IR 05000312/1975009

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IE Insp Rept 50-312/75-09 on 751014-17,20,22,28 & 29.No Noncompliance Noted.Major Areas Inspected:Emergency Preparedness Status,Radiation Protection Program & Verification of Licensees Action on Unusual Events
ML19317F894
Person / Time
Site: Rancho Seco
Issue date: 11/10/1975
From: Book H, Fish R, Wenslawski F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML19317F884 List:
References
50-312-75-09, 50-312-75-9, NUDOCS 8002210620
Download: ML19317F894 (11)


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,. U.. S. NUCLEAR REGULATORY CC103.ISSIC;l

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REGION V

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4IE Inspection Report No.

50-312/75-09 Licensee carrar$+nMunicinaltref15*.,nie.4,.+

Docket No. 50-312

'. O. Box 15830.

License No.

DDR-54 P

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Sacramento, California 95313 '

Priority

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Facility category C

Rancho Seco

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Clay Station, California Location

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Type of Facility PWR. B&W, 913 M0e (2772 MWt)

Type of Inspection Routine. Announced. Padiological

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Dates of Inspection October 14-17. 20. 22. 29 and ?9. 1975 Dates of Previous Inspection June 16-19.1975 (Radiological)

//!0!7I Principal It.spector

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R. F. Fish, Radiation Specialist

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Accompanying Inspectors

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F. A. Wenslawski, Radiation Specialist l

Date other-Accompanying Personnel: None

//!/c[7i Reviewed by

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H. E. Book, Chief, Radiological.& Environmental D^ t

Protection Branch

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Sumary of Findings Inspection Sumary

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Onsite inspection' performed October 14-17 and followup review of licensee documentation and telephone verifications on October 20, 22, 28 and 29.

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Reviewed status of licensee's emergency precaredness including coordina-i tion with offsite agencies, readiness of facilities and equipment, procedure changes, and drills and tests conducted. Also reviewed selected portions of radiation protection program and verified licensee's action on four unusual events reported since the last inspection.

Radioactive liquid and gaseous waste samples were obtained for con-firmatory measurements.

Enforcement Action

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None Licensee Action on Previously Identified Enforcement Items Not applicable Unusual Occurrences

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The information and corrective actions described in the licensee's Unusual Event Report Nos. 50-312-75-5, 75-6, 75-7 and 75-8 were con-s firmed by examination of records and interviews with personnel.

(Para-graph S of Details)

Other Significant Findings A.

The licensee has issued significant changes to the Emergency Plan and Procedures and to the Radiation Control Manual.

(Paragraphs 2.3 and 3.C of Details)

B.

The licenseeL is in the process of conducting comprehensive ra.fiaticn protection retraining.

(Paragraph 3.B of Details)

C.

The licensee's emergency plan drills appear effective in identifying problems.

Corrective actions are being taken.

(Paragraph 2.Cof Details)

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Thel licensee's action on the two comitments made during the last inspection concerning operability testing of the automatic isola-tion valves and laboratory instrumentation calibrations were

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examined and found to be satisfactory.

(Paragraph 3.D of Details)

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-2-Management Interview At the conclusion of the inspection, the scope and findings were scrari:ed and presented to the following licensee personnel:

R. Rodriguez, J.

McColligan, P. Oubre, R. Colombo, L. Schweiger, R. Miller and J. Jewett.

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The following items were specifically discussed:

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Records were not.being maintained for refresher training in fire fighting and it appeared that some offshift personnel may not be cycled through refresher training.

The licensee assured the inspector that all appropriate offshift personnel would receive the

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annual refresher training and stated tnat a record system would ce established.

(Paragraph 2.C of Details)

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B.

Licensee management was made aware that Revision 1 to the Emergency Plan and Procedures was in need of certain changes, i.e., telepnone numbers and minor inconsistencies.

A licensee representative had previously stated that appropriate corrections would be made.

(Paragraph 2.B of Details)

C.

The licensee had not updated the status of coordination with all the offsite agencies designated in the emergency procedures.

The licensee recognized the importance of periodic updating and stated that annual updating will be conducted.

(Paragraph 2.A of Details)

D.

It was noted that a portion of the (-)20 foot level of the auxiliary building had inconsistent entry conditions in that cne entry had an activated alarm and the alarm on the other entry was inactivated.

(Paragraph 3.F of Details)

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E.

Radiation exposure termination reports were not including the results of whole body counts for individuals on whom counts were made. The licensee agreed to evaluate the situation and provide a means of including these results in termination reports.

(Para-graph ~3.E of Details)

F. ' With respect to tritium bicassay, the licensee agreed to evaluate

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bioassay capabilities and possibly implement a limited bioassay program prior to the first refueling.

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Details 1.

Persons Contacted R. Rodriguez, Manager Nuclear Operations R. Columbo. Technical Assistant-

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J. McColligan, Assistant Superintendent, Technical Support P. Oubre, Assistant Superintende.nt, Operations

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L. Schweiger, QA Director

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J..Jewett, QA Engineer

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R. Miller, Chemical and. Radiation Protection Supervisor

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D. Gardiner, Senior Chemical & Radiation Assistant

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L. Bell, Senior Chemical & Radiation Assistant

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F. Kellie, Senior Chemical & Radiation Assistant T. Morrill, Chemical & Radiation Assistant D. Martin, Environmental Specialist

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H. Heckert, Surveillance Scheduler R. Bright, Safety Technician M. Carter, Shift Superviser B. Thomas,Iturse

E. Jordon, Clerical Supervisor

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R. Ripple, M.D., Sutter Memorial Hospital

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G. Schreiner, Emergency Operations Coordinator, Sacramento County

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J. Kearns, Radiological. & Intelligence Officer, Office of Emergency Services, State of California Cs 2.

Emergency Planning

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A.

Coordination with Offsite Acencies

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The licensee did not have an explicit program of periodically contacting offsite agencies to assure continued coordination and that responsible persons of the agencies are maintaining a i

familiarity with their role in an emergency respcase.

Various emergency drills have, however, effectively accomplished continued coordination with those agencies having a signifi-cant role.- In additibn, the licensee has been working clcsely with Sacramento County in a significant realigr. ment of Sts:e

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and County responsibilities.

However, some organizations (i.e.,

Galt Medical Group and the California Forestry's Fire Fignting Academy) have not been contacted to assure continued coordina--

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tion. The licensee-recognized the necessity of periodic-l

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updates with all organizations specified in the emergency clan

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and procedures'and agreed to implement a program to. assure all'

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. appropriate agencies are contacted at least annually.

It was agreed that such contact can consist.of participation in periodic training or drills or mere verbal contact to assure

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-continued coordination.

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The Sacramento County Emergency Opera:icas Office (ECC) bs recently completed an " Emergency Opera:icns Plan" wnicn,. en

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implemented, will result in the County E03 assu~.ir.g trany :f

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the dut.ies of the State Office. of E-er arcy Servi:ss GIS..

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Although the County emergency pian will a::iy for any :/;e emergency, the licensee has been working witn tne Cour.:y ::

detemine how the plan will apply to P.an:no Seco.

Cnce :ne plan receives required approvals (late Zvem::er), E00 will

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assume the role of a coordinator for C an:y effer:s and t e

licensee will need to nake only one tele:c:ne call to sur :n

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County and State assistance.

Status of :ce new pian '..as confirmed with both County and State officials as well as : e

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licensee.

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i The licensee's agreement with Sutter General Hos: ital to provide facilities and services in the event.of a medical problem involving a radiation overexp::ure or t..e presence :f

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radioactive contamination were confirmed :y tele;n:ne c:nta::

with a hospital representative.

The re:resentative re;or:e:

that the hospital recently revised their raciological e. e ;E :y

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procedures'and they expected to conduct a crill with the

licensee in November.

Discussions wi:n tne licensee and review of the emergency procedures discl: sed that Metnctis:

Hospital has been designated as a revise: locatica for trea:ing O

injuries not involving radiological conci:icns.

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B.

Facilities, Equipment and Procedures Facilities and equipment.for emergency resp:nse remain bast: ally unchanged. The first aid treatment stati:n is in the for a.-

Bechtel warehouse (onsite) and was beir.; ranned by a nurse.

The facility contains a complete array cf first aid equi; e :.

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As of June, th~e licensee had completed eignt nours first a':

refresher training for onsite personnel.

The ensite erer;s :y vehicle was still available and has ncu been designated f:-

principal usage rather than the Galt ambulance.

The conte :s of the assembly point emergency locker in :ne machine sh::

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warehouse were inventoried during the inspection. All re-quired. equipment was. on hand.

Emergency survey meters in ne-locker were u' served to be within calibration.

Calibrati:-

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records for all emergency survey meters were reviewed and found satisfactory.

Calibrations are performed in accor:1 :e

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with approved procedures.

In additicn.:o routine calibra:i: st

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monthly battery checks are done. on the _ emergency survey e:a. s.

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' Emergency comunication systems were exa:.ined and founc :: :e as described in the emergency plan. Two tests of emerge.:j radio communication systems were satisfactorily performed during the inspection.

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b plan and procedures.On October 1 the licensee issued

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The rgency

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clarification of language, revision principally consi3:ed of

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realignment of responsibilities between :ne Stata 055

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County E00 improved methcds of dose calculations as de er mined neces,sary by a

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otner minor enanges. drill, updated telephone num:ers an:d

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changes to provide any lesser degree of preparedn

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changes were reviewed and approved by the Plant The and approved by the plant superintendent.

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revised plan and procedures revea

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Examinaticn of the

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and two telephone listing errors. led a few minor inconsistancies of these and stated that appropriate c The licensee was ride aware made.

10 CFR 50.59 will include a description of the citan; the emergency plan.

will only affect shift supervisors.For'the most part, the revised pr made in plan and procedures.all st.Ift supervisors were instru The licensee s:1:sd that

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on dayshift indicated that he was knowledge

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Records showed appropriate distribution of the revisi

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been made.

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Drills The emergency plan specifies quarterly drills be cond involving evacuations of onsite personnel and testi

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ucted emergency communications.

ng of groups and emergency transport vehicles are to be h Since the initial annual drill held in June nnually.

has held drills on 9/30 The operating license wa/74, 3/19/75, 6/18/75, and 9/?5/75., 197 licensee considers the 9/30/74 drill to be the quarte for the last quarter of 1974.

The drill of 9 r y drill annual drill involving offsite support groups /25/75 was the volvin

1975 g Sutter Hospital is planned for the A drill in-

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discussed and corrective actions identified i

appropriate corrective actica is taken.the drill re e

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assures-that the drills appear effective in identifying weakn problem areas.

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involve equipment, onsite communications an

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n gency procedures were generally workable although one

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Emer-in the dose calculating procedure was identified a d

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a ness n corrected.

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-6-v The licensee has recently appointed a safety technician whose duties include coordination of fire drills. The emergency plan does not specifically specify a frequency for fire drills but two drills have been concucted (8/3/75 and 5/20/75) since the safety technician has ceen appointed. The first of these drills involved notification and response by tne Herald Fire Department.

Both drills. invo'.ved the extinguishing of oil / gas fires.

Evaluation ano documentation of fire crill results are

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done by the safety technician, who recorded coth drills to be satisfactory.

The. emergency plan specifies that yearly refresher training courses in fire fighting are to be given to operating and maintenance personnel.

The licensee is still in the process of developing the scope of training and drills, but stated that some refresher traiaing had been given to two dayshift crews and that drills are considered refresner training.

The licensee was not maintaining records of training.

During the exit interview the inspector expressed concern tnat all offshift personnel may not cycle t.hrough deyshift training and the lack of records made it af fficult to ascertain training status. The licensee statec that henceforth records of

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refresher training would t2 maintained and stated that all appropriate offshift personnel would be cycled through the training.

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Radiation Protection A.

Organization The licensee's management str s ce has not changed.

Two new Chemical and Radiation Assistants have been hired, one has several years experience at the Idaho Test Site, the other is a former navy ELT.

The li.censee is rotating all Chemical and Radiation Assistants between the Radiochemistry, Chemistry and Health Physics sections. The-licensee is considering varicus

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options for filling the plant health physicist position.

The

'former health physicist transferred to SMUD headquarters but remains available for consultation.

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Training

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The licensee is presently in the process of conducting radia-tion protection refresher training intended to establish a minimum level of competence for plant personnel. Operations and Chem / Rad personnel are-participating in a 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> training session covering the following topics:

regulations (Parts 19

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and 20), rad. protection instrumentation, personnel dositetry, l

radiation monitoring methods,- exposure control, respiratory

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protection, area control field applicaticns, personnel decentamination,

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area and equipment decontamination, records. Maintenance and I&C' personnel are participating in a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training session covering most of-the same topics.

Tests are being concucted

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after cornpletion of each training topic with a passing grade being 70';.

Copies of tes,ts are being raintained. The four

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i hour general orientation training is still given to all new employees. This training includes basic radiation centrol measures and basic emergency respense procedures.

Records of

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general orientation training are being maintained.

C.

Procedure Changes

Three revisions have been cade to the Radiation Control ihnual since its initial issuance.

The first of these revisions

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contained the most significant chinges.

The second and third revisions were primarily editorial chances.

Procedures _ effected by the first revision were the-radiatien work permit precedure

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and the procedures for the environmental release of liquic and gaseous radioactivity.

Generally the changes are refine-ents to reflect operating experience. All the procedural changes

were reviewed and approved by the Plant Review Ccemittee and approved by the plant superintendent.

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Equipment Calibration Radiation survey meters are calibrated quarterly or semiannually depending upon the type of instrument.

Calibration is performed

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by the-health physics staff in accordance with approved proce-

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dures.- I&C ' personnel provide assistance for calicration of -

neutron measuring instruments-Records consist of a " Radiation

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. Instruments' Calibration and Lccation" sheet which specifies

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the instruments, serial nt..Mers, locations and calibration due

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' dates.. Instruments are also-tagged with a calibration' sticker'.

A."Radiac Calibration Worksheet" details the results of tne calibration and a copy'of the worksheet is maintained for each calibration performed.

Review of calibration records did not

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. reveal any discrepancies.

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The licensee's actions concerning weaknesses in the radio-chemistry laboratory instrumentation calibraticns and opera-bility testing of the autcmatic isolation valves in the liquid and gaseous waste disenarge systems were examined, problens

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in these areas were identified during the last inspection and

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are described in IE Inspection Report.io. 50-312/75-05,

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paragraphs 3.A and 3.B.

It was observed that complete cali-

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bration entries are now being entered in tr.e labcratory instrumentation calibration log books and tne calitra: ion procedures for the liquid and gaseous effluent monitors nave

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l been formally changed to include specific instructions for

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operability checking of the automatic isolation valve and the N

basin divert valves. The licensee's action on these catters is considered satisfactory.

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E.

Personnel Exposures

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Personnel radiation exposures are measured by TLD badges with TLD service being providcd by Toledyne Isotcpes.

Tieutron measuring devices are available and used when a neutron exposure is expected.

Daily exposure is also measured by pocket dosimeter and results are recorded on the incividual's dosimeter card.

The senior health physics technician reviev.s a'~'s the. weekly dosimeters readings and transfers the readings to (

the individual's Radiation Oosimeter Record which is a tuo N-year record showing weekly, monthly and quarterly dosimeter totals. Monthly TLD reacings are compared to ncnthly cosimeter readings and significant disparities are investicated.

Quarterly TLD readings are transferred to AEC Form 5's which are maintained in indivicual exposure files.

Administrative exposure limits exist and are as follows: above 100 meerA.cek, first line supervisor approval required; above 300 crea/ wack, Chem / Rad Superviser approval required; above 1250 crem/auirter,

. Plant Review Committee approval required.

A 300 mrcm/ quarter exposure limit exists for vendor / contractor personnel witn specific administrative approval necessary to exceed tne limit.

Review of the licensee's 1974 exposure records revealed the highest annual individual expostre to be 175 mrcm beta-i gamma plus 242 mrem neutron.

The highest individual exposure through August,1975 was 1350 mrem.

This exposure occurred completely in August and the licensee's documented investiga-tion of the exposure concluded that it was not real.

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as a conservative measure the PRC decided the exposure should tre assigned to the individual involved.

The next two highest

' exposures were 470 mrem beta-gamma plus 155 mrem neutron and 555 mrem beta-gamma plus 41 mrem neutron.

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O The licens'ee's whole body counting and bioassay program were reviewed. The onsite whole body counter is a unit provided by

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Helgeson Nuclear Services with data analysis being provided by Helgeson.

New plant employees are given a background whole

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body count.

Followup counts are performed whenever a suspicion of internal deposition exists, after a major outage and annually for personnel routinely working on radioactive systems.' Depending upon various availability factors, an

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effort is also made to whole body count vendors / contractors prior to starting work.

A followup count is done if any suspected-internal contamination exists.

Due to the limited operational time to date, follouup counts have been minical.

Review of whole body counts perforced thus far did not reveal any significant internal depositions.

  • It was noted that radiation exposure termination reports-pursusnt to 10 CFR 20.408 for vendor / contractor personnel did not include the.results of whole body counting when sucn counting was performed.

The licer.see stated that the lengthy time period in receiving data analysis results frcm Helgesen had precluded the inclusion of this information in termination reports. The licensee receives prompt notification if a c:unt indicates greater than 10 percent of a MPBB, otherwise rou:ine results are received sometice later.

The licensee stated that Q

they would review this problem and that future termination fV<

reports would include whole body counting information when applicable.

A discussion was held with the licensee concerning tritium bioassay.

It has been the licensee's intention to begin tritium bioassay during the first refueling.

The inspectcr commented that it may be appropriate to begin developing techniques and procedures and familiar 1 zing personnel prict to the first refueling.

The licensee agreed to begin to evaluate these factors but generally does not intend to actually start sampling until the first refueling.

F.

Plant Tour A tour of the auxiliary ~ building was conductec.

One unusual condition was observed on the (-)20 foot level. A segmented portion of that area, containing posted high radiation areas,

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had an activated alarm at one entry while the alarm at a

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second entry to the area was deactivated. The condition did not. involve noncompliance with technical specifications or NRC regulations. The licensee agreed to correct the inconsistency.

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14.

Radwaste Radioactive waste samples were cbtained from the miscellaneous I

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waste tank (liquid) and the "B" gas decay tank for purposes of confirmatory' measurements.

Results of analysis will be reported in

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a future report, Liquid radioactive waste was transferred to a licensed waste disposal company taak truck during the,ccurse of the inspection, however, the operation was not observed oy :he inspectors.

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Unusual Events Four. unusual events-(Hos. 75-5, 75-6, 75-7 and 75-8) had been

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reported since the last inspection, June 16-19, 1975.

The details

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of these events were described in the licensee's letters of July 14, July 15 and August 12, 1975. A licensee letter of Octoter 6, 1975 i

revised the action being taken in response to unusual event No. 75-6.

This inspection confirmed the infermation centained in these letters and that corrective acticns were as described.

The licensee was informed that the four reported unu:ual events constituted noncompliance with Appendix B, Technical specifications but identification r

of the problem by the licensee and initiation of appro:riate corrective

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action and reports negated the need for any NRC enforcement acticn.

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The proposed re-engineering of the waste water systen centioned in the licensee's letter of July 14 concerning event :;o. 75-5 was in

"'s the process of being implemented during the inspection.

The new design of the waste water sy: tem should preclude recurrence of the types of events described in tne four event reports.

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6.

Correction to IE Inspection Report 50-312/75-06 Paragraph 2.B of the Details section of this report mistakenly stated that the monthly releases of radiofodines was in the range of 20-70 mCf.

"20-70 mci" was a typographical error and the quantity should read "20-70 uCi."

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