ML20141C942

Insp Rept 50-285/86-01 on 860106-10.Violation Noted:Valve W/ Radioactive Contamination Above DOT Limits Shipped as Nonradioactive Matl on 851009 & Termination Repts Not Processed within Required Time Period

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: ML20141C920 ML20141C942
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

Text

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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)

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                *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
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                  J. E. Bentzinger, General Office QA

j T. J. McIvor, Supervisor Technical Services

                                                                                                 t
                Others

D. Whitlock, Contract CRP Technician

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                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.

4 e s

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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.

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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

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             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.

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        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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                                            5
        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
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        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:
                 J

r_ . f'

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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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                           8.

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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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                                          8
           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.
 .
       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
       -
             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).

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! 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

 .     .
                 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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