,reconmendations of NRC RG 1.21 are incorporated by reference into the atorementioned TS.
l No' violations or deviations wert identified.
14. Exit Interview The NRC inspector met with tha licersee's representatives and the NRC
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resident inspector identified in paragraph 1 of this report at the conclusion of the inspection on August 8, 1986.
The NRC inspector summarized the scope and the results of the inspection.
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ATTACHMENT
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FT ST VRAIN PROCEDURES
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REVIEWED FOR j
NRC INSPECTION REPORT 50-267/86-21
j 1116E Egylg10N D615 t "L.0detoist.tative_Cteceduces
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R-3, RadioactiverContaminated Waste / Area
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Cantro1
07-29-06
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FSV Organt:ation & Responsibilitien G
O2-13-06
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o.' - 4 Procurement System G
07-09-86
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0 - 7. Control of Procured Materials.
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Eouipment, and Services O
04-28-86 i,
J-JPl'OC$ GetV1 CSE Mauogtys_.OdO101stta.ti,vg_Etggedytqs_,iSUQM6E),
.UaM W-1.
Health Physics. Radiochemistry,
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and Chemintry Experience. Qual-
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i f i c a t-i on and Training Requirn-ments
11-05-85
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U :;l MP - ?, Offntte Date Calculation Manual
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ein! Hadiological Environmental Monitoring Program (REMP)
04-18-86 I
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GlEMAP-L Process Control Program
11-13-04
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SUGiloP-4, Radiation Pratoction P1an
05-06-06 t
huCMAP-G. Chemical Control Proqrem
04-09-06 i
ib "1.th PhyQgs Proc;mlytop_fUEE1
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H*r P - 1 7, Determantnq Radioactive Liquid
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i Rolvese Paton
06-19-86
i W P -- 1 J. Radicoctive Gau Wasto Reloane Hato C,d c ol ati ons
09-16-05 t
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- U ? ?>. Reroivinn Radtowctivo Noterials 10-07-29-06 l
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TITLE REVISJON DATE IFP-20. Radioactive Material Control and Hand 1ing
11-01-85 HFP-30, Shipment of Radioective Material
07-24-86 f tPP-35, Fast Ga:. and IcGi ne U..orp12 ng to 03-26-86
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itPP-46 Tectini cal Specifications Related to Health Physics
07-24-06 Hit-47 Gutde for Outat ning Gas Sanales f rom the He; i utt Tratler and
Other Systems
02-07-G5 HFF-Si. C.ortanuous Atr Monttees Fiiter and Cartridqe Chanan Out
06-19-06 H'P-53.
RI-7325 and RT-73437 Emercency Filter end Cartridon Removal
04-01-06 hFw S6. beactor fsui 't d t nq Ex haust Statl-Dic:barna Ac t i vl. t y Calculation
06-24-06 HF1'-ov. R metor Duilding Pump (T-7202)
t!f(lvent S4.aplino G
07-09-86 i edio, hen:t ytty Ptocedurus. Assoc;att;d..'s thR fluent,,Bglggggs,jEC@l RCP-7 Lanol o Propersat t on for Gomma Lpectral Analysts rp go_31_g4 RCP - 10. Samp l e Precar a ti on for Grcss Bota arid Gross Alpha Analysis
05-24-85 N'. P 10. Operat_ t on and Calibration forocoduce for the beckman Lt31000
10-15-85 RCP-21, Ouality Ansuronce Progrotn for the Radiochumantry Laboratorv
12-09-85 RCP~24. (M a l vr,i et for Vent Particulate end Todine Monitor filter for Surveillance
'le au i r t ir eo t I.2R 0.G Ief-W
02-07-05
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PO'-10, Iwt op t c Cal t brat A or, of Gategur f. t-t i v1 t y Moni i or t, Uc(nq MR "
00-08-06 ({l -
', Operatien o n tf C a l i br a t i ore Procedure for the H.o c!ms TAGC-12 Automatic Al nha /Imr. > Countincs S v t. em
03-21-05 e
NCF
'. l ' id i r.n: ri c a s i t r y C.alculattant to 05-13-06 i
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IIILE BEVIS10N DOIs'
Besultra_P oegdytes_1 bel t
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RP-Su2. Calibration and Maintenance of the RT-73437 Stack Monitor System
05-14-85
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RP-300. Reactor But1 ding Sump's Continuous
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Sampler
07-02-04 Begults_DeneCtment_sutvetiteogg_etggeduces_IsB1 SR 5.4.1.2.e.c-R, Reheat Header Activity j
Ca1ibration
12-07-84
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f SR 3.4.9+A1, Process Gamma Monitors
- o1-11-85 l
SH S.4.9-A2, Process Beta Monitors
Calibration
01-24-86
,
SR 5.5.3a-SA, Reactor building Enhaust Filtern Charcoal Filter Cemples
- 11-30-84-
,-
'
i
I Sh 3. % 3bc-H. Reactor Plant Exhaust Filters Charcoal Filter Halogenated Hydro-Carbon Removal and HEPA Leak
'
Test
11-30-84.
i
'R S. i W-W, Reactor Plant Exhaust Filter HEPA i
,
and Charcoal Pressure Drop Check
03-14-86-
,
S P - Hi
'r A. Halogenated Hydrocarbon Removal and HEPA Filter Leak Test
11-30-84 i
SP --OP -41 - X. Volume (Datch) Release From Reactor Du11 ding Sump
07-09-86 FSR 3.1.la-l.5Y, Radioactive Gaseous Effluent
!
System Calibration
12-07-84
ESP 3.1.Ia-m, Radicactive Gaseous E.ffluent Vent Monitor Gystem Source and Functional Test
11-01-85
F 9R G. I. l d -)', Equivalent Curies of 88 Kr in Gas Waste System
11-15-05
.
L6P U.1.2c-1.SY-/, Radioactive Liquid Ef fluent Activity Monitors i
Ca1ibret. ion
09-27-85 l
FLR R.1.Tc.O. Radtoactive Ltquid Effluent i
activity Monitorn functional 1act
07-t5-86
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IIILE BEVISigN DOIE ESR 8.1.4ab-X. Sclid Radioactive Waste
01-04-85 ESR 8.1.Sab-M, Total Dose
01-04-85 IratoAgg_Ctggtqms_6dminisitgtive_Uggggl_IIE6dl TPAM-HP, Health Physics and Radiochemistry Training Programs
03-05-86 Oucleet_Eact.lity_Sciety_ committee _INEsg1_sudits IIFGC K-05-01, Radwaste, Effluents, and Meteorology 10-21-85 NF 5C J--86-01, Environmental (Radiological and Non-Hadiological) Monitoring 02-18-86 NFSC I-86-01, Offsite Dose Calculation Manual and Prncess Control Program 06-01-86 St ? qd etd, _ Opt;td t 1gg _Ecgced ytq s _1gQEl GOP 62. Radioactive Waste & Radiation Protection
11-04-85 GOP 63, Padioactive Gas Waste
10-02-85
.
O thet _Docurlients_ Eel at ed_to_the_10=gpection FSV Gemt-Annual Radiological Effluent Release Reports 1983, 1984 and 1985 FGV Internal Memorandum (From TSS J.
Sills to SSM F.
Borst), Serial No.
PPC-86-3010, date June 30, 1986, Subject: 12 Month. Data Reduction Per Peo. Guide 1.21 Format (Meteorological Data)
FSV Gummary of Spent Fuel Shipping Activities (PPC-86-2416)
05-28-86 Ltquid and Oaseous Waste Release Summaries for 1985 and 1986 Radioactive ftaterial Shipment Records for 1985 (21 Shipments)
and 1906 (9 Shipments)
,
Fuel 3 hipping Cank t1ointenance Records (MPF-1001)
10-16-85 Fuel Shipping Documents (22 Shipments)
FHPWP-66 03-24-86 FhPWP 47 03-24-86 FHiWP-'oi 11-01-05 FHPWP-1Oa 03-24-86
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